annual report 2004 - IRSN

Annual Report2004

IRSN missionsResearch and public service missionsDefining and implementing national andinternational research programmesContributing to training in radiation protectionPermanent monitoring in mattersof radiation protectionPublic informationTechnical support and assistancefor public authoritiesTechnical support with regard to nuclear andradiological riskOperational support in the event of a crisisor radiological emergencyContractual services of expert appraisal,research and measurementCarrying out expert appraisals, research andworks for public or private organisations

Annual Report2004News, strategy and organisation

1 and organisationNews, strategy2I R S N ANNUAL REPORT 2004

News, strategy and organisationMonitoringfor protectionI R S N ANNUAL REPORT 20043

Expertise, independenceof judgement andopen-mindednessIRSN’s three prioritiesEmployees were granted a three-year right ofreturn and now at the end of this period morethan 80% of those who worked at IRSN underCEA status have opted for an IRSN contract. Thissuccess shows great support for our Institute’smissions and definitively validates our neworganisation and project.Together,the 1,500 IRSNemployees now share the same priorities and thesame choices: the Institute must show a high levelof scientific and technical expertise;it must ensureindependence of judgement in all circumstances;its open-mindedness towards all those concernedby its missions,the strengthening of relations thusformed and the quality of information circulatedwill make society place its trust in IRSN.Good management and team confidence in theInstitute’s global project are the main keys tosuccess. Having fulfilled the commitments madeby IRSN, the financial year 2004 shows that theInstitute is in good working order.More comprehensivethan previous reports, the 2004 annual reportalso covers the numerous projects carried out.The objectives were achieved. Three significantexamples can be cited:■ the success of the last test carried out in thePHEBUS-FP research programme on the fissionproducts that would result from a core meltdownaccident in a nuclear reactor;■ the acceleration of ENVIRHOM, the researchprogramme dedicated to understanding howhumans and ecosystems react to chronic, longtermexposure to low-level radioactive contamination;■ the record number of dossiers presented to thestanding advisory groups of experts who deal withsafety and radiation protection issues for safetyauthorities.Transparency is a further challenge.The excellenceof IRSN’s research and the quality of its expertassessments are well known. Yet, all scientificassertions deserve to be explained, analysed andcompared. In the same way, an expert assessmentshould not put an end to discussions. It opens thedebate and guides the decision. It should alsohelp to enlighten the public opinion.IRSN’s 2004 annual enquiry into how French peopleperceive nuclear risks met with a great responsefrom the ministries, the media and the public.Thisstudy particularly underlined the trust placed inthe work of scientists and experts. However, theFrench would like to be better informed and moreinvolved when there are decisions to be taken.This demand is particularly directed at IRSN, thepublic expert in nuclear and radiological risks.It must be addressed.IRSN boasts many assets but it must fully acceptits essential choice of opening up to the Europeanand international scientific community. In thefuture, it will be the norm for researchers to4I R S N ANNUAL REPORT 2004

Jacques Repussard,Director GeneralJean-François Lacronique,President of the Boardof DirectorsNews, strategy and organisationexchange ideas and work together on shared projectsregardless of national borders,for knowledge to bepooled and for investments to be shared in themost expensive test facilities and calculation codes.Risk assessment criteria,expert appraisal methodsand safety standards are to be gradually harmonisedwithin the European Union and worldwide.Sarnet,the European network of excellence, dedicated tomodelling serious accidents in nuclear installations,demonstrates this desire to integrate. One couldconsider transposing this example to the field ofradiation protection and radioecology. IRSN has aleading role to play in encouraging the developmentof networks devoted to research and expertise inEurope and beyond, and in exerting a growinginfluence within international scientific bodies.“Institute for RadiologicalProtection and NuclearSafety has a leading role toplay in encouragingthe development ofnetworks devoted toresearch and expertise inEurope and beyond, and inexerting a growinginfluence withininternational scientificbodies.”Jean-François Lacronique,President of the Boardof DirectorsJacques Repussard,Director GeneralI R S N ANNUAL REPORT 20045

Part of IRSN’s expertiseis devoted to national defenceand security issuesIn fact the Institute’s “nuclear defence expertise”covers two distinct areas in which the State isliable to be held directly responsible and forwhich defence secrecy often has to be implemented:• nuclear safety and radiological protection innuclear installations and activities related to nationaldefence, whether of a military or civil nature;• the security,and above all the physical protectionof nuclear materials, installations and transportationnationwide.The corresponding activities,including basic studiesand research,are carried out in a specific operationaldivision, with the support of the entire Institute.Michel Brière,Assistant Director General,in charge of missions related to defenceIn 2004, the framework agreements between theInstitute and State authorities were carefully drawnup.They concern the provision of direct assistance(inspections, operational command of transportations,etc.) or technical support (processingdossiers, preparing exercises, etc.).In the present context when the demand for expertiseis increasing but budgetary resources cannotbe increased, good relations and mutual trustbetween the Institute and State authorities are amajor advantage.As far as activities are concerned,there was a significantincrease in the work due to:• the ongoing modernisation of France’s deterrentforce which is adopting a very strict approach tosafety;• the strengthening of the international fight againstthe proliferation of nuclear weapons (additionalprotocol to IAEA’s safeguard agreement and newEURATOM regulations).Nuclear defence expertise is a specific applicationand,for obvious reasons,does not lend itself to developmenton the national and international markets.Michel Brière,Assistant Director General,in charge of missions related to defence6I R S N ANNUAL REPORT 2004

IRSN missionsIRSN’s articles of association (Decree No. 2002-254 of 22 February 2002) laid down seven missions forthe Institute, relating to radiation protection and nuclear safety. They are organised into three fields:Research and public service missionsDefining and implementing national and international research programmesIRSN defines and conducts research programmes aimed at maintaining and developing the skillsnecessary for expert appraisal in its fields of activity. It either carries them out itself or entruststhem to other French or foreign research institutes.News, strategy and organisationContributing to training in radiation protectionAs a research and expert assessment establishment, IRSN has a duty to contribute to teachingin the areas in which it has competence: nuclear safety and radiation protection. The radiationprotection training courses it organises are directed at professionals working in the health sectorand people exposed to risk in their jobs.Permanent monitoring in matters of radiation protectionIRSN carries out permanent monitoring in matters of radiation protection by assisting inthe radiological monitoring of the environment and by managing and processingdosimetric data on workers exposed to ionising radiation and managing the inventoryof ionising radiation sources.Public informationIRSN informs the public of nuclear and radiological risks via publications, the Internet,a travelling exhibition jointly organised with DGSNR, conferences, etc.Technical support and assistance for public authoritiesTechnical support with regard to nuclear and radiological riskIRSN provides technical support in the field of nuclear and radiological risk to public authoritiesthat so request it. Its scope of intervention includes civil nuclear facilities, secret classifiedinstallations, the transport of radioactive substances, the application of treaties on the control,physical protection and security of industrial and medical applications. In the fields of safety andradiation protection, the Institute carries out tests, research, development experimentations, anddevelops models, codes and safety tools.Operational support in the event of a crisis or radiological emergencyIn the event of an incident or accident involving ionising radiation, IRSN carries out measures ofa technical, health and medical nature for public authorities, in order to ensure the protection ofthe population, workers and the environment, and restore the security of the facilities.Contractual services of expert appraisal, research and measurementCarrying out expert appraisals, research and works for public or private organisationsIRSN carries out contractual services of expert appraisals, research and works – analysis,measurement and dosing – for French, European and universal organisations in the public andprivate sector. In addition, the Institute carries out third-party expertise for ICPE outside the nuclearsector.I R S N ANNUAL REPORT 20047

IRSN in 2004Report and perspectivesIn 2004, IRSN, a public establishment created in 2002, strived to implement all the strategic actions setout by the Director General in 2003.They are based on a system of management through quality aimedat contributing to the efficient running of the Institute. Within this framework and in order to carry outits missions properly, IRSN has started to draw up a contract of objectives between IRSN and the State(2006-2009).As leading public expert, the Institute should make proposals on matters concerning radiation protectionand nuclear safety.A strategy of action, in both research and expertise, is developed through internal andexternal discussions, approved by the establishment’s supervising authorities. IRSN has identified about10 strategic and multidisciplinary programmes corresponding to fields in which the stakes are high andin which the Institute shall have to evolve in the coming years.IRSN’s main lines ofdevelopment in 20041. OPTIMISING SUPPORT MISSIONSFOR PUBLIC AUTHORITIES■ Formalising relationships withpublic authoritiesIn 2004, IRSN signed nine framework agreementswith the administrations to which it providestechnical support (DSND,DGSNR,DRT,DPPR,etc.).Two agreements remain to be drawn up with theauthority in charge of defence-related safety.■ Clarifying operating methods withadministrationsThis involves adapting the “code of practice”drawnup with DGSNR to improve the efficiency of relationsand practices when evaluating the safety of basicnuclear installations.An inventory of current practices was carried outin 2004 with the administrations concerned. Itled to the implementation of working groups incharge of identifying lines of progress whiletaking the constraints of all parties into account.This work will be completed in 2005.■ Implementing public service missionsWithin the limits of the resources allocated to it,IRSN continued setting up a national network forStrategic investment schemeAt the end of 2004, IRSN developedan investment plan of 40 M€ intendedto finance the renewal of equipment.One of its aims is to bring the networkof environmental measurements up tostandard requirements and to make itdenser.It also aims to renew the emergencyvehicles used in crisis situations, the SIPAsimulator, etc.environmental measurements, the SISERI (a databaseon doses received by workers), the sourcesmanagement system, etc.2. REWORKING ITS RESEARCH PROCESSIN CONSULTATION WITH ITS MAIN PARTNERS■ Promoting scientific and technicalexcellenceThe Scientific Board was put together and held itsfirst meeting in 2004. It is in charge of ensuringthe quality of the Institute’s scientific productionin research and expertise: the quality of projects(upstream and downstream) and the quality ofteams and researchers. As well as the Institute’s8I R S N ANNUAL REPORT 2004

internal evaluation tools (audits, commissions,project reviews, etc.), the Scientific Board judgesthe scientific and technical interest of the programmesand their results.Moreover,the Institute wanted to assess the researchprogrammes it conducts with the manufacturers thatuse them and who sometimes contribute financiallyto them. It was with this approach to quality andpertinence that IRSN and EDF decided to organisea discussion seminar on research in 2004.Drawing up the contract of objectiveswith the StateDiscussions on the contract of objectives between IRSNand the State started in January 2004, and involvednumerous internal projects and meetings with thesupervising authorities. Organised around the four mainlines of development set out in 2003, the contract ofobjectives should eventually lead to the strengtheningof the Institute’s position in the field of nuclear andradiological risk control, nationally and internationally,taking into account the expectations of the differentparties involved.News, strategy and organisation3. OPENING UP ITS EXPERTISE TO TAKETHE EXPECTATIONS OF SOCIETY INTO ACCOUNT■ Giving an impulse to pluralist expertiseThe Institute has started to set up groups bringingtogether manufacturers, associations and outsideexperts with which it can discuss the technicalchallenges of complex and controversial subjects.In 2004, the first discussions were held at theBois-Noirs mining site in the Loire department.Thesediscussions could be extended to all mining sites viaa group of pluralist experts.■ Developing the Institute’s activitiesActions have been conducted within the Instituteboth to inform teams (seminars to promoteindustrial awareness) and to formalise the rangeof services provided by the Institute (40 data sheetswere drawn up).Preparing the corporate projectIn September, IRSN organised a forum thatbrought together 200 employees to discuss:“What strategy and actions should beundertaken in the future?” The aim was to getworking groups to build IRSN’s corporateproject for the years ahead – a project thatwould enable it to carry out its public expertmissions for the benefit of society.4. DEVELOPING THE EUROPEAN ANDINTERNATIONAL DIMENSION■ Continuing international researchprogrammesIn 2004, IRSN took the position that the 7th FPRDshould support research on existing reactors anddistinguish between support projects for publicpolicies and projects for manufacturers.■ Adopting common policy in relation toexpert appraisalIRSN,AVN and GRS have started to write commonguidelines on how to evaluate the safety of nuclearfacilities. In 2004, they completed the first chapterdevoted to harmonising the principles applied by thethree organisations.■ Getting involved in internationalorganisationsThe ICRP, whose radiation protection recommendationsform the basis of internationalregulations,renewed its composition in 2004.IRSNis represented within the main commission andwithin four of the five theme-based committees,the most recently created being dedicated toenvironmental protection. This subject is relatedto the strategic programme “Chronic risks”. IRSNalso tries to be present and active in the otherinternational bodies involved in nuclear safety andradiation protection.I R S N ANNUAL REPORT 20049

Main eventsJANUARY■ 8Launching of the TACIS projectwhereby technical support was givento the Ukrainian safety authority inthe analysis of the dossier authorisingstart-up of the Rovno 4 andKhmelnitski 2 VVER 1000 reactors.■ 22The standing advisory group fornuclear reactors examined an IRSNreport on the safety of CABRI, theexperimental reactor, and thepressurised water loop that CEAintends to install in this reactor.■ 31Meeting to summarise the2nd international inter-comparisoncampaign for laboratories thatcalibrate radon measuring instruments(EUROMET, No. 657).FEBRUARY■ 4-5Awareness course on the treatmentof risks related to earthquakes formembers of the standing advisorygroup for nuclear reactors and thestanding advisory group for plants.MARCH■ 3The standing advisory groupof experts on installations intendedfor long-term storage of radioactivewaste examined an ANDRA dossierconcerning the mechanical behaviour ofa possible storage facilityat the Bure site (Meuse).■ 16In-house seminar on scientificand technical excellence held atthe Le Vésinet site (Yvelines).■ 16-19Participation in the Medec trade fairfor the medical world.■ 18Creation of Sarnet, a Europeannetwork of excellence devotedto research on severe accidents,organised by IRSN.■ 23IRSN organised a seminar devoted to“concerted approaches”. This seminarassembled about a hundred playersfrom society (industrialists, operators,experts, administrations, unions,associations, CLI and ANCLI) witha view to improving concerted actionaround high-risk industrial sites.■ 24■ ANCLI and IRSN organised a seminarto describe the main lines of theircooperation following an enquirypreviously carried out with CLI.■ The standing advisory group ofexperts on installations intended forlong-term storage of radioactive wasteand the standing advisory groupin charge of the basic nuclearinstallations other than nuclearreactors examined an EDF dossierconcerning the dismantling of firstgenerationreactors (Saint-Laurentdes-Eaux– Loir-et-Cher andBugey – Ain).■ 26The HFD from the Ministry ofIndustry signed two agreementsconcerning IRSN’s technical assistancein the implementation of theconvention prohibiting chemicalweapons and the regulations onthe protection and control of materials.■ 29■ Jacques Repussard presented thesupervisory authorities with thestakeholders’ committed approach,particularly through the pilotinitiatives in pluralist expertise.■ The framework agreement wherebyIRSN provides technical assistanceand support to DSND was signed.APRIL■ 20The CD-Rom “Information on nuclearrisk and how it is managed” was sentto prefectures and EDF nuclear powerplant CLIs.■ 28■ The Reactor Safety Commissionexamined an IRSN report onthe security systems of Barracuda,the future nuclear attack submarine.■ Renewal of Cofrac accreditationsfor IRSN metrology laboratories.■ The TACIS RF/TS/39 contract forSEC/NRS (Russian safety authority)started up with the participationof IRSN, GRS and APAT. It covers:evaluation of the procedure toauthorise storage of radon-typewaste, writing of a safety reportplanning guide for the safety of waste10I R S N ANNUAL REPORT 2004

News, strategy and organisationstorage and evaluation of the safetyreport on the creation of a newstorage facility that could in the longterm (fifty years) become a surfacewaste disposal site at the SerguievPosad site located in the north ofthe Moscow region.MAY■ 24-28■ An IRSN expert chaired the meetingon social aspects and public involvementin radiation protection at the IRPAcongress in Madrid.■ A contract was signed with SNCF,involving a study of workstations withregard to nine types of transportedradioactive materials.■ The “Kursk 1 safety report review”project was completed and the resultswere presented to the Safety ReviewGroup (EBRD).JUNE■ 4The agreement with DGSNR wassigned – it describes the conditionsunder which IRSN provides technicalsupport to DGSNR and the methodsused to launch and conduct thetechnical support actions.■ 8The standing advisory groupof experts on installationsintended for long-term storage ofradioactive waste examinedan ANDRA dossier concerningthe geo-chemical phenomenagoverning the release andtransportation of radionuclidesin a deep geological disposalat the Bure site (Meuse).■ 9■ The standing advisory group fornuclear reactors examined EDF’smethod of taking aspects related tohuman factors into account whenmodifying installations.■ Seminar summarising the REP-Naprogramme: assessment of the first10 tests of the CABRI REP-Naprogramme and unansweredquestions that will be addressed inthe next CABRI-water loop programme.■ 10-11Organisation of the final seminar ofthe OECD MASCA international projecton the behaviour of corium at tankbottom.■ 14A Eurosafe seminar was held inCologne (Germany) on knowledgemanagement in institutes that conductresearch and expertise in nuclearsafety.■ 18The agreement with DPPR was signed:it describes the conditions underwhich IRSN provides technicalsupport to DPPR and the methodsused to launch and conduct thetechnical support actions.■ 23-25IRSN gave its first training course on“radon metrology” as part of itsradiation protection training mission.JULY■ 1The standing advisory group onnuclear reactors examined certainaspects related to the safety of theEPR (command-control, radiationprotection, containment building, etc.).■ 6Members of IRSN’s Scientific Boardwere appointed.■ 8■ Presentation of IRSN’s radiationprotection action plan (Maison del’Amérique latine, Paris).■ The national inventory of uraniummining sites put together by IRSN waspublished (from the end of theSecond World War to May 2001).■ A seminar on waste was organised inHavana (Cuba) by CPRH, IRSN, CSN,SSI – six Central American countriestook part.AUGUST■ Signing of a cooperation agreementwith CEREGE (European Centrefor Research and Education inEnvironmental Geosciences) on thepaleoseismic programme in Provence.■ The cooperation agreement withthe Ukraine on the Chernobylexperimental platform projectwas renewed for four years.SEPTEMBER■ 6-10IRSN organised the second EcoradConference aimed at taking stock of theI R S N ANNUAL REPORT 200411

Main eventsknowledge that enables us to assess howradioactivity impacts the environment.■ 20-21IRSN in-house forum – “What strategyand actions should be undertaken inthe future?”■ 22Signing of a BfS/NRPB/IRSN tripartiteagreement concerning dosimetricassistance (biological analyses) inthe event of a crisis.■ 22-23■ Organisation of an SFRP day onexposure to natural radioactivity dueto human activities.■ A report on the radiologicalconsequences of flooding inthe Petite Camargue in December2003 was given to the PACA andLanguedoc-Roussillon DRASS,the Bouches-du-Rhône, Vaucluse andGard DDASS, the DSND, the DGSNR,the Gard CLI, the DPPR and the PACADRIRE.OCTOBER■ 1-2IRSN participation in the Journéesfrançaises de radiologie(French Radiology Congress).■ 4-6IRSN Thesis Presentation 2004 in Aussois.■ 5-6IRSN, GRS and ICC organiseda seminar in Kiev at which FGI(Franco-German Chernobyl Initiative)results were presented.■ 6■ The PHARE contract with theLithuanian safety authority came toan end and another contract wassigned with this same authority andwith the European Commission,concerning the dismantling ofthe Ignalina power plant.■ The Reactor Safety Commissionexamined an IRSN report on thesecurity baseline of Barracuda,the future nuclear attack submarine.■ 14■ The agreement with DDSC wassigned – it describes the conditionsunder which IRSN provides technicalsupport to DDSC and the methodsused to launch and conduct thetechnical support actions.■ The standing advisory group forreactors and its German counterpart(RSK) met to discuss the recommendationson the safety of nuclear powerreactors issued in 2003 and 2004.■ The Safety Assessment Guide,a document common to IRSN,GRS and AVN, was circulated.■ 19A crisis situation exercise involving anuclear material inventory wasconducted at the CERCA and Orphéefacilities.NOVEMBER■ 8-9IRSN and GRS organised the 6th EurosafeForum in Berlin (Germany) basedon nuclear safety experiencefeedback.■ 15IRSN’s Scientific Board held its firstmeeting.■ 18■ The Phebus FPT3 test wasconducted. It was the fifth and lasttest in the PHEBUS FP programme.■ The standing advisory group fornuclear reactors examined certainaspects related to the safety ofthe EPR (corium recuperator, safetyinjection system, boron dilutionaccidents, etc.).■ 19A round table was organised todiscuss the role expert assessmentorganisations had to play regardingnuclear transparency. About10 players from various fields took part(journalists, CLIs, associations, experts).■ 25The standing advisory group fornuclear reactors examined theexperience feedback on the use of fuelduring the period 1996-2002.■ 30■ The standing advisory group in chargeof facilities intended for long-termstorage of radioactive waste examinedANDRA’s “Granite 2002” dossier.■ Riskaudit signed a contract toprovide Bulgaria with technicalassistance to reinforce the controlof radioactive sources.■ 30/11-3/12Participation in the Pollutec trade fairin Lyon.12I R S N ANNUAL REPORT 2004

News, strategy and organisation■ 2DECEMBER■ The standing advisory groupon nuclear reactors examined experiencefeedback on the use of French andforeign pressurised water reactorsduring the 2000-2002 period (1st session).■ Contracts were signed with CEAto operate the CABRI and PHEBUSreactors, to conduct tests in theseinstallations and to bring the CABRIinstallation up to standard.3The cooperation frameworkagreement with INRS was signed:it specifically concerns the transferof knowledge from one organisationto the other, the pooling of scientifictools, joint research and expertise,professional training and expertassessment of workstation risks.■ 6A cooperation agreement was signedwith ANVAR to promote technologicaltransfer and make the most of IRSN’spotential for innovation anddevelopment.■ 12Tripartite agreement between IRSN,EDF and CEA relating to the SOURCE TERMEVALUATIONS research programme,whose purpose is to reduce uncertaintieson the evaluation of releases fromradioactive products in the event ofan accident involving core meltdownof a pressurised-water reactor.■ 14The Reactor Safety Commissionexamined an IRSN report oninteractions between the weaponsystem of Barracuda, the future nuclearattack submarine, and the safety ofthe nuclear boiler room.■ 14-22Meetings between the federal atomicenergy agency (Rosatom), NIKIMT,IBRAE and ERC of Saint Petersburg(Russia) and IRSN as part of the crisismanagement cooperation.■ 15The standing advisory group for basicnuclear installations other thannuclear reactors examined theconditions for dismantling Super-Phenix.■16The standing advisory group fornuclear reactors was presentedwith different subjects concerningmeasures taken or envisaged by EDFwith regard to core meltdownaccidents that could affect PWRpower plants.■ 21■ As new website was launchedwhere the analysis results ofradioactivity in aquatic environmentscan be consulted.■ The report specifying radonmeasurement protocols in spafacilities was sent to DGSNRand put on the Internet.■ A study on the origin and future ofradioactivity resulting from medicalactivities and found in Toulouse’swaste-water system was presented tothe Compagnie Générale des Eaux deToulouse (water company), theToulouse hospital, the local DRASS,DRIRE, DDASS and DSNR.■ The DPPRA was sent a report onfood chain contamination by fissionproducts released during nuclearweapon testing.■ 22The standing advisory groupfor nuclear reactors examinedthe specifications on modificationsenvisaged by EDF on the cloggingof sumps in safety injection andcontainment spray systems,in the event of an accidentalbreak in the primary system of a PWR..I R S N ANNUAL REPORT 200413

OrganisationA short description of IRSN■ CreationIRSN was created by article 5 of the law of9 May 2001 instituting the French healthand environmental safety agency and bythe implementing decree of 22 February 2002.■ StatusIRSN is a public establishment of an industrialand commercial nature placed under the jointauthority of the Ministries of Defence,the Environment and Sustainable Development,Industry, Research, Health and Social Affairs.■ DirectorsJean-François LACRONIQUE, Presidentof the Board of Directors.Jacques REPUSSARD, Director General.Michel BRIÈRE, Assistant Director Generalin charge of IRSN missions related to defence.Philippe JAMET, Assistant General Directorin charge of general matters.■ Expertise and researchIRSN is the public expert in research andexpertise related to nuclear and radiologicalrisks.■ Fields of activity• Environment and response.• Radiation protection of persons.• Prevention of major accidents.• Reactor safety.• Safety of plants, laboratories, transportand waste.• Defence nuclear expertise.■ 4 main lines of development• Optimising support missions for publicauthorities.• Reworking its research process in consultationwith its main partners.• Opening up its expertise to takethe expectations of society into account.• Developing the European and internationaldimension.■ 2004 budgetReceipts of 254 M€, expenditure of 276 M€,of which 16 M€ went into investments.■ StaffIRSN employs about 1,500 specialists –engineers, researchers, physicians, agronomists,veterinarians and technicians, expertscompetent in nuclear safety and radiationprotection and in the control of sensitivenuclear materials.■ IRSN sitesHead office: ClamartAgen, Cadarache, Fontenay-aux-Roses,La Seyne-sur-Mer, Le Vésinet,Les Angles/Avignon, Mahina (Tahiti),Octeville/Cherbourg, Orsay, Pierrelatte, Saclay.14I R S N ANNUAL REPORT 2004

Activity 2004Key figuresNews, strategy and organisationRESEARCH50%of the IRSN budgetdevoted to researchactivities172publicationsin scientific journals,with review committeesINTERNATIONALACTIVITIES100bilateral agreementswith research andexpertise bodiesfrom 30 countries80international projectsin progress2004 budgetExpenditure:Operating 94%Investment 6%StateMEDD 99%Others 1%FranceTECHNICAL SUPPORTFOR PUBLIC AUTHORITIES608technical reportsto the public authorities(excluding defencerelatedactivities)HUMAN RESOURCES1,515peopleemployed by IRSNor seconded to theInstitute from CEA272noticestransmitted to safetyauthorities for defencerelatedactivitiesIRSN’S INTELLECTUALASSETS16French patentsin force (one of whichis co-owned by CEA)and 20 patents in forceabroadOrigin of funding:State 81%France 16%Foreign 3%EDF 30%COGEMA 7%DGSNR 7%CEA 5%Others 51%Foreign158Software applicationsand databases listed,24 of which are co-ownedby CEACCE 25%RISKAUDIT 24%GRS 12%EPRI 8%NRC 7%Others 24%I R S N ANNUAL REPORT 200415

The Board of Directorson 31 December 2004Through its deliberations, the Board of Directors decides upon the organisation and running of IRSN. It monitors the programmesof activities and when results of the work carried out are known, it decides upon the follow-up. From a financial point of view,it approves the annual statement of estimated revenue and expenditure, the amendments and the allocation of results.It examines the general terms and conditions for formalising agreements and contracts. It approves acquisitions and sales ofindustrial property rights, acquisitions or sales of shareholding and large-scale real-estate projects. It checks on the generalconditions of human resource management (recruitment, employment, remuneration).The Board of Directors is made up of 24 members: 10 appointed representatives of the State, 6 qualified figures chosenfor their competence, including either a member of parliament or a senator from the Parliamentary Office for evaluationof scientific and technological options, 8 elected representatives from the establishment’s staff. The term of office formembers of the Board of Directors is five years.■ COMPOSITIONPresident: Jean-François LACRONIQUE■ STATE REPRESENTATIVESPatrick AUDEBERTManager of the national mission supporting the nuclear risk management,representing the Minister for Civil Security.Jean-Denis COMBREXELLEDirector of Labour Relations, representing the Minister for Employment.Marie-Claude DUPUISDirector of the Industrial Environment Department, Department forthe Prevention of Pollution and Hazards, representing the Minister forthe Environment and Sustainable Development.Florence FOUQUETBranch manager of the nuclear industry, General Directorate for Energyand Raw Materials, representing the Minister for Industry.Bernard FROISDirector of the Power, Transport, Environment, Natural ResourcesDepartment from the Technologies Department, representingthe Minister for Research.Marcel JURIEN de la GRAVIÈREDelegate for nuclear safety and radiation protection for activities andinstallations related to defence.André-Claude LACOSTEGeneral Director of nuclear safety and radiation protection.Thierry MICHELONDeputy Director of environmental risk management, General Directoratefor Health, representing the Minister for Health and Social Affairs.Marc PREVÔTEngineer General, shipbuilding armaments Inspector, representingthe Minister of Defence.Nicolas VANNIEUWENHUYZEOffice Manager, Budget Department, representing the Minister forthe Budget until 30 June when he is resigning – successor has not yetbeen appointed.■ QUALIFIED FIGURESClaude BIRRAUXVice-President of the Parliamentary Office for scientific and technological choices.Dominique GOUTTEDirector of the major heavy ion accelerator, at the instigation ofthe Minister for Research.Jean-François LACRONIQUEProfessor of Medicine, at the instigation of the Minister of Health andSocial Affairs.Maurice LAURENTFormer department head at the National Assembly, at the instigation ofthe Minister of Industry.Jean RANNOUAir Force General, at the instigation of the Minister of Defence.Jacques VERNIERMayor of Douai, at the instigation of the Minister for the Environmentand Sustainable Development until April 2004 when he is resigning –a successor has not yet been appointed.■ FIGURES PRESENT BY RIGHTThierry TROUVÉGovernment Commissioner and Director for the prevention of pollutionand risks.Daniel RACINETState Controller.Jacques REPUSSARDDirector General.Jean-Claude DALEAccountant.Marie-Catherine POIRIERSecretary of the Works Committee.■ SALARIED BOARD DIRECTORSCFDT representativesFrançois ROLLINGER, Dominique MARTINEAU, Thierry FLEURYCFE-CGC representativesHervé BOLL, Jean-Marc DORMANTCGT representativesMireille ARNAUD, Xavier MOYA, Betty CATANIA16I R S N ANNUAL REPORT 2004

The Scientific Boardon 31 December 2004The Scientific Board examines the Institute’s programmes of activities and gives its opinion. It checks upon the pertinenceand follow-up of research programmes defined by IRSN. It assesses their results. It can make recommendationson the directions of the establishment’s programmes.The Scientific Board can be consulted by the President of the IRSN Board of Directors or by the supervising Ministers.The IRSN Scientific Board was formed on 6 July 2004, by a joint order from the Minister of the Environment andSustainable Development, the Minister of Health and Social Safety, the Minister of Defence, the Minister in chargeof Industry and the Minister in charge of Research.News, strategy and organisation■ COMPOSITIONPresident: Michel QUINTARDDirector of Research at the Toulouse Institute of Fluid Mechanics,at the instigation of the Minister in charge of Research.Bernard SEVESTREEngineer General, Assistant Director of the French Atomic EnergyCommission, at the instigation of the Minister in charge of Defence.Martin SCHLUMBERGERProfessor of Medicine and Clinical Director at the Gustave-Roussy Institut,at the instigation of the Minister in charge of Defence.Ethel-Esther MOUSTACCHIScientific Director for the Atomic Energy High Commissioner,at the instigation of the Minister in charge of the Environment.Victor TESCHENDORFFHead of Department at the Gesellschaft für Anlagen und Reaktorsicherheit(GRS / Germany), at the instigation of the Minister in chargeof the Environment.André AURENGOProfessor of Medicine and Clinical Director at the Pitié-SalpêtrièreHospital, at the instigation of the Minister in charge of Health.Jean-Marc COSSETProfessor of Medicine and Clinical Director at the Curie Institut,at the instigation of the Minister in charge of Health.George YADIGAROGLUProfessor of nuclear engineering at the Swiss Federal Instituteof Technology, at the instigation of the Minister in charge of Industry.André PINEAUProfessor at the École des Mines in Paris, at the instigation of the Ministerin charge of Industry.Philippe LECONTEPhysicist and former Director of the research programme on managementof radioactive waste at the CEA, at the instigation of the Minister incharge of Research.René AMALBERTIProfessor of Medicine and Clinical Director at the Institute of AerospaceMedicine, at the instigation of the Minister in charge of Employment.Lars-Erik HOLMProfessor of Medicine and Director General of the Swedish RadiationProtection Authority, at the instigation of the Minister in chargeof Employment.I R S N ANNUAL REPORT 200417

Organisation chartApril 2005BOARD OF DIRECTORSJean-François LACRONIQUE, PresidentGENERAL DIRECTORATEJacques REPUSSARD, Director GeneralMichel BRIÈRE, Assistant Director General in charge of IRSN missions related to defencePhilippe JAMET, Assistant General Director in charge of general mattersOPERATIONAL DEPARTMENTS■ Department for Nuclear Defence ExpertiseJérôme JOLY, Director• Application of international controls• Technical support and studies• Defence safety assessment• Nuclear facility security■ Department for the Environment and ResponseDidier CHAMPION, Director• Study of radionuclide behaviour in ecosystems• Studying and monitoring radioactivity in the environment• Analysis of geosphere-related risks• Sample processing and metrology for the environment• Radiation Protection response and assistance• Emergency situations and crisis organisation■ Department for the Prevention of Major AccidentsMichel SCHWARZ, Director• Studies and experimental research on accidents• Experimental engineering and instrumentation• Fuel studies and modelling in accidents• Fire, corium and confinement studies and modelling■ Department for the Radiation Protection of PersonsPatrick GOURMELON, Director• Radiation protection studies and expertise• Radiobiology and epidemiology• External dosimetry• Internal dosimetry■ Department for Reactor SafetyMartial JOREL, Director• Pressurised-water reactors• Gas-cooled, fast-neutron and experimental reactors• Equipment and structures• Systems and risks• Thermohydraulics, cores and control of facilities• Severe accidents and radiological consequences• Human factors■ Department for the Safety of Plants, Laboratories,Transport and WasteThierry CHARLES, Director• Fuel cycle transportation and installation• Laboratories, irradiators, accelerators and decommissioned reactors• Radioactive waste• Confinement, fire and industrial risks• Criticality• Aerodispersion of pollutantsFUNCTIONAL DEPARTMENTS■ Department for Strategy, Developmentand External RelationsJean-Christophe NIEL * , Director• Strategic programmes• Relations with institutional partners• Management tools and follow-up of strategic objectives• Study and research programmes• International relations• Policies and syntheses• Promoting and supporting operations• Relations with stakeholders• Secretariat for standing advisory groups• Risk management■ Department for Scientific and TechnicalEvaluation and QualityJoseph LEWI, Director• Radiation Protection training• Scientific evaluation and activities• Quality Management• Health, Safety and Environmental protection• Scientific and technical knowledge engineering• Scientific information resources■ Communication DepartmentMarie-Pierre BIGOT, Director• Internal communications• Information and relations with the media• Programmes and relations with the public■ General secretariatJean-Baptiste PINTON, General secretary• Financial matters• Human resources• Commercial relations and legal support• Managing real-estate holdings and corporate services• Managing information systems■ Accounting OfficeJean-Claude DALE, Accountant* No longer working for IRSN at the time of publication of the report.18I R S N ANNUAL REPORT 2004

IRSN sites:Activities and staffNews, strategy and organisationOCTEVILLE – CHERBOURGStaff: 16 employees■ EnvironmentLE VÉSINETStaff: 161 employees■ Environment and response■ Radiation protection of personsCLAMART(Head office)Staff: 220 employeesFunctional departmentsFONTENAY-AUX-ROSESStaff: 749 employeesOperational activities■ Defence nuclear expertise ■ Environment and response■ Radiation protection of persons ■ Reactor safety■ Safety of plants, laboratories, transport and wasteSACLAYStaff: 51 employees■ Safety of plants, laboratories,transport and wasteORSAYStaff: 17 employees■ EnvironmentAGENStaff: 3 employees■ Environment and responsePIERRELATTEStaff: 21 employees■ Response■ Radiation protection of personsLES ANGLES – AVIGNONStaff: 25 employees■ Response■ Safety of plants, laboratories,transport and wasteCADARACHEStaff: 328 employees■ Environment■ Prevention of major accidents■ Radiation protection of persons■ Defence nuclear expertiseMAHINA - TAHITIStaff: 3 employees■ EnvironmentLA SEYNE-SUR-MERStaff: 5 employees■ Environment> Details of IRSN sites can be found on the flap at the back of the report.I R S N ANNUAL REPORT 200419

Activities in 2004Knowledgefor predictionI R S N ANNUAL REPORT 200421

Description of programmesTo optimise the manner in which it carries out its assigned missions, IRSN organises its activities into a rangeof subject-related programmes. Some of these are termed strategic, as they are either cross-disciplinary, aresponse to the priority challenges of the Institute or mobilise resources and teams around a common objective.IRSN programmes are structured around six targets.Civilian nuclear expertiseHuman and organisational reliabilityThis programme covers all IRSN activities on thesubjects of human reliability and organisationalanalysis in nuclear installations or other situationsinvolving exposure to ionising radiation.It also meets the growing demand from the safetyand radiation protection authorities and takesaccount of the changes associated with the ageingof operating teams, changes in skill levels, etc.Analysis of the safety of PWRand other operational reactorsIRSN carries out in-service monitoring in supportof the authorities of EDF nuclear power plantsand other reactors being operated for experimentalpurposes.It examines the information arising fromthe use of these reactors, identifies and prioritisessafety problems and prepares reports based on thefeedback. IRSN also analyses the safety dossierssubmitted by users in accordance with the regulations.Support for the safety assessmentof operational reactorsIRSN carries out studies and research actions tooptimise support for the public authorities in respectof safety for current and future installations. IRSNactivities divide into three fields:the developmentof probabilistic safety studies, the carrying out ofstudies in support of analysis and the acquisitionand/or development of software and calculationcodes with the associated research.PWR ageingThe ageing of nuclear power plants results indeterioration of components which needs to beprevented, monitored and counteracted to ensurethat the installation can continue to operate undersatisfactory safety conditions.The research carried out by IRSN covers variousaspects of the problem:ageing of components,studyof the containment behaviour and non-destructivetesting.The fuel and its managementduring normal and accidentoperating conditionsFor economic reasons, EDF is seeking to extendthe useful life of fuel and is turning towards newmaterials.For these new operating conditions,IRSNactivity involves:■ for expertise, the relevance of current safetycriteria or the definition of new criteria and anassessment of the associated safety margins;■ for research, improvements in knowledge.22I R S N ANNUAL REPORT 2004

Future reactors and innovative projectsBy around 2010, this programme should provideIRSN with an appropriate and considered positionon the most credible projects being consideredfor the replacement of current generations ofnuclear power plants.The programme is targetingGeneration IV reactors, with a view to achievingimprovements in safety, reductions in waste andresistance to proliferation and malicious acts.Severe reactor accidentsIRSN studies and research carried out on coremeltdownaccidents in a water reactor (severeaccidents) aim to gain a sufficient understandingof the phenomena to be able to understand therisks associated with these accidents and theprocedures adopted by the operator in responseto them.The aim is to improve prevention of suchaccidents,to identify the resources needed to limittheir consequences and to prepare IRSN for themanagement of the crisis should an accident occur.Safety of plants, transportand dismantlingThis programme is intended to contribute to safetyof plants,transport and dismantling by identifyingareas for safety improvements,where appropriate.It includes:■ assessment of safety in plants,other installationsand transport;■ management of the national inventory of “civil”radiation sources;■ research and studies into the risk of criticality,especially during transport;■ expert assessment activity at an internationallevel and for at-risk non-nuclear installations.Defence nuclear expertiseSafety of installations, systemsand transportIRSN provides technical support to governmentauthorities for the safety assessment of militarynuclear systems, secret basic nuclear installationsand defence-related transport systems. Activitiesconcentrate on the expert assessment of safetydocuments, analysis of operating experience,assessment of internal emergency plans as well aspreparations for the crisis organisation.Material protection and monitoringIRSN activities on this subject concern, on theone hand,the level of protection for nuclear materialagainst the threat of theft or hijacking with maliciousintent and, on the other hand, the respectfor France’s international commitments on the useof material that could serve in the manufacture ofnuclear and chemical weapons.In this context, the Institute provides directtechnical support to the public authorities (nationalinspections, accompanying internationalinspections,missions of an operational nature) andalso technical support to the administrativeauthorities (expert assessment of dossiers,contribution to the development of doctrines andregulations).Protection of installationsand transport against malicious actsThis programme aims to take account of maliciousacts during the design and operation of nuclearI R S N ANNUAL REPORT 200423

installations. It also addresses the assessment ofpotential consequences resulting from maliciousacts against transport containers for nuclear orradioactive materials.Protection of persons and the environmentagainst ionising radiationEnvironmental monitoringThe aim of this programme is to be able to determine,at any time, the radioactivity levels to whichpopulations are being subjected, to determine itsorigin and to provide early warning of any abnormalrise in ambient radiation fields in the various environments.Waste management safetyActivities under this field aim to understand therisks associated with radioactive waste and toidentify, where necessary, the options available toimprove its management from the point of view ofsafety and radiation protection. Activities underthis programme relate to:■ an understanding of unused matter and material,waste and packages;■ the storage and disposal of radioactive wasteregardless of its origin, activity levels or the radionuclidesinvolved;■ the management of used sources;■ polluted sites.These activities involve an assessment of operators’dossiers, the development of technical doctrinesas well as studies and research to help understandthose events that might affect the storage safety.Chronic risksThis programme contributes to the assessment ofthe effects of chronic exposure to radioactive contaminants.Althoughrisks are low for a given individual,they apply to vast human populations and immenseecosystems,which may give rise to significant consequences,especiallyat a collective level.Refining theirassessment may therefore offer advantages whenconsidering health or environmental management.RadioecologyThe research and studies carried out within IRSNare contributing to knowledge and understandingof the origin and future of radionuclides dischargedor pre-existing in the environment.The aim is to assesstheir radiological impact under normal operating,incident or accident conditions.Operationally,thisinvolves making contingency plans using aids-todecisiontools, the prediction of releases and theirmovement, reinstatement of the immediate andremote environment of an incident site, etc.RadonFor more than twenty years,IRSN has been studyingradon in all its aspects: formation and migrationin the ground, exhalation then dispersion in theatmosphere,metrology,cartography,accumulationin buildings,health risks,reductions in concentrations,etc.The knowledge and experience acquired, whichhas no equivalent in France, enables IRSN to offersupport to the public authorities engaged in a riskmanagementpolicy associated with radon and tothose tasked with implementing it.24I R S N ANNUAL REPORT 2004

Radiation protection of workersThe ultimate aim of the programme is to identifythe most critical situations and to analyse themeans to reduce exposure. This programmecombines IRSN activity relating to exposure(internal and external) of workers in nuclearinstallations, other installations and workstationsthat result in exposure to ionising radiation.Radiation protectionin the medical fieldMedical exposures represent the main sourceof exposure of the population to ionisingradiation of artificial origin. These exposuresmay present risks for practitioners exposed in arepeated manner and for patients also exposedrepeatedly. This IRSN programme is divided intothree areas:■ medical expert assessment;■ epidemiology of medical exposures;■ research into delayed complications in patientstreated with radiotherapy.Exposure assessmentand protection equipmentThis programme aims to improve understandingof people’s exposure in normal situations and tocarry out dosimetric expert assessments undercomplex situations, in several areas:■ radiation protection and epidemiological expertassessments of populations;■ dosimetry, routine measurement devices;■ dosimetry,measurement devices under development.Radiation protection doctrineRadiation protection doctrine is developed at aninternational level by a range of authorities thatmay be scientific,technical or regulatory in nature(ICRP, AEN, IAEA, Euratom, etc.).This programme,based on the involvement of IRSNexperts within these authorities, aims to developthe doctrine,introduce new subjects to study withinthese authorities and build a dialogue with all theFrench players concerned with radiation protection.Hazards and crisis situationsFire, explosion and dispersionThis programme covers IRSN activities in the fieldof control of risks associated with fire,explosion andaerodispersion of radioactive or toxic contaminantswithin the facilities or into the environment. Thestudies, research and expert assessments underthis programme aim to improve installation safetylevels and hence provide better protection for thepublic, workers and the environment.Naturally-occurring hazardsActivities carried out by IRSN aim to assess thesafety of installations against naturally-occurringhazards (earthquakes and floods), and to identify,where applicable, prospects for improvement.This programme addresses:■ expert assessments of the risks of flooding andsevere drops in water level that could affect nuclearinstallations;■ an understanding of the phenomena that governthe morphological and geological changes at sites;■ the development, optimisation and validationof methods and tools enabling an assessment ofthe seismic hazard.I R S N ANNUAL REPORT 200425

Management of emergencysituations, risk managementIRSN ensures that its resources (EmergencyResponse Centre,mobile means) remain operationaland are improved to be able to provide assistanceto the public authorities following an accident orpost-accident situation in France. IRSN preparescontingency plans and takes part in crisis exercises.This activity offers training to its teams in interactionwith other players in the crisis, the coordinationof exercises at national level and the preparationof both national and international contingencyplans.Feedback,in this field,is a vital factor in achievingprogress.This programme has two parts:■ studies and development, crisis exercises;■ ensuring that the Emergency Response Centre andmobile means remain operational.Managementof post-accident situationsPost-accident management of a nuclear or radiologicalcrisis may involve a large number of playersrequired to undertake the long-term managementof many interdependent facets: radiological protectionand health monitoring of populations,reinstatement of territory,redeployment of industrialand agricultural activities,compensation for victims,etc.This programme aims to put in place an organisation,methods, and a range of technical tools, aswell as a network of external contacts, to enableall the partners to carry out their missions effectively.Radiation accidentsFollowing an accidental exposure to ionisingradiation, medical teams must be able, in as shorta time as possible, to assess the injuries sufferedby the irradiated individual in order to be able toestablish an appropriate treatment protocol. Theaim of IRSN, as provider of technical support tothe hospital structures,is to improve the diagnosisby taking full advantage of the interface betweendosimetry, biological research and medicalapplications.Radiation protection responseand assistanceThis programme covers:■ activities involving checks, tests and expertassessments of the effectiveness of ventilation andfiltration systems in nuclear installations;■ assistance and response in operational radiationprotection, to characterise the radiological stateof the premises or sites, and contribute to themanagement of abnormal situations;■ monitoring activities in accordance with thedecree relating to the protection of workers againsthazards rising from ionising radiation.These activities are carried out under conventionswith the public authorities.26I R S N ANNUAL REPORT 2004

Education, distributionCommunicationAs part of its missions, the Institute contributesto informing the public and public authorities aboutnuclear safety and protection of persons and theenvironment. It publishes the scientific results ofits study and research programmes.Training and educationthrough researchEducation activities enable the Institute’s knowledgebase to be formalised, enhanced and taught. Thisinvolves the setting up of external or internal courses,participation in external training and providing supportfor theses and courses. In addition, the IRSN’spolicy of scientific and technical excellence aimsto achieve the highest possible level of scientificand technical merit across all its research and expertassessment activities and recognition of thisexcellence.International assistance, supportfor programmes and agreementsThe Institute’s international activities involve:■ bilateral relations with foreign opposite numbers;■ relations with international organisations;■ special involvement in relations with Europeaninstitutions;■ support activities for foreign safety authorities;■ contributions to the international activities ofthe French safety authorities.Investments: updatingof the CABRI reactorThe updating of the CABRI reactor involvesimproving the earthquake protection of the buildingsand equipment,modernising the ventilationsystem and installing a pressurised water loopreplacing the sodium loop. Once completed, thisinstallation will be used to reproduce, under theCIP international programme,the thermohydraulicconditions of a PWR during a reactivity accident.AMANDEThis new installation will generate metrologystandardmonoenergetic neutron beams, neededfor the study and characterisation of neutrondetectors for radiation protection purposes. TheAMANDE project will now provide support for thereference installations already operated by IRSNand will enable it to have primary referencescomparable to those in the major internationalmetrology laboratories.I R S N ANNUAL REPORT 200427

14%share of external jointfunding receiptsfor research programmes6,200source movementsrecordedin 200438,000environmental samplestaken annually283personnel attended IRSNradiation protectiontraining689,038“hits” on the IRSN website28I R S N ANNUAL REPORT 2004

IRSN ACTIVITIES IN 2004Research and publicservice missionsIn order to be able to offer relevant expert appraisal, IRSN develops its ownresearch programmes. For the Institute, this involves anticipating future questionson changes to and control over the risks of nuclear activities and developing newresearch topics on the accidents and crisis management where IRSN providessupport to the public authorities. The Institute’s public service missions also coverradiation protection monitoring, contributing to training on radiation protectionmatters as well as public information.> 30 Defining and implementing national and internationalresearch programmes> 78 Contributing to training in radiation protection> 81 Permanent monitoring in matters of radiationprotection> 84 Public informationI R S N ANNUAL REPORT 200429

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESAssessment of programmed systems.Defining and implementingnational and international researchprogrammesThe research activities carried out by IRSN have several objectives: applied research, not excluding basicresearch, research in support of expert assessment, a complementarity between experimentation, modellingand interpretation. Research programmes developed by the Institute give priority to national and internationalcollaboration by welcoming PhD students, developing programmes in partnership and the creation of mixedresearch units.Support for the safety assessmentof operational reactors63current theses16post-doctoratesper year37holders of seniordoctorates or authorisedto supervise research349communicationsin congresses26ICPEunder theEnvironmental CodeIRSN carries out research and developmentactivities into non-destructivetesting methods and the assessmentof research into programmed systems.These activities are in support of itsexpert assessment work.Non-destructive testingThe equipment testing using ultrasound and eddycurrent techniques is mainly aimed at:■ developing new methods for demonstrationpurposes, such as the use of multi-element ultrasoundsensors that can be adapted in real time tothe complex forms of components. This work isaimed at showing the feasibility and advantagesof these methods prior to their industrialisation;■ developing simulation software for these methodsthat will enable their performance to be predictedand hence achieve improvements in their industrialusability.The year 2004 was dedicated to demonstratingthe correct operation of flexible sensors on largegrainor cracked materials.Assessment of programmed systemsThe power of computers enables designers toproduce increasingly complex software. It istherefore becoming increasingly difficult to validateits design. IRSN is constantly striving to improveits methods and tools for assessing programmedsystems.On the subject of the analysis of coverageof validation tests, IRSN commissioned thedevelopment of the GATEL tool by CEA.The resultsof this activity have been used in particular toanalyse the EPR-reactor protection system in 2004.The systems that EDF plans to use for this reactorare also multi-task and therefore introduce anadditional complexity factor: in 2004, IRSN beganthe study of a tool to check the design rules andsynchronisation properties for multi-task softwarethat will facilitate the detection of unsafe behavioursduring the analyses of such systems.30I R S N ANNUAL REPORT 2004

Power plant at Nogent-sur-Seine (Aube).Reactor vessel head at the Civaux power plant(Vienne).Research into the ageing of PWRIRSN launched an experimentalprogramme in 2003 to gain furtherknowledge on the subject of stresscorrosion of alloys used for the weldingof reactor vessel heads.The stress cracking of nickel-based alloys in reactorsled EDF to replace, in particular, some reactorvessel heads on French nuclear power plants. Therecent discovery of cracks in Sweden (on reactorvessel nozzles),in Japan (dissimilar metal junctionson the pressuriser) and in the United States (reactorvessel penetrations) shows that inspections forcracking should be carried out on filler metalsas well as on parent metals. It was in this contextthat IRSN began an experimental programmeto assess cracking speeds on Inconel 82 in CEA’sVenus loop in 2003.This programme, which is dueto end in 2007, produced its first results in 2004.These results will be compared with those fromother international experimental programmes.They will enable the Institute to use data acquiredcompletely independently from operators andmanufacturers when conducting its investigations.14nuclear activitiesauthorised under thePublic Health Code8current Europeanprojects on radiationprotection and safetyHosting of38foreign scientistsThe fuel and its management duringnormal and accident operating conditionsThe fuel behaviour has been the subjectof major research work at IRSN,mainlyconcerned with the control rod ejectionaccident as well as the loss of primarycoolant accidents and dewatering ofspent fuel pits.Control rod ejection accidentThe study of the behaviour of fuel following thecontrol rod ejection accident is primarily basedon experimental programmes (CABRI programmes,analytical tests) and simulations (SCANAIR softwarefor rod thermo-mechanical calculations).Experimental programmesIn 2004, IRSN led the way in seeking to interpretthe REP-Na tests carried out between 1992 and2002 in the sodium loop of the CABRI installationand to define the tests of the CIP (CABRI InternationalProject) which will be carried out using a newpressurised water loop currently under construction(see text on p. 32).For the REP-Na tests, the detailed interpretation ofthe REP Na-12 test (MOX rod irradiated at 65 GWj/t,Zircaloy-cladded) enabled confirmation of itsrepresentativity with respect to the case of a powerreactor up to a maximum fuel enthalpy value of80 cal/g.This test, which did not cause a failure in the rod, alsoenabled the qualification of the SCANAIR softwareto be extended.For the CABRI-CIP programme,the studies carriedout enabled the conclusion to be drawn that thetest loop was representative of power reactors.The first qualification test (CIP Q) of the test series,which should be completed by 2010, will aim toconfirm the absence of artefacts associated withthe new test facility and to study the physicalI R S N ANNUAL REPORT 200431

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESEnvironment of the CABRI experimental reactor.phenomena arising after significant heating ofthe clad (that could not be simulated in the sodiumloop). Development of the test matrix of the CIPprogramme was pursued and was the subject ofdetailed design studies. As a complement to thisprogramme, IRSN is examining the possibility ofusing the Japanese NSRR-reactor for the study ofthe behaviour of fission gases present in the irradiatedfuel during temperature transients.SimulationIRSN has continued to develop the SCANAIR calculationcode, for use in preparing and interpretingthe CABRI tests and their transposition to the scaleof nuclear reactors. This software models thebehaviour of a fuel rod subject to a power transient.The main development introduced into theSCANAIR software in 2004 was a model to assessthe probability of fuel rod sheath failure duringsuch a transient,calling on tools from elastoplasticfailure mechanics.This model exploits a statisticalanalysis of mechanical test results on irradiatedfuel clads in order to derive a (probabilistic) relationshipbetween the size of defects and the rod burnup.MODELLING OF IRRADIATED FUEL BEHAVIOUR IN A REACTIVITYINSERTION ACCIDENT (RIA)FOCUSThe study into the behaviour of irradiated fuel rods following an RIA needs to cover:■ changes in the fuel microstructure (morphology, local heterogeneities in the fuel pellets and the cladding), resulting fromthe radiation effects;■ local effects (pellet-clad interaction, etc.).One of the major difficulties of accident simulation lies here in the coexistence of very different scales: the micron formicrostructures (hydrides in the clads, inter-granular bubbles of fission gases in the pellets) and the metre for rod height.To resolve these difficulties, it was clear that very advanced models had to be developed. By using scale change methods,these models determine the behaviour of a given microstructure, then introduce the result into a more general digitalrepresentation of the structures, such as that used inthe SCANAIR calculation code.It was mainly in the context of two theses, jointly funded withEDF, that these methods were the subject of major developmentsduring 2004 with, for example, the development of anelastoplastic behaviour law for hydrided Zircaloy.Thanks to their general character, the models developed can easilybe applied to different situations (changes to fuel design, changesto operating conditions, other fuel types), demonstratingthe advantages of this development for industrial applications.SCANAIR software specialists.32I R S N ANNUAL REPORT 2004

Storage tank for CABRI installation test devices.A model that is representative of heat exchangesbetween the clads and the coolant was alsodeveloped, validated and incorporated in thesoftware.Its originality lies in the fact that it coversall heat exchange regimes for very rapid heating(of the order of 3,000 °C/s to 10,000 °C/s),includingfollowing a DNB.Version 4 of the SCANAIR software, incorporatingthese latest developments,was transferred to EDF,which is partly funding these developments aspart of the CEA-EDF-IRSN tripartite research agreement.In addition, the detailed modelling work onirradiated fuel (see Focus p. 32) was continued.Models will be prepared on this basis to enhancefuture versions of SCANAIR.In terms of applications,IRSN has used the SCANAIRsoftware to define test conditions for the futureCABRI water loop and has carried out studiessupporting expert assessments into dossiers forfuel development programmes or for fuel managementwithin the reactor, submitted by EDF. Forexample, this software is used by IRSN to assessthe soundness of one of the criteria (clad temperature)proposed by EDF to ensure fuel containmentduring a reactivity insertion accident (RIA).quenching, etc.). IRSN has, in particular, carriedout a study into whether it would be useful todevelop an advanced accident calculation tool withthe associated R&D, in order to model thesephenomena in detail.This feasibility study enabledthe prioritisation of needs and will serve as a basisfor the development of a specification for this tool.IRSN has also undertaken the definition of a multiyearstudy programme concerning accidentsinvolving dewatering of irradiated fuel assembliesduring handling or in the storage pits (power reactorsand spent fuel processing plants). Design of thisprogramme has been mainly based on exploratorycalculations,carried out using the ICARE-CATHAREcalculation code,using the example of a dewateringin a spent fuel storage pit of a 900 MWe reactor.Loss of primary coolant accidentand dewatering of spent fuel pitsThe criteria associated with the loss of primarycoolant accident, mainly aimed at ensuring thatthe reactor core would remain “coolable” duringthis transient, may be called into question bychanges in fuel management (increases in burnupfraction) or new designs of fuel rods. Much workhas been done on the phenomena that come intoplay (expansion/failure, oxidation, resistance toI R S N ANNUAL REPORT 200433

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESStorage tank for CABRI installation test devices.Modifications to the CABRI installationIn order to enable testing underthermohydraulic conditions that arerepresentative of a water reactor,IRSN is jointly funding the fittingof a pressurised water loop in theinstallation to replace the sodium loop,previously used for the study of fuelin fast neutron reactors.The research programmes carried out in theCABRI research reactor of CEA (Cadarache,Bouchesdu-Rhône)on the behaviour of highly irradiatedfuels enables experimental data to be gatheredon the effects of an increase in burnup fraction forthese fuels.The work of installing the water loop is accompaniedby an upgrade to the safety standard of theinstallation.There are also plans to refurbish certainequipment. In parallel, IRSN is developing aninstrumented test device intended to be fitted withthe sections of irradiatedrod that are being tested.The international CABRICIP programme currentlybeing prepared in thefuture installation shouldinclude 12 tests startingbetween the end of 2008and the beginning of2009, at an average rateTeam S2IE for CABRI and PHEBUS, from theexperimental programmes support engineeringof three or four tests perdepartment at Cadarache (Bouches-du-Rhône). year. The modificationsto the installation have been submitted to publicenquiry and have been the subject of a preliminarysafety report that has been forwarded to DGNSR(see Focus p. 96).Progress madeThe year 2004 has been set aside for the cleaningupof the installation, the dismantlement of theold systems, and the packaging and removal ofthe equipment associated with the use of thesodium loop. The reactivity injection system hasbeen dismantled with a view to optimising it, andthe pit equipment of the CABRI reactor has beenremoved with the intention of reinforcing thepile block in 2005, to ensure its resistance toearthquakes. At the end of 2004, the installationwas ready to receive the first components of theloop.Progress in the studiesThe geometry of the test device has been decided,and the corresponding instrumentation has beenqualified.In parallel, technical specifications for keycomponents of the future installation have beenwritten (reactivity injection system,equipment formonitoring fuel ejected during a test, device forcoating the rod for post-test examination, etc.).The national and international partners on theplanned experimental programme met twice during2004 to define in detail the test matrix.34I R S N ANNUAL REPORT 2004

ASTEC software team.The SARNET co-ordinator flanked by two collaborators.Research work into severe accidentswith core meltdownThe study and research programmecarried out by the Institute in the fieldof core meltdown accidents is centredon the primary physical fields identifiedfrom accident scenarios and theoptions for limiting consequences.The approach adopted in this programme is basedon the establishment of accident scenarios, theidentification of physico-chemical phenomena,the carrying out of experiments on discrete effectsto determine the basic data and to develop elementarymathematical models,and writing calculationcodes bringing together these models and data,as well as qualifying them using more generalexperiments.2004, birth of the EuropeanSARNET networkThe scale of the human, technical and financialresources to be used to examine in depth thequestions relating to severe accidents and theadvantages of sharing acquired knowledgeencouraged the Institute to seek national andinternational partners. The European network ofexcellence SARNET, set up as part of the EuropeanCommission’s 6th FPRD is an example of this.This network began its work on 2 April 2004.Coordinated by IRSN, it unites 49 organisationsfrom 18 European nations involved in nuclear reactorsafety research (safety institutes, universities,industry, etc.).This network aims to:■ better coordinate European research capabilitieson core meltdown accidents;■ contribute to reducing the lack of knowledge inthis field by carrying out appropriate joint researchprogrammes;■ incorporate the latest knowledge in advancedcomputer systems for the assessment of electronuclearreactor safety in Europe, especially in thefield of probabilistic safety studies;■ disseminate information and train new expertsin this field.The following were achieved in 2004:■ the development and deployment of the communicationsplatform via Internet ACT. This gives accessto all information relating to the life of the network(documents, announcements of events, seminars ormeetings, etc.); it enables the collection of opinions(discussion forums, questionnaires, etc.) and thecreation of joint documents. It gives access to theASTEC software and to the network’s experimentaldatabase;■ the distribution in June 2004 of version V1.1 ofthe ASTEC software to 25 partner organisations onthe occasion of the session organised by IRSN toprovide training in its use. A qualification matrixand an assessment matrix for the software has beendefined and the corresponding work has been initiated;I R S N ANNUAL REPORT 200435

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESIntermezzo furnace for the BECARRE tests.SOURCE TERM PROGRAMME■ the start of information exchanges betweenpartners. Several circles of experts have been setup and more than a dozen working meetings havebeen organised with the aim of developing commonpositions on the phenomenology of severe accidents:their modelling,methods of assessing their consequencesand priority requirements in research terms;■ the structuring of the DATANET experimentaldatabase configured according to the technicalsolution developed by the Joint research centre inISPRA. This consists of a network of databasesdeveloped by certain European organisations atdifferent sites to which access is available overthe Internet.FOCUSIn 2004, IRSN initiated a new programme, called SOURCE TERM, whose aim is to reduce uncertaintiesconcerning the assessment of the release of radioactive products into the environment followinga core meltdown accident in a water reactor.Amongst these effluent releases called “Source Term”, iodine and ruthenium are the radioactive products that presentthe greatest risk to exposed populations. The studies, carried out under “Source Term” over more than twenty years, along withan analysis of tests of the PHEBUS-FP programme, have shown that significant uncertainties remained (for example a factorof 10 on organic iodine concentrations in the containment, as this chemical form of iodine is virtually not retained, for exampleby the sand filter following a controlled depressurisation of the containment).In 2004, in conjunction with its primary partners CEA and EDF, IRSN prepared a document describing the planned programmefor the period 2005-2010 with estimates of its multi-year cost. The various IRSN experimental areas of the programme havemade progress at a technical level: thus the EPICUR programme on the formation of organic iodine under gamma radiationcontinued with the completion of the experimental device, and the scientific and technical strategy of the CHIP programmeon the chemistry of non-equilibrium iodine was determined.The first item under the SOURCE TERM programme will concern the chemistry of iodine in the primary cooling system (CHIP)and in the containment (EPICUR). In the primary system, special attention will be paid to non-equilibrium chemistry (CHIP).The second item will concern the sequence of a severe accident involving degradation of boron carbide (B 4 C) control rods thatequip the most recent French reactors as well as the boiling-water reactors in service in Europe (BECARRE tests).The third item will address the consequences of a degradation of fuel elements in contact with air following penetration ofthe vessel after the meltdown of part of the reactor core or the dewatering of a spent fuel storage pit, especially the releaseand chemical behaviour of ruthenium (tests of release of fission products in the CEA’s VERDON facility and tests under EPICUR).In addition, correct prediction of the sequence of a dewatering in a spent fuel storage pit requires a better knowledge of theoxidation of clads by air (MOZART tests).The fourth item will address the release of fission products from the fuel. A microanalysis programme on irradiated fuel andon fuel that has been subjected to release tests (VERCORS) will enable a validation of the current interpretation of releasesmeasured during tests already carried out. As a complement to this, it is planned to carry out three supplementary releasetests in the CEA’s VERDON facility using MOX and UO 2 fuel at high-burnup fractions.36I R S N ANNUAL REPORT 2004

What is a severe accident?Fitting the test section in the Intermezzo furnace.IRSN is continuing the joint development of theASTEC software with its German counterpart GRS,with the aim of making it the European referencesoftware for severe accidents.Public information relating to the network isavailable on website www.sar-net.org that openedat the beginning of 2005.Studies and research into severeaccidents carried out in 2004Core degradation and behaviour of the coriumin tankThis phase of the accident is studied using theICARE/CATHARE software developed by IRSN.Version V1 was used as part of the PSA to examinebreaches of the primary cooling system inducedby core meltdown and was used to interpret theresults of the German QUENCH tests carried outusing boron carbide control rods.Version V2 that enables the bi-dimensional calculationof core material thermohydraulics andmotions was delivered in 2004.The behaviour of fission productsInvestigations on fission products have beendominated in recent years by the internationalPHEBUS-FP programme.The final test of the series,FPT-3, was carried out in 2004 (see Focus p. 38).Discussions were held on the way forward forresearch into the behaviour of fission products inan accident situation with core meltdown. Theseresulted in IRSN creating a new programme,entitledSOURCE TERM,whose aim is to reduce uncertaintiesconcerning the assessment of radioactive productsreleased into the environment.The year 2004 wasdedicated to identifying requirements,establishingthe programme’s priorities, defining its technicalcontent and assessing the associated timescalesand costs (see Focus p. 36).A severe accident originates from a core water coolingfailure that prevents the power generated by the reactorfrom being evacuated, even after the shutdown of thechain reaction (so-called “residual power”).Over a period of between one and several hours, a seriesof human or equipment failings can lead to deterioration ofthe fuel and its melting. Complex phenomena then occur,whose impact depends on the initial conditions of the accidentand the actions of the operators. The accident may be describedin four major phases:■ under the effect of residual power, the fuels present in thereactor core lose their integrity, releasing hydrogen followingoxidation by water vapour of the clads surrounding the fuel andemitting fission products into the containment;■ if water is no longer injected into the vessel, the core melts andthe mass of molten material thus formed (called corium) startsattacking the base of the vessel and then penetrating it. Duringthis advanced stage of degradation, a vapour explosion mayoccur; the containment may also be affected by the effects ofthe hydrogen present (deflagration and/or detonation).The reactor structures may also be subject to the effects ofa vapour explosion resulting from a water/corium interactionbefore and after the penetration of the tank.In the particular case of a penetration, ejection of corium maylead to direct heating of the atmosphere in the containment;■ under the effect of the heat released by the corium, the concretebasemat of the reactor pit under the vessel may suffer thermaldegradation that could lead to the release of a range of gasesthat, when added to the water vapour already generated, wouldlead to a progressive rise in pressure within the containment;■ some of the fission products emitted during the first phase(mainly noble gases, iodine and caesium) may escapethe containment either because of its leakage rate or as the resultof deliberate actions of the operators.Such an accident may thus lead to a major release of radioactivereleases (1) into the environment.(1) Such releases are still called “SOURCE TERMS”.I R S N ANNUAL REPORT 200437

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESPHEBUS reactor: dry storage area for test devices.FPT-3: FINAL TEST UNDER THE PHEBUS-FP PROGRAMMEFOCUSThe PHEBUS-FP programme involved a total of five reduced scale (1/5000) overall experiments,which have studied the release of fission products and of structural materials during the meltdown of an irradiated rodassembly, followed by the transport of these products into the primary cooling system, as well as their behaviour inthe containment, under thermohydraulic and physico-chemical conditions that are representative of a severe accident.The results obtained are serving to qualify the ASTEC and ICARE-CATHARE software programs.The fifth test in the programme was completed successfully on 18 November 2004. Its aim was to verify, within an overall test,that the calculation codes used for safety studies correctly simulated the degradation mechanisms of a water reactor coreequipped with boron carbide control rods and the associated “source term”.The core was simulated by an assembly of 20 UO 2 rods (18 irradiated and 2 non-irradiated and instrumented) surroundinga boron carbide (B 4 C) rod cooled by a weak flow of water vapour representative of that following a core meltdown accident.The increase in power in the assembly provokes a thermal runaway in the clad oxidation reaction, the failure of the B 4 C rodand its oxidation.This generates hydrogen, boric acid, as well as carbonated gases that could have a significant impact on the chemistry of fissionproducts, especially on the chemical forms of iodine present in the containment. These gas emissions were detected on line.The power was then increased until movement of the fuel was observed following its liquefaction leading to the shutdownof the test in accordance with predetermined criteria.The fission products and structural material released into the system simulating the PWR primary cooling system and intothe tank simulating the containment were measured. On line spectrometry measurements and sampling of the vapoursand aerosols were carried out. In the containment, the experiment continued for four days, to examine the behaviour of fissionproducts, and especially that of gaseous iodine.A brief and rapid analysis of the measurements made during theFPT-3 test, as well as the initial non-destructive tests of the fuelassembly, suggested that the presence of a boron carbide controlrod significantly affected the fuel degradation.PHEBUS reactor control room during the test at Cadarache(Bouches-du-Rhône) on 18 November 2004.It also suggested that the liquid mixtures resulting from the controlrod degradation accelerated the dissolution of the fuel. High levelsof oxidation of the boron carbide under severe accident conditionswere also observed.Of course, all this remains to be confirmed.Several partners in the PHEBUS programme (IRSN, GRS, PSI) have alsoalready carried out calculations to derive results from the test.38I R S N ANNUAL REPORT 2004

A PHEBUStest in figures■ About 60 people participatedin the test.■ Duration of the test: fivehours for the fuel degradationthen four days monitoringthe behaviour of the fissionproducts.■ Between five and six years toanalyse the data and interpretthe test.The proposed programme will be jointly fundedand executed under the IRSN-EDF-CEA tripartiteframework. It already has support, internationally,from the European Commission and the USNRC.Containment resistanceConcerning hydrogen explosions, IRSN hascontinued the development and qualification ofits calculation tools,including the TONUS software.This has led to its participation in ISP 47 and thecarrying-out of a highly instrumented combustiontest programme, in collaboration with CNRS inOrléans.TONUS was also qualified using the results of theTOSQAN programme for the distribution ofhydrogen in the pressure vessel (see Focus p. 39).IRSN has also carried out RECI analytical experimentswith a view to assessing the effect of catalytichydrogen recombiners on the forms of iodinepresent in the containment. In 2004, these experimentsenabled conversion rates for caesium andcadmium iodides into gaseous iodine to bedetermined.The Institute also carried out a series of studies insupport of the sizing analysis for recombiners inP’4 reactors (1,300 MWe).Concerning the risks of vapour explosions, and aspart of the SERENA operation of the OECD-NEA,IRSN carried out studies into corium/waterinteractions in the vessel and the vessel sump aswell as a major programme of work comparingthe models of the various software routines usedby partners in this activity.Assessments were alsoAnalysis of containment strength.TOSQAN PROGRAMMEThe year 2004 has seen the completion of the “watervapour condensation” test phase of the TOSQANprogramme and its interpretation.A detailed analysis of all the results of these tests was also carriedout. This examined in particular the influence of numerousparameters included in the condensation models in the thermohydrauliccodes for the containment, with a view to identifying limits andsensitivity to the physical parameters measured. These models,generally developed from laboratory experiments, were thus validatedat a more industrial scale. Additional investigations remain to becarried out in the case of stratified atmospheres.Spray tests started during 2004 after initial calculations had beencompleted. A reference test was carried out whose results contributedto the development of an international comparative exercise. Specificspray tests were carried out in parallel to qualify an innovativenon-intrusive optical measurement technique for the temperatureof droplets entitled “overall rainbow refractometry”, developed aspart of a thesis. This technique was coupled to other opticalmethods such as spontaneous Raman diffusion spectrometry,PIV and an imaging technique enabling the measurement of vapourfractions and the speed and size of droplets. The results obtainedenabled the carrying out of general and local analyses ofthe interactions between spray droplets and the air/vapour mix,illustrating the phenomena of condensation on droplets andof evaporation.Apparatus for laser measurements using a newtechnique: rainbow refractometry.FOCUSI R S N ANNUAL REPORT 200439

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESVisual inspection of a fuel assembly at the Romans plant (Drôme).carried out on the risk of loss of containment integrityfor a 900 MWe reactor by the floor movements thatcould resultin an explosion of vapour outside the tank.The experimental programme on direct heatingof the atmosphere of the vessel of a P’4 reactor,carried out in collaboration with FZK in the DISCOinstallation, continued with the carrying out of aseries of low temperature tests and the first hightemperature tests.Safety of plants, transport and dismantlingResearch and studies carried out byIRSN relating to the safety of plants,transport and dismantling mainlyconcern the risks of criticality andthe dispersion of radioactive materialoutside the containment buildings.Studies and research into criticalityThe risk of criticality,i.e.,the unintentional initiationof a chain neutron reaction, exists at all stages ofthe fuel cycle, from uranium enrichment intouranium 235, fuel storage and transport, enhancementof material derived from spent fuelreprocessing through, to the storage of wastegenerated. The prevention of this risk involvesdetermining the conditions that make it possibleto ensure sub-criticality during these operations.It is also essential to know the consequences thatmay arise from a criticality accident.In these fields,the Institute carries out studies and research todevelop advanced calculation tools with the highestpossible level of qualification.The studies that enable an assessment of the riskof criticality call on calculation codes that usenuclear data libraries (cross sections). Thesecodes must be able to resolve neutron problemsthat differ widely one from another because ofthe diversity of fissile environments encounteredand the geometry of the devices that contain them.Under the CRISTAL project (see Focus p. 41), theInstitute developed a multi-group simulationprogram for three-dimensional neutron transport,entitled MORET 4. In 2004, this program was thesubject of new developments to its algorithms forthe physical,mathematical and statistical models.International publications and numerous organisationsstressed the power of this software,particularlywell adapted to the requirements of criticalitystudies.The use of simulation software based on the Monte-Carlo method remains suspect for the calculationof specific situations within which non-groupedfissile materials interact. IRSN has contributed toimprovements in these calculation methods byparticipating in the working group coordinated bythe OECD-NEA; thesis studies were undertaken toreduce the uncertainties and bias of simulationcalculations used to assess the risks of criticalityby improving the statistical methods used. IRSNalso continued,in 2004,to improve all its criticalitycalculation tools in terms of modelling capabilityfor complex systems and the detailed analysis ofcalculation results, to gain a better understandingof safety margins.The qualification of calculation codes is obtainedby comparing data calculated using these codeswith experimental data. Experimental criticalitystudies are therefore carried out under national40I R S N ANNUAL REPORT 2004

Illustration of modelling techniques forcriticality studies.or international partnerships. These involve thecreation of full-scale configurations with knownchemical,geometrical and neutron characteristics,very close to the critical state.These experimentsare then reproduced by calculation. Comparisonsbetween calculations and experiments enableany deviations or bias to be detected and quantified,and the security margins to be incorporated incriticality studies can then be determined.Thus in2004,the Institute completed the development ofthe “Fission products” experimental programmeunder a PIC with COGEMA. This experimentalprogramme was set up in 1995 and included morethan 170 critical experiments, the last of which,carried out in April 2004, aimed at representing arealistic situation of the dissolution of irradiateduranium oxide PWR rods.At the end of 2004, IRSNcarried out an experimental programme enablingthe very accurate measurement of changes in thecriticality properties of plutonium as a functionof its ageing in the criticality laboratory of the CEAat Valduc (Côte-d’Or).IRSN also considered the setting up of the followingprogrammes:■ Pu TEMPERATURE EFFECT programme, intendedto measure experimentally the effects oftemperature on low concentration plutoniumsolutions where the overall effect of temperaturecould become positive;■ STRUCTURAL MATERIALS programme, designedfor the qualification of neutron characteristics ofthe component elements of structural materials(steel, concrete, PVC, etc.);■ programme for the experimental qualification ofconfigurations using low moderated MOX fissileenvironments.The Institute has also continued its activeparticipation in the ICSBEP international project.Under the aegis of OECD/NEA,this project enablesthe sharing of criticality experiments carried outthroughout the world and the acquisition of highquality experimental data, for use in qualifyingcalculation tools.A criticality accident results in the release of energy,CRISTAL V1.0: NEW VERSION OFTHE CRISTAL PACKAGEFOCUSThe new version V1.0 of the CRISTAL package has beenoperational since November 2004.This package, which is made up of a set of calculation codes, nucleardata libraries and calculation procedures, enables the executionof all types of calculations needed to analyse criticality risks innuclear installations – excluding reactors – and the transportcontainers for radioactive materials. It was developed and validatedunder collaboration between IRSN, which manages the project,CEA and COGEMA.This new version is a response to the need to calculate, withoutexcessive conservatism, the criticality of transport containers, spentfuel storage and processing installations, while retaining an envelopeapproach to safety studies. To achieve this, the CRISTAL user hassoftware, nuclear data and interfaces that enable the calculationof the abundance of the main radionuclides present in spent fuel.These calculations are carried out by the CESAR software developedby CEA and COGEMA, for different types of fuel taking accountof the manner in which they were irradiated in the reactor andcooled in the spent fuel pit.The CRISTAL package was validated by comparison betweencalculations and experiments. At the end of 2004, 1,300 criticalexperiments had been modelled and calculated using CRISTAL;these included 230 that were representative of spent fuel, somewith fission products, which represents a unique step forwardin the world.I R S N ANNUAL REPORT 200441

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESSTARMANIA test bench at Saclay (Essonne).In transport configurationIn storage configurationY60.430.20.0-30.2-60.4Spent fuel pit: storage error-364.0 -291.2 -218.4Scale 3:26.96 - Cross section 2 = 0.0STORAGETRANSPORT-145.6 -72.8 0.0 72.8 145.6 218.4 291.2 364.0Illustration of modelling techniques for criticality studies.ZOOMessentially in the form of heat, accompanied byintense emissions of neutron and gamma radiation.In 2004, the Institute carried out studies intocriticality accidents for transport containers toassess the consequences and options for response.Collaboration was initiated on these subjectswith Imperial College, which provides technicalsupport to the UK safety agency.Radionuclide dispersionIn support of expert assessments of the risks ofdispersion of radioactive or toxic material outsidethe containment buildings,IRSN carries out studiesand experiments corresponding to a range ofpossible accident situations.In order to be able to carry out more realisticXassessments of radionuclide releases, work wasundertaken to improve understanding of thetransfers of gases and fine particles. The resultsobtained in the context of aeraulic tests in air oncracked concrete slabs (for example following anearthquake) enabled the development of a flowlaw through the cracks that is more appropriatethan existing models. The work is continuing toaddress air/vapour mixtures and the retention ofaerosols.Full scale experiments in the STARMANIA installationenabled the gathering of data on the aeraulicand mechanical behaviour of equipment used toisolate for fire protection purposes (doors andfirewall valves) when subject to pressure andtemperature conditions that are representativeof a fire in a confined area.Modelling was carried out, aimed at determiningthe effectiveness of high-efficiency filters installedin series. The corresponding calculation modelswill be the subject of experimental validation.Work was also carried out on the effectiveness ofzeolith trapping for certain gases.In 2004, a programme was launched to enhanceknowledge of the influence of wind effects onaccidental releases, in the case of a partial or totalfailure of an installation’s ventilation.This programmeincludes the carrying out of wind tunnel testson models that are representative of nuclearinstallations.42I R S N ANNUAL REPORT 2004

Dry boring in a gallery of an experimentaltunnel at Tournemire (Aveyron).Waste-related research activityIn the field of waste,IRSN concentratedits efforts in 2004 on the managementof high-level long-lived waste (HLLLW),in the light of the upcoming parliamentarymeeting under the law ofDecember 1991.Storage in clay strataThe work was primarily concerned with the storageof HLLLW in a deep geological clay stratum. Theyincluded the development of digital models andtheir validation by laboratory or field tests.To carry out these experiments on geologicalstorage, IRSN has access to an old railway tunnelcut through a thick clay (shale) strata in Tournemire(Aveyron). The similarities between the shale atTournemire and the rocks at the ANDRA laboratoryin Bure (Meuse) enable IRSN to carry out bothmethodological and phenomenological studies.The study of the containment properties of shalewas started by identifying and characterising fissuresand an analysis of the interstitial solutions containedin the pores of the material. The chemical andisotopic analysis of fluids collected from thesefissures enables their origin and their residencetime within the massif to be identified. The verylow water content of the shales made it necessaryto develop a methodology intended to minimiseany effect on the interstitial solutions duringsampling.There was in fact evidence that extractionconditions did affect the isotopic composition ofthese fluids.Characterisation of zones disruptedby excavationExcavation usually disrupts the rocky massif leadingto an increase in permeability in the area of theworkings.This disrupted or damaged zone (termedEDZ: Excavation Disturbed Zone) may vary overtime as the galleries are ventilated and the shalesflow.In 2004, under the DECOVALEX internationalproject,IRSN began an exercise in modelling of theEDZ around the Tournemire tunnels. This projectwill continue to 2006 and will incorporate acomparison between modelling results and in situcharacteristics.Changes over the longer term couldbe studied under this exercise as the Tournemiresite has tunnels of very different ages (one year,eight years and a hundred and ten years).A campaign of characterization of the EDZ bymaking radial drillings around the tunnels atTournemire was set up to obtain the most completeset of data possible to form a basis for the modellingexercises. The data collected will enable betterunderstanding of propagation in space and timein the disturbed zone. Drillings will enablemeasurement of the zone’s permeability andchanges in the propagation speed of ultrasonicwaves.Measurements,especially of water contentand porosity,carried out on the core samples takenduring drillings,will complete the characterisationof the zone.A test termed “mine-by-test” (tunnelling intoinstrumented rock to monitor the hydro-mechanicalI R S N ANNUAL REPORT 200443

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESInstrumentation used to monitor changes in the rock after drilling.INNOVATIONS IN THE MELODIE SOFTWAREThe MELODIE software for modelling the transferof radionuclides in geological formations benefitedfrom two major advances in 2004:■ the first enables the simulation of radionuclide transportphenomena by convection and diffusion in heterogeneous geologicalenvironments, thanks to a calculation scheme using finite volumes;■ the second, taking advantage of a new, advanced, multi-processorarchitecture, concerns the parallelisation of the resolution oftransport equations.These changes offer major advantages for the overall modelling ofa repository site and the assessment of dose impact in case a packageis released.IRSN is responsible for the developmentand updating of the MELODIE software.FOCUSreaction),undertaken as part of the European projectNF-PRO (6th FPRD),enabled,in 2004,the obtainingof measurements of displacement, deformationand interstitial pressure. Programs for theinterpretation and digital simulation of the reactionof rock to tunnelling have been developed.Modelling of the behaviourof a storage siteStudies have been carried out with a view todescribing the thermal, mechanical and chemicalbehaviour of a radioactive waste storage site,takinginto account the disturbances caused by theimplementation and the progressive deteriorationof the various constituent materials.These studies have mainly involved:■ modelling the geochemical interactions associatedwith the introduction of oxidising water into theCallovo-Oxfordian shales, as well as the presenceof large quantities of concrete,to assess the degreeand extent of the corresponding perturbations;■ developing hydro-mechanical models of thebehaviour of shale/bentonite and shale/cementinterfaces to be able to quantify the possible roleof these interfaces in the performance of a seal;■ modelling the behaviour of an anchor keystonefor a tunnel seal to assess the advantages anddisadvantages of such a device in preventing flowacross the fractured zone around the excavations;■ completing the development of a delayed failuremodel of the fracture zone around the excavationsin the shales, to estimate the possible long-termbehaviour of this zone;44I R S N ANNUAL REPORT 2004

Packaging and reference marking of clay coresample taken at Tournemire (Aveyron).■ modelling the thermal changes in a chambercontaining exothermic waste to identify the keyparameters affecting the intensity and extent ofheat flow in and around the packages.The results of IRSN studies into the alkalisation ofshales by cement and the long-term mechanicalbehaviour of damaged shales have been publishedin peer-reviewed publications.IRSN also carried out studies in 2004 on:■ the hydro-geological modelling of the Paris basin,and especially the Bure site, by incorporating intoits model a new set of data and especially thoserelating to salt concentrations in deep aquifers;■ the development of a modelling approach forstorage structures in a geological environment, toidentify the complementarity of storage barriersin order to confine released activity as close aspossible to the packages. This study has been thesubject of a European research project (BENIPAproject) and is continuing under the Franco-Germanproject REGIME (IRSN/GRS);■ the development of a water transport program,including the possibility of change of phase(liquid/gas).As for the development of the MELODIE software,which offers risk estimation for waste storage,2004 marked a major development in the digitalmethods used, as well as in the strategy implementedto estimate the dose impact of a repository(see Focus p. 44).I R S N ANNUAL REPORT 200445

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESVentilation system at the DIVA experimentalinstallation at Cadarache (Bouches-du-Rhône).Incorporation of human factorsin the design processesIn 2004,the Institute continued the research startedin 2003 on the incorporation of human factors inthe design processes.This involved identifying theimpact of the various decisions taken during thedesign on the future operators’ work, and thenstudying the way in which this impact is taken intoaccount in the development of the project team’sdecisions.Three modification processes for SEVESOclassified installations were thus analysed.The Institute also reviewed expert assessmentscarried out in the human factors and organisationalfields over the last fifteen years. This involvedprimarily surveying the subjects analysed(supervisory interfaces, operating instructions,maintenance organisation, incident analysis), aswell as the approaches adopted (ergonomics,sociology, management, etc.).Research activity in the fireand aerodispersion fieldsIRSN research into fire encompassesthe sequence and consequences of fire,its propagation and the circulation ofsmoke to other premises via openingsor the ventilation system.The purpose of the research into the aerodispersionof pollutants is to develop the ability to containradioactive or toxic materials and to reduceuncertainties in the assessment of the normal oraccidental releases of pollutants and of theirdispersion,especially with a view to understandingthe consequences for man and the environment.Research programmesThe experimental approach offers, among otherthings,the opportunity to extend knowledge aboutthe specific physico-chemical phenomena of firesand to supplement the database needed to developand then validate models related to the variousphenomena resulting from fires in a confinedventilatedarea.These models are then introducedinto the calculation codes used for studies in supportof the assessments of the effectiveness of fireprecautions. Some programmes are carried out incollaboration with industrial partners (EDF,COGEMA, etc.) and are the subject of exchangeswith other national and international organisations(INERIS, universities, US-NRC, etc.).Two research programmes were completed in2004: the first addressed fires in electricalcabinets (CARMELA/CARMELO programme), andthe other was about changes in gas pressurewhen a fire occurs in an installation consisting46I R S N ANNUAL REPORT 2004

Full-scale blowing device to test the strength of VHE filters and fire dampersunder pressure (STARMANIA).of several spaces (DIVA 0 programme).Two other experimental programmes, started in2003, firmed up in 2004 with the preparation andcompletion of the first test campaigns.The PRISMEprogramme is concerned with heat and smokepropagation from a fire source to adjacent spaces(see Focus p. 48). The PICSEL programme aims tobetter assess the consequences of fires with slowkinetics of the “electrical cabinet type”in a nuclearinstallation (see Focus p. 49).In parallel with these programmes, in 2004 IRSNcontinued with the acquisition of data andinformation on the behaviour of compartmentationequipment (doors and firewall valves) in theSTARMANIA installation.These tests are intendedto ascertain changes in aeraulic and mechanicalstrengths of these compartmentation devices asa function of the temperatures and pressures towhich they might be subjected during a fire in aconfined space.Simulation of a fireTwo approaches have been developed to simulatea fire in a nuclear installation:a simplified approach,currently using the FLAMME_S/SIMEVENT software,and,from 2006,the SYLVIA software,and a detailedapproach being run under the ISIS code. For thesimplified approach, the coupled FLAMME_S/SIMEVENT software has been operational since1999. It was used in 2004 to carry out studiesprior to the PRISME programme tests (accuratedefinition of test conditions and integrity checkfor the DIVA installation during these tests).Development of the SYLVIA software continuedin 2004 (see Focus p. 50).For the ISIS code,which will enable the developmentBEHAVIOUR OF URANIUMHEXAFLUORIDE (UF 6 )Under the PIC set up by IRSN with operators of theupstream cycle of nuclear fuel (COGEMA, EURODIF, FBFC)addressing the behaviour of uranium hexafluoride(UF 6 ), the work undertaken by IRSN in 2004 covered:■ tests and simulations to assess the UF 6 behaviour in a room underdifferent configurations (building ventilation configuration, leakrate, etc.). Because of the difficulties of operating with UF 6 , thetests undertaken in IRSN facility in Saclay (Essonne) were carriedout using SF 6 , a good simulator of UF 6 for the phenomena studied;■ the development of a modelling tool for the sublimation of solid UF 6 .The aim of this work was to enable a more realistic assessment ofthe chemical and radiological consequences of an accidental uraniumhexafluoride release.All the tests and models will be used in support of the design for a newmethod to quantify releases.The programme is planned for completion in 2006.Experimental device simulating the behaviour of heavy gases atSaclay (Essonne).FOCUSI R S N ANNUAL REPORT 200447

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESDevice for PICSEL tests under the SATURNE hood.PRISME EXPERIMENTAL PROGRAMMEFOCUSIn 2004, IRSN continued its work under the PRISMEexperimental programme.The aim of this is to study propagation mechanisms for smoke andheat from a fire in a given room towards adjacent premises.It will provide unique large-scale information on these phenomena thatare important for the understanding of the risks associated with fire.It will enable the validation or modification of the corresponding IRSNcalculation codes, and hence offer better estimates of the time periodsafter which there might be failure in essential safety equipmentfollowing a fire.Three smoke propagation modes were taken into account: propagationvia an open door, propagation via a ventilation duct transitingthe room where the fire started and ventilating an adjacent room,and propagation via a ventilation duct involving reversal of flow inthe latter.The programme includes both an analytical and a global approach.The analytical approach involves separate studies of the source,the three propagation modes described above and the flows intothe adjacent room.The global approach studies the interactions between the threepropagation modes for actual fire scenarios, with and withoutthe effect of ventilation.The study of the fire source, carried out in 2004, enabled thedescription of the behaviour of a sheet of hydrogenated tetrapropylenein an open area and in a closed room ventilated mechanically. Thisreference fire will be used for the study of the three propagationmodes and of flows into the adjacent room.of a fire to be studied in detail by calculating inparticular the temperatures and concentrations ofthe various gases in the different elemental volumesof a room, 2004 saw the development of version 2that enables the simulation of fires in confinedspaces with mechanical ventilation. A series ofcalculation cases (test cases), of increasingcomplexity, enabled the validation of the modelsused to be consolidated, in particular for thesimplified ventilation model that was coupled tothe basic version in 2003.The calculation of a fullscalefire test in the FLIP test series, carried out inthe PLUTON installation,began at the end of 2004and marked the start of the qualification phase.In conjunction with the PRISME and PICSELexperimental programmes, a preliminary study,conducted with specialist universities in the field,led to a proposal and initiation of work on a thesison the generic development of the power of a firewith a view to creating improved models forcombustion rate in solid materials.Research into aerodispersionIn order to assess the measures needed tounderstand the containment of radioactive materialand to reduce uncertainties in the estimation ofreleases into the environment,the work undertakenby IRSN aims to determine the physico-chemicalphenomena relating to the suspension ofcontaminants and their transfer under normaland accident situations in an installation. In 2004,under this topic,IRSN undertook the enhancementof the BADIMIS database, used in the Institute’sexpert assessments and studies, exploiting newlyobtained test results about the suspension ofradioactive materials when powders andcontaminated objects are dropped.New programmeson the suspension of contaminants were48I R S N ANNUAL REPORT 2004

Control room of the DIVA experimentalinstallation.launched.They concern contaminated liquids andcontaminated solid materials affected by a fire.The work about changes in physical characteristicsof aerosols generated during a fire and the cloggingof high-efficiency filters by these aerosols hasenabled new basic data to be acquired that hasbeen incorporated into the calculation tools.As far as atmospheric dispersion is concerned,IRSNhas continued to upgrade its calculation tools fordispersion and the estimation of the consequencesof an accidental release of radioactive products toreplace certain models now considered obsolete.The aim is to have available a set of tools incorporatingthe latest knowledge acquired on the topicof dispersion in the near field of the installations,but also at a regional or continental level,that couldbe used in a crisis situation and for study and expertassessment purposes.In 2004, the architecture of the various tools wascompleted and the development of calculationmodels was continued with collaboration fromuniversity partners. A first version of the pX softwareintended for crisis situations was developed.PICSEL EXPERIMENTAL PROGRAMMEFOCUSThe PICSEL programme is being undertaken by IRSNunder a PIC with COGEMA.It concerns the study of fires in electrical cabinets that could affectan installation including several ventilated premises (cloggingof high-efficiency filters by smoke, disturbance of pressure levels inpremises, etc.), as well as equipment containing radioactive material(glove boxes, bins, etc.).The aim of this programme is to enhance knowledge about thephenomena relating to the propagation of fires in solid materialsin confined and ventilated spaces, and to qualify the calculationcodes for these phenomena. The PICSEL programme started in 2003and will continue to 2008.2004 was set aside for the carrying out of PICSEL_A tests: thesewere intended to characterise an electrical cabinet fire in a freeatmosphere under the extraction hood of the SATURNE device,by measuring the concentration of soot produced, the heat flux fromthe source to nearby equipment and the source power. In parallel,the PICSEL_C tests, relating to the characterisation of componentsof the glove box (glove ports) and waste bins, were preparedfor execution at the beginning of 2005. The PICSEL_A and PICSEL_Ctests represented the two stages prior to the tests that will becarried out in the DIVA installation (in multi-premises configuration)in the second half of 2005. For these tests, the configuration of thepremises and the ventilation network will be decided based on initialcalculations carried out using the FLAMME_S software.1 2 3Test aimed at ascertaining electrical cabinet combustion modes.1- Ignition phase. 2- Fully developed fire. 3- Post-experimental phase.I R S N ANNUAL REPORT 200449

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESTeam developing the SCANAIR software.SYLVIA SOFTWARE PLATFORMFOCUSIf the risks associated with fire are to be better understood, it is vital to be able to predict thedevelopment of a fire within an industrial complex consisting of premises that may or may notcontain radioactive material, linked one to another by a ventilation system or other openings.To this end, IRSN is developing SYLVIA, that simulates the propagation of a fire in such an installation and calculatesin particular the transport of smoke, hot gases and, where applicable, any suspended contaminants. Delivery of the firstversion is planned for 2006. A preliminary version was produced in 2004. This simulates the flows of a gaseous mixtureand is coupled to a graphical tool that enables the construction of a ventilation network and the entering of software inputdata. The physical models correspond, for the fire, to a simplified approach, as in the FLAMME_S/SIMEVENT software, butwith significantly improved digital processing of the equations, especially for the description of the interaction betweenthe fire and the ventilation. Subsequently, changes in the compartmentation and containment elements resulting fromthe fire will be modelled (filter clogging, changes to the aeraulic behaviour of doors and firewall valves, etc.).Over the longer term, SYLVIA will incorporate a detailed calculation module of the fire (ISIS software) and will be coupledto SUNSET to carry out uncertainty analyses.Research on earthquakesIRSN’s seismological work aims at abetter understanding of earthquakesas an external source of potential hazardto at-risk installations.Location of stations of the IRSN seismic network for the MiddleDurance fault, against a topological background. The red lines showthe fault segments.Seismological and geodesic instrument arrays enablesource activity to be measured, and speeds anddeformations to be estimated.In 2004, data from the array installed around theMiddle Durance fault and determination of thesource mechanism for around thirty earthquakesenabled confirmation of the primarily strike-slipfaulting nature of the fault, which must be knownin order to be able to carry out digital simulationsof motion prediction.The study of site effects (effects of superficial soillayers on motions resulting from earthquakes) alsofocussed on the two instrumented sites:the Grenobleintermount basin and the Aigion region in Greece.In 2004,the response of superficial layers to seismicstresses,termed the “transfer function”,was calculatedfrom recordings of weak motions at both sites.Finally, a major effort addressed the probabilisticestimation of the seismic hazard for which astudy was carried out at the Tricastin site (Drôme).50I R S N ANNUAL REPORT 2004

Electronic slate for the referencing of samplestaken from the environment.The SYMBIOSE platform is used to model transfers of radionuclides in theenvironment.Radioecology researchIn 2004, the Institute carried outresearch into two aspects of radioecology:onthe one hand,the behaviourof radionuclides on ecosystems inrelation to controlled or accidentalreleases resulting from nuclear activitiesand on the other hand, workintended to achieve a better understandingof the spatial and temporaldevelopment of radioactivity in theenvironment.Development of models, tools andexpert assessment techniquesIn order to be able to assess the impact of nuclearactivities on the environment, IRSN has been overmany years developing and maintaining the modelsand tools needed to predict the behaviour ofradionuclides.In 2004,a new version of the ASTRALsoftware, jointly funded by EDF, was installed atthe Institute’s Emergency Response Centre (CTC).This software enables an assessment of theconcentrations of radionuclides in various sectorsof the food chain, following an accidentalatmospheric release. The main innovation is theability to carry out calculations for uranium. Inaddition, a version of the CASTEAUR software,dedicated to the estimation of the radiologicalimpact of radionuclide releases into watercourses,has been developed to enable longer-termcalculations. For the marine environment, theDISPRO software, whose aim is to predict theatmospheric dispersion of radionuclides in the nearfield of the La Hague plant (Manche) has beenvalidated by campaigns involving sea plotting.In the field of new tools, a prototype of theSYMBIOSE integrated modelling platform has beencompleted. Unlike software that only works in asingle environment (agricultural, aquatic orairborne),SYMBIOSE addresses all the media usingthe same software, enabling the modelling oftransfers both within and between the differentmedia. As part of the work undertaken incollaboration with EDF, specific models have beenLAUNCH OF THE ERICA EUROPEANPROGRAMMEFOCUSAdopted under the 6th FPRD EURATOM, the ERICAEuropean programme was launched in March 2004.Its aim is to develop a method to measure (from scientific, decision-makingand societal points of view) the effects of radioactive contaminants onthe environment, with an emphasis on the protection of fauna, floraand ecosystems. ERICA is based on lessons learned from the EuropeanFASSET programme (5th FPRD), in which IRSN participated, that formaliseda conceptual framework for assessing the impact of radionuclides on theenvironment. Coordinated by the Swedish radioprotection authority (SSI),ERICA brings together 15 partners from seven European nations.Five working groups have been set up:■ development of assessment tools;■ development of methods to characterise and estimate the risk to theenvironment;■ preparation of recommendations concerning the demonstration ofthe protection of the environment against radioactive contaminants,including managerial aspects and communication with interested parties;■ applications for the assessment methods developed to a range ofin situ study cases;■ general project management.IRSN participates in all these groups and is coordinator for the second.The ERICA programme, which will end in February 2007, will provide anapproach that offers logical links between methods and software tools enablingassessment and management of the environmental risk associated withradionuclides.I R S N ANNUAL REPORT 200451

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESSampling of sediment in the Rhône river at Arles following a flood occurrence.developed and incorporated into SYMBIOSE thatenable the prediction of carbon 14 and tritium transferin the environment.Development of applied knowledgeExperimental activity, aimed at understanding themechanisms that control the behaviour of radionuclidesin the environment,are being undertakenin support of model development. 2004 thus sawthe completion of the European BORIS programme,LAUNCH OF THE EXTREME PROJECTFOCUSIn 2004, IRSN launched a project concerned with theimpact of extreme events on the transfers of materialsin coastal regions.This project, entitles EXTREME, was in part born out of the results ofthe CAROL project, that enabled, on the scale of the lower Rhône valley,the determination of what had become of the various artificialradioactive element contributions that this region has been subjectedto over the past forty years. The aim of EXTREME is to assess the impactof “extraordinary” natural processes on the flow and distributionof radioactivity stocks, whether they are artificial or natural in nature.The main aim will be to understand the scale of the transfers of materialsand contaminants associated with these exceptional climatic episodes.Studies will also be carried out into the transfers betweenthe atmosphere and the ground during high precipitation rates, fog ordeposits of particles of Saharan origin. Similarly, the river flow towardsthe sea or the land, in the case of flooding, will be monitored. Finally,the resuspension of sediments in coastal regions, in stormy conditions,will also be studied. Preliminary results show that such exceptionalevents lead to significant flows of radioactivity and to activities thatare temporarily superior to those corresponding to the mean transferprocesses. Some extreme events may thus lead to transfers equivalentto several months, even several years, of accumulated mean transfers,as well as the creation of new storage areas.coordinated by IRSN, that, using experiments andmodelling, enabled the role of biological elementsto be better explained, firstly in the properties ofsorption/absorption of radionuclides in soils andsecondly in the soil/plant transfers.In the study area concerned with the resuspensionof marine sediment,work under a thesis presentedin 2004 enabled the demonstration of possibleremobilisation of plutonium in sediments depositedin the Channel and the Irish Sea.In the atmospheric dispersion field, IRSN participatedin several experimental measurementcampaigns that aimed either at a better understandingof atmospheric dispersion phenomenain an urban environment (collaboration with Météo-France), or at characterising aerosols released bythe La Hague plant (collaboration with COGEMA).The activities planned under the IRSN/CEA/EDFtripartite collaboration continued in 2004. In thiscontext, IRSN worked mainly on the developmentof a method for the assessment of the risk to theenvironment resulting from radionuclides andcarried out several studies into the behaviour ofradionuclides in the non-saturated zone of the soil.At an international level, IRSN teams were heavilyinvolved in the IAEA’s EMRAS programme. Inparticular,the Institute was tasked with coordinatingthe activities of the group assigned to revising theIAEA guide TRS-364 that is a compilation of basicradioecological data.Finally, in the context of the many calls for tenderemanating from public organisations (ANDRA,Seine-Normandie Water Agency,Basse-NormandieRegion ,PACA Region ,Ministry for Research,Ministryfor Environment), around 10 projects proposed bythe Institute were adopted concerning the evolutionand effects of radioactive pollutants in theenvironment.52I R S N ANNUAL REPORT 2004

Sediment press used to extract interstitial waterfor analysis.Understanding spatial and temporalchanges to radioactivityin the environmentThe Rhône is the primary source of artificialradioactivity in the western Mediterranean. Theflow of pollutants, whether radioactive or not,travel down the Rhône to the sea, and hence theaccumulations of radionuclides that have formed,especially at its delta,are of interest to the nationaland international scientific community. They arethe subject of a range of projects (ORME, RESYST,MEDICIS and EUROSTRATAFORM): IRSN participatesin some of these.For the ORME project, the collaboration takes theform of the supply of data from the IRSN’s OPERAstation in Arles (Bouches-du-Rhône) that possessesa device unique in France for the automaticmeasurement of pollutants flow. The Institute’sknow-how is also of interest to the Rhône andMediterranean Water Agency that participated inthe funding of this station, as well as theOceanographic Centre of Marseilles,that will soonbe using this infrastructure to analyse chemicalpollutants. Studies based on the results from thisstation have also shown the significance of peaksin the flow arriving at the sea. The first results ofa thesis started in 2002 show that more than80% of the 115 GBq of caesium 137 carried bythe Rhône during 2002 were carried during onlyabout twenty days of flood flow.The primary sourceof the flow of caesium and plutonium into theMediterranean is no longer discharges from nuclearinstallations but the drainage of the radioactivitypresent in the soils of the drainage basin and theremobilisation of radionuclides present in ancientsediments stored in the riverbed. At sea, variousphenomena result in the rapid deposit of radioactivepollutants in a fairly limited 30km 2 zoneTHE ECORAD CONGRESSIn September 2004, IRSN organised the second ECORAD,an international congress on radioecology; this was heldin Aix-en-Provence (Bouches-du-Rhône).Under the patronage of the International Union of Radioecology (IUR)and the International Commission on Radiological Protection (ICRP),ECORAD brought together more than 320 scientists from 36 differentcountries.The aim of the congress, entitled “The scientific basis for environmentprotection against radioactivity” was to carry out a surveyof the knowledge available to the international scientific communityand hence to assess the impact of radioactivity on the environment.The congress was particularly interested in newly acquired data onthe effects of chronic exposure on organisms and ecosystems, witha view to enabling the development of relevant internationalrecommendations.Five technical meetings were held in the margins of the congress,including the general assembly of the IUR.150 papers were submitted to the congress secretariat, for publicationin the report of the congress. The year 2005 will see the issue of thesepapers in the SFRP’s review Radioprotection. The guest lectures willthemselves be featured in an IRSN publication.The Institute intends to make ECORAD a regular international meetingplace for radiological scientists. The third is planned for September 2007.Programme of the ECORAD international congress(September 2004).FOCUSI R S N ANNUAL REPORT 200453

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESSince April 2004, the CEA’s carbon 14 measurement laboratory at Gif-sur-Yvette hasbeen equipped with an accelerator mass spectrometer (AMS). IRSN is entitled touse it to study 400 samples a year as it made an 8.5% contribution to its financing.corresponding to the river’s prodelta. However,the results obtained in 2004 in respect of oneof the sampling series under the REMOTRANS(5th FPRD) programme, carried out in 2001 andinvolving many institutes under the supervisionof IRSN, showed that this zone did not representan ultimate resting place for radionuclides.Levels had in fact dropped significantly since theinventory carried out in 1998 using samples takenin 1991. The future for the deposits and thedispersion of radionuclides on the continentalshelf concerns the international community underthe European programme EUROSTRATAFORM inwhich CNRS, IFREMER and IRSN are participatingfor France along with around 10 European institutes.Research into the metrology ofradionuclides in the environmentRadioecological studies on land involvethe search for radionuclides under arange of conditions,sometimes in verysmall quantities, in order to be ableto understand and quantify the spatialand temporal movements of radionuclidesdischarged during nuclearactivities. There is therefore an ongoingrequirement for improvementsand changes to metrology techniquesin support of such studies.In 2004, IRSN therefore pursued several developmentsin radionuclide metrology:■ development of an analysis method for gammaradiation spectra by digital simulation of differentmeasurement configurations; this method is currentlybeing adapted to the in situ characterisationof radionuclides present in the soil;■ improvements in understanding of backgroundnoise in germanium diode spectrometers usedby IRSN in the Modane (Savoie) undergroundlaboratory, enabling the measurement of verylow activities (of the order of a few mBq) ofradionuclides in very small quantities of material(less than a gram).As an illustration, developmentof this instrumentation has allowed us to offerinstrumentation support to a radiotoxicologicalstudy carried out in 2004 within IRSN on theingestion of sand particles with high levels ofnatural radiation;■ development,in collaboration with the École desMines in Nantes (Loire-Atlantique), of the couplingof a mass spectrometer and a capillary electrophoresissystem intended to characterise thechemical form (speciation) in which radionuclidesare found in the environment,information essentialto an understanding of their behaviour.54I R S N ANNUAL REPORT 2004

Sorting female zebra fish (Dario Rerio) to study their fecundity after chronicexposure to uranium.Influence of exposure chronicityon the behaviour and toxicity of radionuclides:the ENVIRHOM programmeAmongst the environmental disruptionsthat are often evoked as a possiblecause of the development of certainpathologies, the case of radioactivitymerits detailed study. It is for thisreason that IRSN launched, in 2001,the ENVIRHOM research programme.Its aim is to enable a better assessmentof the risks associated with chronicexposure to ionising radiation.Within the ranges of exposures that lead to deferredrisks (cancers, genetic mutations, etc.) ratherthan immediate effects, the current system toprotect the human from ionising radiation is basedon the assumption of a linear relation without athreshold between a “dose” indicator and the riskrun. This indicator has been adjusted primarilythanks to the monitoring of Hiroshima and Nagasakisurvivors,who were exposed to high levels of exposureconsisting of gamma and neutron radiation.In practice,this exposure mode rarely affects majorpopulations or the environment, which are moreoften exposed to chronic moderate radiationresulting from internal contamination and for whichthere is very little relevant experimental data.This is one of the main conclusions of the Europeanprogramme ERICA,in which IRSN participates.Theaim of the ENVIRHOM programme is therefore tocontribute to correcting these shortcomings sothat the extrapolations used to assess risk can bemade more reliable. The initial results, while stillnot suitable for transfer to an operational impactassessment tool, already confirm that moderateinternal contamination are indeed a specific situation.Human exposureThe first task undertaken involved verifying, usingseveral specific examples,whether the accumulationrates, excretion rates and toxicity of radionuclidesafter chronic contamination could be predicted basedon what can be observed in the case of acute exposures.The first element studied was uranium, as this canbe present in high concentrations in the subterraneanwaters of certain regions (Finland, New Mexico,Canada). The corresponding studies were carriedout using rodents that had been contaminatedexperimentally by uranium added to their drinkingwater. The first results were obtained in 2004.Accumulation of uranium in tissuesand comparison with ICRP modelsThe experiments show that uranium accumulatesin most organs of the rat, and that the process iscomplex.The uranium concentrations in the colonseem to increase gradually over time. This agreeswith the ICRP models predicting that, in chronicexposure cases, the uranium concentration in agiven organ rises to reach a plateau, and the ratevaries according to the organ studied. In contrast,the results obtained for other tissues show thaturanium accumulation does not follow this pattern.The kidneys,the skeleton,small intestine,the brain,muscles, liver and the body overall, show veryspecific contamination profiles that result inphysiological changes linked to the contaminationI R S N ANNUAL REPORT 200455

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESLaboratory specialised in the study of daphnia at Cadarache (Bouches-du-Rhône).duration. In addition, one can see a significantdeposit of uranium in certain structures, such asthe brain or the teeth, which were not coveredspecifically in conventional models. The dataobtained is not yet such as to support an opinionthat these phenomena, observed on rodents withuranium,can be generalised to other radioelementsand the human race. However, they show that theconsequences of chronic exposure cannot besystematically extrapolated from those arisingfrom acute exposures. These results have beensubmitted for publication.Effects on the central nervous systemThe studies on the central nervous system were carriedout by measuring anydisruptions to sleep orURANIUMbehaviour. Enriched+ = +uranium and depletedMedicineMedicineuranium were used todistinguish the effectPHASE IPHASE Idue to chemical toxicityfrom the overallPHASE IIPHASE IIPHASE IIIPHASE IIItoxicity of the element.The results show thatan exposure of fortyfivedays to enrichedDisposalDisposaluranium is sufficientSchematic representation of the effects of uranium.to disrupt the sleep/waking cycle in animals, affect their short-termmemory and increase anxiety levels.These effectsare not seen with depleted uranium and can beexplained, at least in part, by the uraniumaccumulation in certain brain structures. Whenthe contamination is continued for nine months,the depleted uranium seems to affect the cellularorganisation in certain brain structures.An articlehas been accepted for publication.All these effects are observed when the uraniumconcentration measured in the kidneys, usuallyconsidered to be reference target organ,is less thatthe known toxicity threshold.This seems to indicatethat the brain is more sensitive to uranium thanare the kidneys and that it could be used insteadof the kidneys as reference organ. However, itremains to be explained why depleted uraniumdoes not accumulate on the same way in thebrain and why, apparently, it does not induce thesame neurobiological effects.The detoxification function of xenobioticsThe experiments carried out after chroniccontamination by depleted uranium over ninemonths show that the latter can modify thedetoxification function of xenobiotics, such asmedicines.The three medication metabolism phasesthat exploit the enzymes and transporters thatenable the elimination of foreign substances wereanalysed especially in the liver and kidneys. Thisstudy shows that chronic contamination by depleteduranium induces over-expression of first-phaseenzymes (P450 cytochromes) in these organs whilethe phase-II enzymes and the phase-III transportersare not affected.The increase in the expression of P450 cytochromesand the absence of changes to phase-II enzymesand phase-III transporters could result in changesto a major defence mechanism of the organism,detoxification by xenobiotics. Effectively, in thecase of a medicinal treatment, the medicationmetabolism may produce a metabolite that couldbecome toxic if it accumulates following a rise56I R S N ANNUAL REPORT 2004

Chironomid larvae in uranium contaminatedenvironment.in its synthesis rate (phase I) without an increasein its elimination (phases II and III). Conversely,if the medication retains its initial active form,its rapid degradation in phase I could lead totherapeutic ineffectiveness.If these hypotheses are confirmed, medicinaldosages will have to be changed when treatingindividuals with chronic exposure to uranium.The results obtained in 2004 are presented in articlesthat will be submitted for publication in 2005.Exposure of the environmentThe limited amount of data available prior to thelaunch of ENVIRHOM would appear to substantiatethe hypothesis that relatively high dose rates areneeded before definitive effects emerge. Theorder of magnitude is around 10 mGy per day (orabout 1,000 times the natural exposure rate).Nevertheless, the data is too fragmentary to drawreliable conclusions.It is in fact entirely possible that this order ofmagnitude will vary depending on the nature ofthe radiation source.Furthermore,interpreting observations in the naturalenvironment is particularly difficult because of itslack of homogeneity. A large-scale environmentshowing little contamination could in fact be amosaic of accumulations and of zones with virtuallyno contamination.The case of uraniumIndisputable effects are seen even for quantitiesthat are lower than those used in the experimentson the rats. For example, concentrations as low as150 nanomoles per litre are sufficient to preventgrowth in seaweed populations. The same resultsare obtained using depleted uranium orwith uranium enriched with uranium 233(which is highly radioactive);this wouldappear to prove that the effect of theradioactivity is, in this case, negligiblewhen compared with the chemicaltoxicity. At this level of concentration,the dose estimations are however of theorder of 10 mGy per day, which seemsto confirm that, for the low dose ratesthat are characteristic of environmentalcontamination, quite large doses ofradioactivity are needed to producediscernable effects.Other radionuclidesThis example naturally poses thequestion of improvements to conventionaldose indicators to make themmore representative of real effects.Thedose rate is clearly an important parameter,asis the type of radiation.To clarifythis point,tests are under way on a rangeof test organisms (daphnia,fish,worms)using depleted uranium, uranium 233,americium 241, polonium 210 andselenium 79.ProspectsThe first results confirm the validity of the initialassumptions:chronic exposure is a specific problem,the different test organisms and the range oftechniques applied demonstrated that they werewell suited to the task of demonstrating definiteeffects or microscopic effects that could beprecursors.0,40,30,20,1032 95 186 312 368 5700Experimental Length of Theoreticalvalues exposure (days) valuesAssessmentof memorisationcapacities bymeasuringspontaneousalternationsSpontaneousalternations (%)747270686664626058TheoreticaldataSpecimensExperimentalresultsY-mazeDUEUUranium concentration in the ratafter chronic ingestion of depleteduranium (DU) via its drinking water.*#21I R S N ANNUAL REPORT 200457

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESGranite house in Kersaint (Bretagne) where the Institute conducts experiments tofurther understanding of the circulation of radon in the home.Research activity on radonIRSN undertakes research to improveknowledge of the effects on healthresulting from radon in housing.Research also addresses the measurementof radon under particularconditions, its behaviour in buildingsand the deposit of its daughterproducts.Risks of lung cancer associatedwith domestic radon.The risks of lung cancer associated with domesticexposure to radon and to tobacco smoking haveUNDERSTANDING THE RADON CONCENTRATIONMECHANISMS IN BUILDINGSbeen the subject of numerous epidemiologicalstudies. Most of these have failed to show asignificant risk but lacked statistical power. Thejoint analysis of 13 case studies undertaken inEurope, that included the French study carriedout by IRSN,enabled some conclusions to be drawn.The French study, published in 2004 in the reviewEpidemiology covered 486 cases of lung cancer and984 subjects.Radon concentrations were measuredor recreated for each of the houses over the thirtyyears preceding the diagnosis of lung cancer andthe tobacco smoking history of each subjectestablished by questionnaire.The study showed anFOCUSAs part of a research programme concerned with understanding the mechanisms affecting theradon concentration in buildings, IRSN is using an uninhabited detached house, located inKersaint (Finistère), on a well-characterised uranium-bearing geological formation.Instrumentation of the various rooms and of the garden has enabled monitoring since 2002 of radon penetration throughthe basement slab, its accumulation in the building and its distribution via air circulation between the floors and exchangeswith the outside. In 2004, changes to the instrumentation enabled the detection of the disturbance caused by the buildingon the surrounding ground and the characterisation of two additional radon sources in the building: the semi-buried wallsin the basement and the building materials.In parallel, the multiplicity of parameters involved led IRSN to develop the calculation code RADON2 that enables thestudy of radon concentrations in the internal atmosphere of the building. The aim is to develop a tool for the predictionof radon activity per unit volume in houses located in regions with a high potential for exhalation or on polluted sites.As a preliminary, the validity of the phenomenological model on which RADON2 is based must be confirmed using dataacquired by instrumentation during the experimental phase that continues into 2005.Scientific collaborations have been developed with the University of Bretagne-Occidentale and the laboratory for the studyof transfer phenomena as applied to buildings in La Rochelle (Charente-Maritime) for the characterisation of thepermeability of the overall envelope of the building.58I R S N ANNUAL REPORT 2004

Probe measuring radon concentration in theground.increased risk of lung cancer as radon concentrationrose,with results at the limit of statistical significance.The joint European analysis, published in 2004 inthe British Medical Journal, covered 7,148 cases oflung cancer and 14,208 subjects. It shows asignificant relation, of the linear type with nothreshold, between exposure and effect onceallowance has been made for age, sex, the regionlived in and smoking habits. For an increase of100 Bq/m 3 of radon, the risk of lung cancer over alifetime increased by 8.4%.Thanks to its significantstatistical power,the study confirmed the existenceof an increased lung cancer risk following domesticexposure to radon. This result is coherent withvalues published in the literature and with thoseextrapolated from results of studies on uraniumminers.Radon metrologyIRSN has undertaken work on the presence andbehaviour of radon in thermal spa establishmentsto improve understanding of the exposure of thosetaking the waters and the staff to natural radiation.This work has shown that exposure routes andlevels differ according to the category of personnelconsidered (doctors,kinesitherapists,maintenanceand laundry personnel, etc.) and as a function ofduration of stay and of contact with the thermalwater, which is responsible for the presence ofradon in the buildings. In 2004, IRSN developed aprotocol that defined two methods for measuringnatural radiation in thermal establishments.Following work on the metrology of the activityper unit volume of radon in a particularly humidatmosphere,IRSN carried out radon measurementsin prehistoric decorated caverns that come underUSE OF RADON AS A GEOLOGICAL PROBEEver since the launch of the Viking spacecraft in 1976,the search for life on Mars has been a major concernof scientists studying the planets.A vital aspect of this research is the unambiguous determinationof the presence or absence of water in the first few metres of soilat equatorial latitudes. A “simple” measurement of radonconcentration in the lower Martian atmosphere could provide proofof the presence of water, which up to now the Spirit andOpportunity robots and the satellites Mars Odyssey and MarsExpress could not provide.The planned use of radon as a geological probe on the planet Marsresults from the well-established fact on Earth that the exhalationof radon from a porous soil is highly dependent on the watercontent of that soil: a quantity of water, even very small, increasesspectacularly the ability of radon to collect in the pores of the soiland migrate into the atmosphere.A thesis jointly funded as part of the partnership with the CNESis under way to transpose this observation to the environmentalconditions on the Martian surface and to define the characteristicsof a radon detector that could be embarked on a future Marsexploration platform. A PhD student arrived in December 2004in IRSN’s laboratory for the physics and metrology of aerosols.Baccara, the radon calibration bench at Saclay.FOCUSI R S N ANNUAL REPORT 200459

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESMap of the gamma dose rate in real time with respect to geographic location.the Ministry of Culture.Because of the very specificnature of the atmosphere of these caverns(confined and humid), an experimental protocolto characterise radon concentrations is beingvalidated in five prehistoric decorated caves selectedby the Ministry: Chauvet in Vallon-Pont-d’Arc(Ardèche),Niaux (Ariège),Lascaux,Font-de-Gaumeand Combarelles (Dordogne).Epidemiology of nuclear workersIRSN is developing epidemiologicalactivity with a view to estimatingthe risks of cancer associated withchronic exposure to low doses ofionising radiation.Current radiation protection standards are primarilybased on the results of the followupof survivors from the Hiroshimaand Nagasaki bombs, who wereexposed to high dose rates over veryshort time scales. Current concernsin radiation protection are moredirected towards individuals exposedto low doses over a prolonged periodin the course of their work. Modelsare used to extrapolate the knowledgefrom the Hiroshima and Nagasakisurvivors to groups of individualschronically exposed.In order to verifythe validity of these extrapolations,epidemiological studies on popu-Radon dosimeter at Kodalpha.lations exposed to low doses over time have beenset up since the 1970s.Workers in the nuclear industryrepresent an appropriate group for thesestudies as they form an abundant population whoseemployment is stable and where there are highqualityrecords of doses received.In this context, IRSN has set up monitoring for acohort of employees from the CEA-COGEMA group,with a view to estimating the risks of cancerassociated with occupational exposure to ionisingradiation, exposures that are low but chronic.Thismonitoring requires the retrieval of the individualdoses received by the workers throughout theircareer,search for vital statistics (whether deceasedor not) and, where relevant, the cause of death. Intotal, more than 50,000 workers employed by theCEA-COGEMA group since the 1950s are involved.An initial descriptive analysis of the mortality ofCEA workers was published in 2004 in the AmericanJournal of Industrial Medicine.This showed evidenceof under-mortality of this population in comparisonwith the general French population for both all60I R S N ANNUAL REPORT 2004

Archive room of the source expertise unit atFontenay-aux-Roses (Hauts-de-Seine).causes of death and for all cancers,but a significantexcess of deaths from malignant melanoma. Ananalysis of the dose-effect relationship for part ofthe cohort (29,000 individuals) was carried out.Analysis of the whole cohort will be possible onceall dosimetry has been validated.Part of this data was forwarded to the ICRC, thatis coordinating the international study relating toabout 50,000 nuclear workers in 15 countries andthat in particular addresses the effects on healthof external X- and gamma radiation. An analysisof mortality was carried out and an article wassubmitted in 2004 for publication in a review.The cohort of CEA-COGEMA workers will also beincorporated into the European research project,coordinated by IRSN, into the risks of internalexposure to ionising radiation.Finally, under a PIC between IRSN and COGEMA,a study was launched in 2004 into the morbidityof current workers,in collaboration with COGEMA’swork medicine department.COORDINATION OF EUROPEAN PROJECTSON THE EPIDEMIOLOGY OF IONISINGRADIATIONIRSN’s epidemiology laboratory has alreadycoordinated several European research projects,especially under the 4th (1996-1999) and5th (2000-2003) FPRD.FOCUSThis work concerned the quantification of the risk of cancerassociated with cumulative exposure to radon, and in particularbased on studies of uranium miners.In 2004, a new research project was developed in response to thecall for tenders from the 6th FPRD.This research, more ambitious than earlier programmes, will involve18 partners from nine countries, under the coordination of IRSN.Its aim is to improve understanding of the health implications –cancers and other pathologies – of chronic exposures to ionisingradiation.In particular, it aims to introduce new factors into the quantificationof the risks associated with internal exposures, by incorporatingthe majority of European studies on the subject: cohorts of uraniumminers (more than 20,000 miners), study into domestic radon (jointstudy by 13 European countries), and studies into the risks for nuclearworkers who have received internal exposures, etc. This researchimplies collaboration between research teams across three disciplines:epidemiology, dosimetry and bio-mathematical modelling.The project is due to start in 2005 and will last three years.I R S N ANNUAL REPORT 200461

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESEnd of acceleratorbeam line andTID targetPolyethylene0.80.70.660500.5400.430DepletednaturaluraniumIronWater lens0.30.20.10.010 -8 10 -7 10 -6 10 -5 10 -4 10 -3 10 -2 10 -1 10 -020100Neutron Energy (MeV)Development of reference neutron fields with the CANEL T400 device producingrealistic mixed fields.Improvements in radiation protectionTo improve radiation protection forworkers,patients and the public,IRSNmakes regular improvements to themethods and tools it uses to assessthe exposure of persons to ionisingradiation.In nuclear installations whereradioactive material is handled, theworkers are exposed to a risk of internalcontamination. Their protection isprovided by equipment, whoseperformance following an accident hasbeen studied by IRSN. Effectivenesshas also been improved.In 2004, IRSN mainly worked on the developmentof tools for the simulation of internal contamination,by developing reference neutron fields,the loweringof detection limits,for example for the measurementof wounds contaminated by actinides or for thepassive dosimetry of neutrons, and finally theassessment of exposure on board aircraft duringsolar maximum.Effectiveness of protection equipmentIn the area of protection equipment effectiveness,IRSN studied in 2004 the situation created by theaccidental failure of static containment providedby the gloves and sacks fitted to glove boxes usedfor the handling of radioactive material.The resultsenabled a quantification of the amplitude of aerosoltransfer phenomena following the tearing of suchequipment under a range of configurations. Theeffectiveness of a safety device offering dynamiccontainment by means of an additional extractionflow was demonstrated, regardless of the nature ofthe contaminant (gas, aerosol).The benefits of sucha device on the reduction of aerosol transfers towardsthe outside of a containment are greater for thelarger particles (5 µm).Dispersion of pollutantsIn the field of pollutant dispersion, thesis workcompleted at the end of 2004 enabled thedevelopment of correlations describing thespatiotemporal evolution of the concentration ofa gaseous pollutant in the immediate vicinity ofan accidental leak as a function of the variousparameters concerning the leak (speed and durationof the emission, dimensions of the aperture), thepollutant (initial density and concentration) andventilation of the room (transverse flow rate).Thesecorrelations were incorporated into a simplifiedcalculation tool that can be used to estimate theconcentrations of pollutants in a room after anaccidental rupture in the containment provided bya containment. Complementary work is beingundertaken to study the case of a specificcontaminant, as well as the influence of partitionsand obstacles in a room.SamplingIn the field of aerosol sampling,the work undertakenby IRSN aims to provide the means to evaluatethe sampling strategies to be introduced to estimatethe exposure of workers, and especially the choicebetween individual and fixed-station sampling. In2004,comparative tests of various types of samplerwere carried out in situ in a workshop. Two mainpoints were identified:responses differed betweenfixed-station samplers and individual samplers anddepended primarily on their individual performanceas a function of the granulometry of the sampled62I R S N ANNUAL REPORT 2004

Physical phantom used for the calibration ofwhole-body radiation measurementinstallations.aerosols. In addition, the comparison betweenindividual sampling and ambient sampling showedthat the activities measured by individual samplingmight be significantly higher, in certain contexts,than those determined from ambient sampling.Improvements to in vivomeasurement of actinidesMathematical phantoms for the realistic invivo measurement of actinides in the lungs andcontaminated woundsOne of the methods used to estimate the internalcontamination of an individual relies on thedirect measurement of X- and gamma radiationemitted by his/her organism. This in vivo method,termed “anthroporadiametry”, offers the advantageof being quick and easy to implement for X- andgamma radiation emitters at energies exceeding100 keV.Where actinides have been incorporated,its use is more problematical as the emittedradiation is low and highly absorbed in tissues.Although major efforts have been made to improvephysical phantoms (mannequins) used to calibrateanthroporadiametry installations,such models canonly offer an approximate representation of thehuman body.Consequently,corrections have to beapplied to the calibrations obtained using thesephysical phantoms in order to extrapolate themto a given individual.These corrections are critical,but particularly significant for the in vivo measurementof low energy radiation, as absorption intissue is high.So, to improve the calibration, three-dimensionalmathematical phantoms built up from scannedimages or IRM (voxelised phantoms) were linked toMCNP Monte-Carlo calculation codes. An interface,called ŒDIPE, enabled, firstly, the generationof voxelised phantoms and,secondly,the simulationof whole-body measurement under conditionssimilar to reality.In 2004, an initial validation of this approachinvolved introducing into ŒDIPE the geometriccharacteristics of the multi-detector countingsystem belonging to the biological and medicalanalysis laboratory at COGEMA Marcoule (Gard)ANTHRO-Si projectFOCUSIn 2004, IRSN completed development of a prototypeof ANTHRO-Si, the whole-body counting measurementsystem.This was the result of a project started in 1995, to lower the detectionlimits of current measurement systems, that use germanium detectorscooled using liquid nitrogen.This project involves the design of a system based on the use of “pixelated”PIPS silicon detectors operating at ambient temperature.Whole-body measurements can rapidly determine the radiation ofradionuclides incorporated by a person. It is used for medical monitoringof workers at risk of internal contamination. However, for transuranicelements, the sensitivity of the measurement is limited by the factthat low energy X- and gamma lines (< 100 keV) associated with alphadisintegrations are absorbed. This absorption and the heterogeneousdistribution of activity in the tissues contribute to the difficulty ininterpreting the results of the measurement.The metrological performance of ANTHRO-Si will be studied in 2005for wounds contaminated by actinides, before considering whether it canbe industrialised.The major advantage of ANTHRO-Si is its ability to locate contaminationsmore accurately thanks to the “pixilated” detectors with minimal mechanicalsize, while offering, at first sight, a better compromise between resolutionof the measurements and the surface of the detector than the germaniumdetectors. This system, if industrialised, would be a simple in vivomeasurement system for internal contamination resulting from accidentsituations.I R S N ANNUAL REPORT 200463

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESDevelopment of 3D digital phantoms.based on drawings provided by the manufacturer.Activity measurements were then made using pointsources; these enabled the validation of thegeometric description of the system by comparisonwith measurements “simulated”by the MCNP code.Other measurements, made using the Livermorephysical phantom (at the Lawrence LivermoreLaboratory – USA), enabled the validation of theŒDIPE tool for the installation,demonstrating thepossibility of deriving graphs of virtual effectiveness,as they were obtained by simulation, with a viewto calibrating the installation.Application of voxelised mathematical phantoms associated withthe MCNP Monte-Carlo code for the realistic in vivo measurementof actinides in the lungs and in contaminated wounds.14716 91610 15 15 1017 101711610138 14Sectional view of the modelling of a germanium detector.Based on these results, research has been targetedon determining the uncertainties in themeasurement. The first stage involved studyingthe variation of incorporated activity within anindividual (represented by a voxelised phantom),when the measurement system was calibratedusing a range of thoracic thicknesses for theLivermore physical phantom.The results obtainedrevealed two points: the advantages of carryingout calibrations of whole-body installations usingvoxelised phantoms with morphology close to thatof the persons being measured; the need todetermine bio-parametric equations specific toEuropean morphology, as current equations are ingeneral determined by the morphology of NorthAmericans.The second stage involved the simulation of nonhomogenouscontaminations, to improve understandingof the influence of heterogeneity in thecontamination on the calibration. Two simplifiedcases of lung contamination were used;their resultswere compared with those obtained for a uniformcontamination of the lungs. The results seem toshow no significant difference between a nonhomogenouscontamination and a uniformcontamination for energies in excess of 26 keV;but,a slight difference is reported at 17 keV.Consequently,heterogeneity in contamination does notcall into question existing calibrations.Dosimetry of neutrons by track detectionIn 2003, the IRSN’s dosimetric monitoring laboratoryundertook a study with the aim of improvingthe passive neutron dosimetry system based onthe track detection technique. The objectives area reduction of the detection threshold, bettertreatment of background noise as well as anextension of the response of the dosimeter to lowenergy levels.The physical principle of the detector used (apolycarbonate commercialised under referencePN3) depends on the interaction of neutrons inthe volume of the material. The resultant breaksin the polymer chains create damaged areas thatreact in contact with a strong alkaline mediumbefore the rest of the polymer. The result is theappearance of microscopic tracks on the detector64I R S N ANNUAL REPORT 2004

Positioning of the neutron dosimetricapparatus in front of CANEL.Dosimetric assessment during a solar flare.surface after several hours of immersion in an alkalinesolution.The determination of optimum parameters for chemicaltreatment concluded in 2004 with the development of anew protocol for the measurement of doses resultingfrom neutrons.Thanks to a chemical treatment,the detectorbecomes sensitive to external charged particles, whichimproves its performance, with a response multiplied bytwo; there is an indicator that shows if the dosimeter hasbeen irradiated; the addition of converters in contact withthe dosimeter enables the entire energy spectrum to becovered.Development of reference resourcesThe IRSN’s neutron metrology and dosimetry laboratoryholds the status of laboratory associated with the Nationalmetrology and test laboratory (LNE). It therefore operateswithin its facilities all the tools required to better definethe major standard quantities such as fluence and ambientdose equivalent. These quantities are obtained afterexperimental confirmation of energy distributions forradiation fields calculated using the MCNP code. In 2004,the final results of the international spectrometry campaignon the CANEL T400 installation were published. Theseresulted in improvements to the characteristics of one ofthe CANEL screens; they also gave access to the energydistribution of the neutron field of the SIGMA stack. Inaddition, liquid scintillation spectrometry of the neutronreference sources called into question the universalityof the spectrum of the AmBe source indicated in standardISO 8529-1.COSMIC RADIATION:THE DOSMAX PROJECTBecause of cosmic radiation, aircrew receive individualannual doses that, in certain cases, can attain severalmillisieverts.In this context, the DOSMAX project, funded by the EuropeanCommission, linked more than 10 European laboratories between 2000and 2004, with the aim of assessing exposure on board aircraft duringsolar maximum periods. Numerous measurements were carried outin flight by the various laboratories, in collaboration with the airlines.The Institute organised an airborne intercomparison of dosimetricsystems from the various laboratories on an Air France cargo aircraftduring a Paris-Fairbanks-Tokyo flight. This intercomparison was aunique opportunity to compare the responses of several dosimetrictechniques in an actual situation and to show if there was goodcoherence between the various experimental systems and themodels used to carry out the routine monitoring of the doses receivedby aircrew. The effective dose measured for a return flight was120 µSv ± 10 µSv (for comparison, the individual annual effectivedose due to cosmic radiation in France is of the order of 300 µSv).FAIRBANKS0,150,14WASHINGTON 0,09SAN FRANCISCONEW-YORK0,08TOKYO0,10PARISFOCUSBUENOS AIRESDoses in millisieverts (mSv) for one tripMeasurements taken by IRSN with the NAUSICAA apparatus on board AirFrance long-haul aircraft between 1996 and 1998 show the reality of exposureof flight personnel.I R S N ANNUAL REPORT 200465

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESAMANDE accelerator.The AMANDE installationIn 2000, IRSN decided to build a newinstallation, called AMANDE, whichcould generate mono-energeticneutron radiation fields,whose energycould be varied between 2 keV and20 MeV. The primary aim of thisinstallation is to determine the responseof measurement equipment asa function of neutron energy,as recommendedby the international standardISO 8529-1.The AMANDE installation will be at the heart ofthe French neutron reference system,ensuring thatthe IRSN’s neutron metrology and dosimetrylaboratory (LMDN) becomes a reference laboratoryfor this field at national,European and internationallevels.This laboratory is associated with the nationalmetrology and test laboratory (LNE) for bothdosimetry and neutron metrology matters. TheAMANDE installation could also generate a reference7 MeV photonic field (recommended by theinternational standard ISO 4037-1) that currentlydoes not exist in France.It will enable an extensionto the IRSN’s calibration capabilities in the highenergyphoton field.2004 saw the completion of build and installationas well as the setting up of the accelerator itselfwith its associated equipment. The performanceof this accelerator will enable an accuratedetermination of the energy and fluence of theneutron field with a resolution of less than a fewpercent. Neutron emission could reach 5.10 8 s -1and will generate continuous or pulsed radiationfields with a pulse width of less than twonanoseconds. As the experiment hall has metalwalls, background noise resulting from diffusedneutrons is significantly reduced compared withequivalent installations with concrete walls.Finally,an automated system with moving arms enablesaccurate location of the detectors to be irradiatedat a given angle and distance (up to 6 m) from thetarget, the neutron source.The AMANDE installation completes the installationsalready in use at IRSN:■ two neutron generators, associated with theCANEL device,that generate neutron fields similarto those observed at certain work stations inreactors;■ an irradiator that employs two radioactive sources(one of americium-beryllium and the other ofcalifornium);■ SIGMA that generates a field with a high proportionof “thermal” neutrons.Test hall for the AMANDE installation.66I R S N ANNUAL REPORT 2004

“Rando” whole-body phantom for dosimetryof patients.The radioprotection of patients:consequences of radiotherapy onhealthy tissue present in the radiation fieldThe IGR and IRSN have formed a mixedunit,under the framework of the HigherEducation’s Own Research Unit (UPRES)27-10 for the study of the physiopathologicalmechanisms that controlthe development of radiation-inducedfibrosis and the definition of newtherapeutic strategies for theirtreatment.The doses of radiation required to control canceroustumours in the abdominal-pelvic region cause acuteand delayed intestinal toxicity phenomena.The delayed complications of the radiationinducedfibrosis type may have very significantconsequences both from their chronic andprogressive nature and from the associatedmorbidity and mortality. Currently no treatmentis available.Recent studies have shown that the fibroses wereevolutionary pathologies comparable to a chronicscar-formation process. Two models have beenproposed to explain the delayed effects developedby healthy tissue following radiotherapy.The firstdescribes the delayed effects as the consequenceof severe and persistent acute effects.The seconddescribes the delayed effects and the radiationinducedfibrosis as the result of the irradiationof connective tissue and the reduction ofparenchymatous and stromal cells. These twohypotheses are being examined within the mixedteam. Preclinical tests have been carried out witha specific intestinal growth factor: the GlucagonlikePeptide 2 (GLP-2). This therapeutic approachaims to produce epithelial cells and the recolonisationof the intestinal mucus after irradiation.The study is being undertaken under a researchcontract with the Novo Nordisk laboratoriesEUROPEAN MOVES IN MEDICALRADIATION PROTECTIONFOCUSThe research carried out by the mixed IGR/IRSNteam on radiation-induced enteritis forms part ofthe European-wide effort to encourage the transferof research results to radiotherapy.The Translational Research Group (TRG), formed in 2001 within theRadiotherapy group of EORTC, had as its aim the development andcoordination of relations between clinicians with the aim of ensuringthe early clinical application of advances in research into radiobiologyand radiopathology. The activities of the group are directed alongthree lines: predictive agents, diagnostic agents and therapeutic agents,into which the work of IRSN fits perfectly. Two clinical studies, plusa predictive test resulting from IRSN work, will be set up incollaboration with the IGR.The involvement of IRSN in the TRG/EORTC and ESTRO groupputs theInstitute at a European level in the medical radiation protection field.I R S N ANNUAL REPORT 200467

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESPreparation of the colouring of histological cross section slides.(Denmark), suppliers of the growth factor. Onebeneficial effect has been shown in the acute anddelayed damage to the irradiated small intestineof the rat. This work was the subject of twopublications in 2004. Complementary studies arenow needed to confirm the therapeutic effect andto understand the modes of action of GLP-2.A second therapeutic line of enquiry has beendeveloped in parallel. This is based on the resultsobtained by IRSN on physiopathological mechanismsleading to radiation-induced enteritis in man.These results mean that it may be possible toconsider using the inhibition provided by ConnectiveTissue Growth Factor (CTGF/CCN2) as a meansof effective and specific action against fibroses.This discovery opens up genuine therapeuticpossibilities as pharmacological inhibitors of theRho/ROCK channel exist that control the productionof CTGF: the statins and fasudil. Therapeuticexperiments using statins have been startedusing the rat: the first results show a resorption ofradiation-induced enteritis in the rat.These promising preliminary results, published in2004, and the close collaboration with the IGR,lead one to hope that an early clinical applicationof the new anti-fibrosis strategies will be possible.Irradiation and contamination accidentsThe research programme carried outby IRSN on the effects of medium andhigh doses of radiation is divided alongtwo lines: research for bio-indicatorsfor diagnostics, or even prognostics,enabling an understanding of theextent of the radiation-induceddamage; research into new targetsfor therapeutic action.In parallel, the development of operationalmeasurement systems at different points of theorganism completes the diagnostic resources.Therisk of terrorist actions has increased interest inthis research programme that associatesphysiopathologists with physicians.Cutaneous radiation syndromeTwo hospital organisations, the Burns TreatmentCentre (CTB) at the Defence teaching hospital inPercy (Hauts-de-Seine) and the oncologyradiotherapydepartment at the Curie Institute(Paris), to whom IRSN often provides technicalsupport, have acquired an internationallyrenowned ability in the field of medical treatmentof cutaneous radiation-induced syndrome,resultingfrom their experience in the treatment of victimsof accidents in Georgia, Peru and Poland. Theirexperience shows that, while the pathogenics ofthe cutaneous effects of ionising radiation are welldescribed,the medical treatment remains extremelycomplex and problematic; the only therapeuticissue is the removal of irradiated tissue and skingrafting where tissues are tending towards necrosis.This finding has led IRSN, in cooperation with theCTB clinicians, to develop a research programmesupported by the DGA, aimed at improvingdiagnosis and treatment of localised irradiation(see Focus p. 69).68I R S N ANNUAL REPORT 2004

Observation with a fluorescence microscope (FISH technique: fluorescencein situ hybridisation).Improving diagnosticsAn accurate and early dosimetric assessment ofthe degree to which the exposed tissue is affectedis useful but does not suffice to confirm a diagnosis.It must be supplemented by an assessment of tissuedamage and the volume of tissue likely to suffernecrosis.An overall approach to the improvementin diagnostics of localised irradiation,including theintercomparison of various biophysical (Dopplerlaser, thermography, RMN), clinical and biologicaltechniques, was initiated in 2004 under a contractwith the DGA (see Focus p. 69). Here, IRSN isdeveloping a new approach to biological dosimetryof localised irradiation, based on the applicationof cytogenetic techniques on the cells present inthe skin tissue. This approach, tested during thelast localised irradiation accident (Georgia) treatedin France, is being validated on an experimentalanimal model. Its results will then be comparedwith those obtained by the biophysical techniquesregularly used in clinic.Identification of new therapeutic targetsFrom a physiopathology point of view,the responseof skin tissue to acute high-dosage radiation canbe compared to a pathological tissue repair process,with the epidermal,vascular and mesenchymatouscomponents all contributing to the failure toheal.Histological studies, carried out during differentcases of localised irradiation accidents, providedaccurate information about the various stages ofthe process. Molecular studies using biochip haveenabled the identification of the principle genesinvolved in the cutaneous vascular response in man,during the latent phase of the cutaneous radiationsyndrome.The expression of some of these genesIMPROVEMENTS IN THE DIAGNOSIS OFCUTANEOUS RADIATION SYNDROMEFOCUSIn 2004, IRSN responded to a call for tenders from theDGA for improvements in the diagnosis of cutaneousradiation syndrome.The bid by the Institute was accepted. This research programmecombines clinicians from the Percy Hospital, radiobiologists fromIRSN and the Defence medical service research centre (CRSSA) andphysicians from the instrumentation, signals and systems researchand study laboratory (LERISS) in the Paris 12 University.The programme is organised around two major themes:■ the development of dosimetry tools for localised radiation,a thesis jointly funded by the DGA and IRSN started in September 2004;■ the study of the physico-pathological consequences of localisedradiation of cutaneous tissue. The transformation of the irradiatedtissue towards necrosis is one of the possible consequences oflocalised high-dose radiation that remains without a satisfactorymedical response. This transformation occurs through successiveeruptions that are difficult to predict. The aim of the study isto examine the pathological tissue repair process after radiationwith a view to defining new therapeutic strategies. This researchconsolidates the links that IRSN has forged with hospital organisationsthat can take responsibility for radiation victims, and in particularthe Percy Hospital, with the Institute providing technical support tothe medical treatment of victims of accidental radiation.I R S N ANNUAL REPORT 200469

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESPreparing samples after a histological analysis.has been confirmed using molecular biologytechniques, and their functional involvement hasbeen verified in the animal.The significance of the initiation and maintenanceof vascular endothelium activation after irradiationof the cutaneous tissue has thus been demonstratedexperimentally.Strategies aimed at controlling thisstructural and functional degradation of the vascularcompartment could therefore be explored in theshort term.An article summarising this was submitted forpublication in 2004.A therapeutic approach toaccidental irradiationA study of radiological accidents that have occurredover recent years shows that, in most cases, theoutcome was fatal primarily through lack of atherapeutic strategy adapted to the whole rangeIrradiation and contamination accidents - Placing a sample for measurementby EPR spectrometry.of radiation-induced damage. It is difficult totreat an acute radiation syndrome because of thesimultaneous attack against several physiologicalfunctions, and in particular the haematopoietic,gastro-intestinal and cerebrovascular systems. Ageneralised inflammatory syndrome may alsoappear, sometimes accompanied by secondarypathologies affecting the liver, the kidneys or thelungs. This array of pathologies can be groupedunder the term “radiation-induced Multiple OrganFailure Syndrome” (MOFS).Cellular therapyThe reduction or disappearance of normal stemcells,capable of regenerating tissue after a trauma,would appear to be the possible cause of radiationinducedMOFS.In the future,cellular therapy,whichconsists of bringing in cells capable of repairingdamaged tissue, could be a promising approach.The work undertaken by IRSN within the mixedteam installed at the Saint-Antoine Hospital(UPRES 16-38,Paris) is investigating the possibilityof adapting the principles of cellular therapy to thecase of victims of accidental irradiation in orderto correct cellular deficits in each of the damagedtissues.This approach was first developed for bone marrow.The results obtained show that the technique ofex vivo expansion of haematopoietic cells isparticularly effective in treating medullar aplasia.Adaptation of this technique to the case ofaccidental irradiation has been tested on anexperimental model of heterogeneous high-dosageirradiation of a non-human primate. Medullarycells were sampled after irradiation, expandedand reinjected into the animal, seven days afterirradiation; the results obtained showed a real but70I R S N ANNUAL REPORT 2004

Filling of tubes with fixing mixture in order to fix chromosomes.minimal effect on medullary aplasia. However,the irradiated animals developed a MOFS,suggesting the need to use other types of cell tocorrect the functional deficits observed.In the lightof this, studies were undertaken in 2004 aimed atdemonstrating the possibility of transplantinghuman mesenchymatous stem cells (MSC) intoirradiated immunodeficient mice (NOD-SCID), inwhich it is possible to assess the implantation,proliferation and differentiation of the graftedhuman MSC.These studies show that the MSC arecapable of implantation in numerous organsfollowing a whole-body irradiation and that theymigrate in preference towards the damaged zonesfollowing an abdominal irradiation. The resultsobtained also show that once implanted, the MSCproliferate and differentiate by acquiring thecharacteristics corresponding to the receiver tissue,in particular for the vascular system, the kidneysand brain. These results have led to the currentstudy of molecular addressing mechanisms for theMSC towards damaged tissue and their involvementin the functional regeneration of the damagedtissue.Molecular therapyA European contract called NAIMORI broughttogether between 2001 and 2004 a number ofEuropean teams (CIEMAT,Madrid (Spain);ErasmusUniversity of Rotterdam (The Netherlands);ILM/University, Ulm (Germany); CEA/Évry; IRSN)to evaluate the response of haematopoietic tissuesand human epidermis to radiation and to seek newtherapeutic approaches to medullar aplasia,inflammation of the tissues and the cutaneousradiation syndrome. IRSN was responsible for thework to characterise the generalised inflammatoryresponse and its limitation by cytokines. Theexperimental model adopted was whole-body orabdominal irradiation of mice, some treated bytherapeutic agents.The animal survival rate and the recording ofnumerous biological parameters were supplementedby a histological analysis of sampled tissues. Theassociation of thrombopoietin (TPO) withinterleukins (IL) 4 or 11 was shown to be moreeffective for animal survival than TPO alone. Thisimproved animal survival rate cannot be explainedsolely by the restart of blood-cell production; theresults suggest that the combined TPO andinterleukin treatment reduces radiation-inducedinflammation and acts on vascular permeability.In addition, in the case of abdominal radiationalone, a remote effect on the lungs that were notincluded in the radiation field was observed. Thiseffect on the lungs could result from the action ofSignal amplitude (DU)1.2x10 61.0x10 68.0x10 56.0x10 54.0x10 52.0x10 50.0-2.0x10 5-4.0x10 5-6.0x10 53460 3480 3500 3520 3540 3560Magnetic field (G)Irradiation and contamination accidents – EPR signal of hydroxyapatitein tooth enamel showing a high dose (60 Gy).I R S N ANNUAL REPORT 200471

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESChange of culture medium for human adult stem cells.EUROPEAN FIRST PROJECTcirculating inflammatory mediators arising fromthe gastro-intestinal response to radiation.All the results obtained in this European programmewere incorporated in nine IRSN scientificpublications. They tend to show that the threemajor types of tissue that determine the outcomefor victims of radiation are the haematopoietic,epithelial and vascular tissues. The regenerativecapability of the stem cells responsible for therepopulation of haematopoietic and epidermaltissues determines the response of these two typesof tissue. Simultaneously, the inflammatoryresponse developed by the irradiated endothelialcells interferes with tissue repair.Dose measurement by electronicparamagnetic resonanceIRSN is studying spectrometry using electronicparamagnetic resonance (EPR) with a view todeveloping a technique for the determination ofdoses received in different parts of the organismto establish the best possible diagnosis and proposeFOCUSDuring therapeutic radiation for the treatment ofcancer, the healthy tissue surrounding the tumour maybe damaged.These lesions may have serious consequences, such as tissular aplasiaor fibrosis. Their existence limits the effectiveness of treatmentby radiation, forcing a reduction in doses received by the patients.In 2004, the FIRST project was accepted under the 6th FPRD.IRSN is responsible for studying the gastro-intestinal system.The Institute is also involved in the study of the effects on the skin,as well as in a study into the preparation of mesenchymatous stemcells for grafting purposes.the most appropriate therapeutic strategy. Thistechnique involves an assessment of doses receivedby biological specimens that retain the free radicalscreated by the ionising radiation; the quantity offree radicals is directly proportional to the doseabsorbed;the number of free radicals is determinedby placing specimens in a magnetic field andquantifying the absorption of microwave radiationunder resonance conditions.This technique has been in use at IRSN for severalyears for small ex vivo specimens requiring invasivesampling (bone,tooth enamel,dentine) for materialarising from the victims’environment (sugars,etc.),or for exposures to photons or electrons. It wassuccessfully applied to the victims of accidentalexposures in Georgia and Poland. In 2004, thistechnique was extended to the case of an exposureto a mixed field (photons + neutrons) typical of acriticality accident. In particular, a study showedand quantified the difference in sensitivity of dentineand tooth enamel to photons and neutrons.Thesedosimetric properties enabled the experimentaldetermination of the photonic and neutroncomponents of a mixed field using EPR spectrometrymeasurements on enamel and dentine. Themeasurement protocols introduced at IRSN werevalidated during the third international dosimetryintercomparison using EPR spectrometry on toothenamel.72I R S N ANNUAL REPORT 2004

Management of post-accident situationsIn 2004, the major part of IRSN’sresearch into the management of postaccidentsituations came under theinternational projects EURANOS andCORE.EURANOS is a project coordinated by the Germanorganisation FzK, which brings together nearly50 teams and 20 countries. Adopted by the EuropeanCommission under the 6th FPRD, its mainaim is to define possible actions for the rehabilitationof agricultural and built-up areas following anaccident resulting in long-term radiologicalcontamination. The work began in 2004 with thesetting-up in France of groups of relevant parties(agricultural technical institutes,local governmentservices,elected representatives,experts),who willbe tasked with proposing appropriate rehabilitationstrategies for the various post-accident situations:transition between the emergency phase and thestart of post-accident phase,the first weeks followingthe accident and the later years.The CORE programme aims to achieve long-termrehabilitation of living conditions for the populationsof the four districts of Byelorussia contaminatedby the Chernobyl (Ukraine) accident, by means ofa range of actions in the fields of agriculturaldevelopment, health, radiological protection andeducation.IRSN is contributing to this in the healthand education fields.International cooperation to improvecontrol over radiological and nuclear risksCollaboration between nations enablesresources to be shared, knowledge tobe enriched and skills reinforced.In thefields of research into radiationprotection and nuclear safety andreliability, the international aspectof the IRSN’s work develops year onyear.Its major aim is to deepen scientificand technical understanding and todevelop tools for the modelling ofphenomena.By enabling an increase in knowledge and providingadditional tools, especially calculation codes, andoptimising methods, the international cooperationdeveloped by IRSN contributes to a betterunderstanding of radiological and nuclear risks andto improvements in their control. The exchangesand activity are carried out within the frameworkof bilateral or multilateral agreements,programmeslaunched by community or international authorities:European framework programmes for research anddevelopment (FPRD),and projects carried out underthe auspices of the OECD Nuclear Energy Agency(NEA). They also come under the working groupsand committees of the IAEA, NEA, UNSCEAR andthe European Commission, etc. These exchangesand activities lead to conclusions that may haveI R S N ANNUAL REPORT 200473

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESFrench-German Initiative for Chernobyl (FGI): steering committee meetingon 6 October 2004 in Kiev (Ukraine).INTERNATIONAL CONFERENCE ON THEFGI RESULTSOn 5 and 6 October 2004, IRSN, GRS and the Chernobylcentre organised an international conference in Kiev onthe results of the French-German Initiative (FGI) forChernobyl, launched in 1996 by the French and GermanMinisters of the Environment to mark the 10th anniversaryof the accident.This conference was attended by about 200 people from Ukraine,Byelorussia, Russia, the European Union and international organisations(EBRD, EC and IAEA).In fact, while many studies have been carried out in the past, mainly inUkraine, Russia and Byelorussia, on the consequences of the Chernobylaccident from safety, environmental and health viewpoints, the resultswere scattered, sometimes ignored and often heterogeneous.The FGI mobilised numerous teams of scientists around 35 projects.It facilitated the gathering of data, their validation and organisationinto coherent databases that were accessible to public authorities,scientists and the public. The aim was to make available tothe international community a unique tool for the collation and diffusionof scientific information that could be used to model phenomenaand the management of crisis situations and in the developmentof systems to monitor the consequences of an accident on the healthof populations. The data set thus created on the consequencesof the accident is accessible on the website www.fgi.icc.gov.ua.Rostrum at the international conference on 5 and6 October 2004 in Kiev (Ukraine).FOCUSthe advantage of an international consensus.In 2004, the activities of IRSN in this field wereconcerned with the continuation of the projectsin the 5th FPRD, preparation and initiation of new6th FPRD projects, completion of the programmeunder the Franco-German initiative for Chernobyland increasing bilateral collaboration, especiallywith the United States and Russia.Cooperation between IRSN and theCPHR on the study of the Chernobylaccident consequences on thehealth of childrenIn 2004,IRSN and the Cuban CPHR took a first steptowards cooperation on the protection of man andthe environment against nuclear radiation. Thisproject is based on the experience of the CPHR withthe treatment of Ukrainian children irradiated followingthe Chernobyl accident.About 8,000 childrenhave been received in Cuba since 1986 for treatmentunder an inter-government agreement between thetwo countries.In association with the relevant Ukrainianorganisations,the activity was concerned with thestudy and extension of the dosimetric and medicaldatabases for the period 1990-2004.To completethe activity,the medical teams in the Cuban centreof Tarara, where the children were treated, werecontacted.Finally,the current cooperation betweenIRSN and the CPHR in the radiobiology fieldcontinues, with in particular the hosting of twoCuban students in IRSN’s laboratories.Participation by IRSN at the IAEAconference in BeijingIRSN was involved in the international conferenceorganised by the IAEA between 18 and 22 October74I R S N ANNUAL REPORT 2004

IRSN has signedcooperation agreementswith radiation protectionand nuclear safetyorganisationsin 27 countries:Germany, Argentina, Belgium,Byelorussia, Bulgaria, Canada,China, South Korea, Cuba, Egypt,Spain, United States, Finland,Hungary, India, Italy, Japan,Morocco, Czech Republic, SlovakRepublic, United Kingdom, Russia,Slovenia, Sweden, Switzerland,Tunisia, Ukraine.2004 in Beijing on the theme “ContinuousImprovement of Nuclear Safety in a ChangingWorld”. The main aim of this conference was tocontribute to the definition of the Agency’s 2007-2011 programme on the subject of nuclear safetyby promoting exchanges of view in this field.In addition to the presence of nuclear safety experts,this conference brought together numerousmanagers of organisations who came to debatethe major questions associated with nuclear safety.Thus, the IRSN’s Director General spoke on thefollowing subject: “The challenge of sustainabledevelopment in the nuclear field: Research ismore than ever a vital component of nuclear safetyand radiation protection policies.” He stressed inparticular the importance of developing andharmonising risk assessment methods to meetsociety’s expectations in the field of radiologicaland nuclear risk management.More generally,this conference aimed at providinganswers to the questions raised by the deregulationof the electricity markets, the diversification oftechnologies and the globalisation of economies,especially in the fields of quality assurance,knowledge management, the harmonisation ofstandards and safety practices.Participation by IRSN in the 6th FPRDThe 6th FPRD (2002-2006) is directed towardsgreater integration of teams by sharing resources,skills and knowledge, mainly through the creationof long-term networks of laboratories.1st meeting of the SARNET steeringcommittee on 2 April 2004, duringthe 6th FPRD.In 2004, IRSN continued its work under projectsadopted following the first call for proposals:■ the SARNET network of excellence, relating tosevere accidents,headed by IRSN,that coordinatesthe efforts of around 250 scientists in 49 differentorganisations;■ the ERICA project, dedicated to the protectionof the environment against radiation,in which IRSNis participating in the assessment of the radionuclidetransfers into the environment and the resultantrisks;■ the EURANOS project, concerning the conductof the post-accident phase, under which IRSN isworking on the definition of appropriatecountermeasures;■ the NF-PRO project for the behavioural modellingof fission products in the geosphere, with a viewDEVELOPMENT OF COOPERATIONBETWEEN IRSN AND THE NRCFOCUSIn 2004, IRSN and the NRC (United States) increasedtheir bilateral cooperation through numerousexchanges on the subject of the experimentationand modelling of severe accidents.Amongst other things, the NRC decided to participate in the fireprogramme (PRISME) undertaken in the DIVA installation in Cadarache(Bouches-du-Rhône). Similarly, IRSN and the NRC are cooperatingactively in the field of physical protection for nuclear material andinstallations, especially the transport of nuclear materials. In addition,discussions were initiated in October 2004 with the NRC on newexperimental programmes, and especially the SOURCE TERM programmethat, amongst other things, will address subjects associated withthe releases of iodine or fission products. Finally, IRSN and the NRCare continuing their cooperation under the CABRI-water loop programmeon reactivity accidents that can affect pressurised water reactors.I R S N ANNUAL REPORT 200475

RESEARCH AND PUBLIC SERVICE MISSIONSDEFINING AND IMPLEMENTING NATIONAL ANDINTERNATIONAL RESEARCH PROGRAMMESto determining the performance of theircontainment during storage;■ the COWAM 2 project on the governance of risksassociated with waste storage.During 2004, IRSN also participated in thepreparations for two projects in the radiationprotection field,which were adopted under the callfor proposals in 2004. These are CHRONIC RADEND OF THE EUROPEAN ASTRID PROJECTFOCUSThe ASTRID project, set up by the European Commissionunder the 5th FPRD and coordinated by IRSN, wascompleted at the end of 2004.Eight partners participated in this, including the safety authoritiesfrom Finland (STUK), Hungary (HAEA) and Sweden (SKI), and technicalinstitutes such as FzK, GRS (Germany) and VUJE (Slovakia).The first objective of the project was to define an assessment method forthe state of the installation in case of an accident affecting a Europeanlight water reactor (PWR,WER, BWR), in order to structure and harmonisethe technical expert assessment at a European level: this objective wasachieved through the definition of an expert assessment method.The second objective was to develop a computerised crisis tool tosupport the expert assessment method, to diagnose the status of theaffected installation and rapidly assess the releases (real or potential)based on pre-calculated discharges. It should also be able to assess inmore detail the possible developments of an accident, by simulatingthe thermohydraulic behaviour of the reactor, and the emission andtransfers of fission products in the installation. The tool is currently ina pre-operational state: collaboration with GRS will contribute torendering it operational.EPID, a project led by IRSN which addresses theepidemiology of cancers associated with ionisingradiation, and CONRAD, a project dedicated todosimetry.Development of cooperationbetween IRSN and Russian institutesIn 2004, IRSN increased its cooperation with theRussian institutes, that began in the 1990s, underthe agreement between CEA and the RussianMinister for Atomic energy (Minatom nowRosatom).This cooperation now covers a wide field: humanprotection, criticality, design and safety of liquidmetal reactors, fuel and severe accidents in waterreactors.As far as human protection is concerned,the subjectscover the study of the tissue banks of irradiatedvictims as well as an assessment of the pathologiesthat could result from chronic contamination bycaesium.2004 was also notable for an increase in cooperationin the crisis management field between IRSN andRosatom.Activities will include the comparison ofcrisis management procedures,including tools,theorganisation of international crisis exercisesconcerning the transport of nuclear material,participation in exercises in France and Russia andthe response strategy in an emergency situationor during the post-accident phase.76I R S N ANNUAL REPORT 2004

Full meeting of the International Commission for RadiologicalProtection (ICRP) in Beijing (China) in October 2004.New recommendations concerningradiation protection2004 was marked by the consultationprocess initiated by the ICRP with professionalsin the radiation protection field,national authorities, international organisationsand more broadly the general public, to listen totheir opinions on the draft for new generalrecommendations concerning radiation protection.The radiation protection doctrine is developed atinternational level within a range of scientific,technical and regulatory bodies. According to theterms of reference of the relevant internationalagencies, IRSN specialists participate in this workeither as experts or as part of their public servicerole or in support of the authorities. It must beremembered in this context that ICRP publicationsserve as a basis for the drafting of internationalregulations, especially the European directives andthe core standards of the IAEA. The internationalbodies involved are:UNSCEAR,ICRP,IAEA (RASSC),Euratom (groups of experts under articles 31 and37),NEA (CRPPH),IUR and organisation for radiationprotection standardisation (ISO,IEC).In this context,IRSN has increased and structured its internal andexternal consultation process.Within the Institute,a network was installed in 2004, linking the IRSNspecialists involved with international authorities,as well as the representatives of the directoratesconcerned. Amongst the seminars organised,the first, for which preparations were made in2004, was held on 27 January 2005 and involveda presentation of the draft for futurerecommendations by the IRSN’s representativesparticipating in the work of the ICRP. Externally,the Institute has set up a pluralist working groupwhose aim is discussion with the players involved(authorities,industry,associates,institutions).Thisgroup met twice in 2004 and was able to distributeinformation on the work of the ICRP and othermajor international agencies concerned withradiation protection.Finally,to parallel the changesin radiation protection doctrine, IRSN wanted toexamine in more depth certain much-discussedsubjects,such as the effects of low doses (especiallyfollowing the publication by non-institutionalexperts of a report calling into question the methodused by the ICRP to estimate the risks associatedwith internal contamination) and the concept ofenvironmental protection,with the aim of updatingthe Institute’s position.Concerning environmentalprotection, it must be emphasised that, up to now,the approach has been characterised by the ICRP’shypothesis that man was the creature that was themost radiation-sensitive, and that the measurestaken to protect humanity should guaranteeprotection for the environment. Over the decade,the lack of scientific demonstration of thisstatement and the rise in influence of environmentalpreoccupations, as demonstrated by numerousinternational conferences, has led to a reexaminationof this hypothesis. It thus becameimportant for the Institute,which is one of the feworganisations in the world to undertake researchinto radioecology,to prepare a doctrinal statementin this field.Furthermore,IRSN has undertaken thetranslation into French of the first publication ofthe ICRP dedicated to this subject (publication 91issued in 2003 and entitled “A framework forassessing the impact of ionising radiation on nonhumanspecies”).I R S N ANNUAL REPORT 200477

RESEARCH AND PUBLIC SERVICE MISSIONSCONTRIBUTING TO TRAININGIN RADIATION PROTECTIONA radon metrology training session in Le Vésinet (Yvelines).Contributing to trainingin radiation protectionOne of the missions assigned to IRSN when it was formed was to contribute to the radiation protection trainingof health professionals and those who are exposed in the course of their work. This activity is based on arecent regulation aimed at ensuring that greater account is taken of the risks to which professionals are exposed.An activity to help prevent risksand their possible consequences20training sessionsorganised and completedAs a research and expert assessmentestablishment, IRSN has a duty toprovide training and to contribute toteaching in the areas in which it hascompetence: nuclear safety andradiation protection.The ultimate aim of this training and education isnot only to provide theoretical knowledge,but alsoto promote tools and methods aimed at minimisingnuclear and radiological risks in all the activity areasunder consideration.Training and education mustcontribute to promoting prevention and theytherefore demonstrate the social worth of theInstitute to those economic, industrial orinstitutional players involved in these risk-bearingactivities.It is for this reason that,apart from the participationof IRSN agents in teaching during the universityyear – long recognised as effective –, the decreerelating to the missions of the Institute focuseson the professional radiation protection training.It targets specifically medical or paramedical staffinvolved with medical imaging or therapy usingionising radiation. This explicit mention of themedical sector echoes the preoccupations of thepublic authorities and the recent development oflegislation and regulations aimed at providinggreater protection for personnel and patients.In this context, IRSN must:■ continue, or increase, its presence on universityor school courses by giving priority to a specifictraining project concerning nuclear safety andradiation protection;■ create the conditions for the development ofa sector for professional training aimed at thevarious professional categories concerned anddemonstrating the Institute’s involvement in “handson” prevention.Following the creation within IRSN of a pole forprofessional training, 2004 was set aside forconsideration of a strategy to be implemented78I R S N ANNUAL REPORT 2004

on this subject and for the setting-up of a rangeof training activities for specific categories ofprofessionals.In strategic terms,the aim was to set developmenttargets taking into account the IRSN’s referencerole in nuclear safety and radiation protection,identify partners,classify the categories of priorityprofessionals and finally reconcile the trainingquality with the economic balance of an activitythat relates to a competitive sector.The first training modules completed in 2004 wereselected on the basis of expressed requirementsand their feasibility. The priority categories wereworkers exposed to ionising radiation: IRSNemployees, approved organisations tasked withmeasuring radon in establishments open to thepublic, company doctors and persons tasked withmonitoring workers’ dosimeters, as well as thefactory inspectorate.At the request of the local information commissionin Saclay (Essonne), a course on “radiationprotection, citizenship and governance” wasarranged for its members, local elected representatives,representatives of associations andteachers. Finally, several specific activities to raiseawareness were arranged in the hospital sector,forerunners of more sustained activity during 2005.In 2004, all the sessions were organised by IRSNmanagement. Several other offers were made oftraining in radiation protection in the medical field.These offers may be supplemented by sessionsarranged at a client’s request. Several dossiersof this type investigated in 2004 should cometo fruition in 2005.TRAINING ON RADONFOCUSSince 2004, IRSN has been organising training courseson the radon metrology for any organisation wantingto participate in an approval scheme for radonmeasurement in locations open to the public. Thistraining has been made necessary by recent changesin legislation in this area.The new French regulations relating to the management of risksassociated with radon, following on from the directive 96/29/Euratom,introduce an obligation for owners of locations open to the publicto “implement measures to monitor exposure to natural radiationwhere these are likely to affect health”. These measures must beimplemented by IRSN or by an approved organisation (decree dated15 July 2003). Obtaining approval issued by the Minister for Healthin the light of a recommendation from the national approvalcommission is subordinate, amongst other things, to the provisionof proof that the organisation has achieved competence eitherthrough practical experience or by attending specialist trainingin the radon metrology.The aim of the training is to familiarise students with the varioustechniques for detecting radon as well as the investigationsrequired when the presence of this gas has been demonstrated.In 2004, more than fifty requests for approval were submittedto the commission and IRSN trained around 20 students.Four training sessions are planned for 2005.Trainees receive a combination of theoreticaland practical training.I R S N ANNUAL REPORT 200479

RESEARCH AND PUBLIC SERVICE MISSIONSCONTRIBUTING TO TRAININGIN RADIATION PROTECTIONEach training session is attended by about 15 external participants.Training sessions carried out in 2004Subject of sessions Session Number Target audience Numberor professional duration of sessions of studentstraining activity in 2004 trainedRadon metrology 3 days 2 Approved organisations, housing experts 21Dosimetry management 2 days 2 Industrial medical officers, 12at workradiation protection officersTraining in the radiation 1 day 7 Exposed personnel 110protection of exposed workersRadiation protection inspection 3 days 2 Factory inspectors, 40in a work environmentmedical inspectorsRaising awareness 1 day 6 Hospital doctors and personnel, 80in a medical environmentindustrial medical officersRadiation protection, 1 day 1 Elected representatives, CLI members, 25citizenship and governanceteachersTOTAL 20 28880I R S N ANNUAL REPORT 2004

Real-time radiological monitoring of Frenchterritory in the warning systems remotemonitoring room in Le Vésinet (Yvelines).Permanent monitoring in mattersof radiation protectionThe public service missions assigned to IRSN relating to radiation protection concern the radiological monitoringof the environment in France, assessment of human exposure and management of radiation sources.Radiological monitoringof the environmentRadiological monitoring of theenvironment is provided by IRSN,usingtelemetry devices and laboratoryanalysis of environmental samples. Itoperates throughout the territory usingstations that may or may not be locatedclose to facilities that could dischargeradionuclides into the environment.The remote monitoring networksThese provide real-time radiological monitoring ofthe environment by means of self-containedbeacons that continuously measure the radioactivityof the area where they are located. In more detail,two networks provide air monitoring (Téléray forthe ambient gamma dose rate and DARA foratmospheric dust). Two other networks monitorthe water (Hydrotéléray for rivers and Téléhydrofor wastewater in towns).Once an increase in radioactivity is detected, awarning is sent to IRSN and an initial investigationis mounted. There were a dozen trips of Téléraybeacons in 2004: most were of meteorologicalorigin or resulted from the near proximity of thebeacons to a transport of radioactive containers.In addition, the year 2004 saw the setting up of a“supervisor”enabling all the data from the remotesensing network to be centralised on a serverindependent from the establishment server.In parallel,most of the equipment was modernised with aview to improving data acquisition and processing.The sampling networksThese supplement the environmental monitoringby taking measurements on samples from variousenvironmental locations. In 2004, 32,727 sampleswere analysed. The samples are taken by IRSN ortechnical associates (DDASS,French Navy,Météo-France, EDF, COGEMA, etc.).They enable changesin activity level to be monitored in the variousenvironments to which the public is exposed.Sometimes, these networks may reveal abnormalsituations and they enable the consequences tobe estimated.This was the case in 2004 for a specialstudy relating to the consequences of the floodconditions on the Rhône in 2003.500sampling pointsacross the country1,000dosimetricmeasurement points213beacons making upthe territorial remotemonitoring networkNearly100,000radiological analysescarried outI R S N ANNUAL REPORT 200481

RESEARCH AND PUBLIC SERVICE MISSIONSPERMANENT MONITORING IN MATTERSOF RADIATION PROTECTIONEnvironmental monitoring by radiation monitors is completed by a network of manualsampling operations.Towards an optimisation ofmonitoring and greater visibilityIn order to improve the management of the massof data acquired by these networks, IRSN hasinitiated work aimed at developing a uniquecomputer management tool. Discussions began in2004 to identify the exact role of this monitoring.This will lead to a redeployment of resources in theyears to come.Finally, a new website (http://eau.irsn.org/) wenton line at the end of 2004.There,the general publiccan find the data relating to the radiologicalmonitoring of the various aquatic mediums(seawater, rain, rivers, subterraneanwaters, etc.).The permanent monitoringmission requires from thelaboratories a rigour in sampleanalysis that the Institutewants to inculcate by meansof accreditation to its instrumentationlaboratories (seeQuality chapter, part 3).managing a network spread over seven islands(Tahiti,Maupiti,Hao,Rangiroa,Hiva Oa,Mangarevaand Tubuai). The total area covered by thismonitoring is equivalent to that of Europe. Thesampling strategy adopted makes it possible todetermine the exposure of individuals eitherexternally, by inhalation or ingestion.The primaryeffort addresses the latter component, for whicha sampling plan was established based on anutritional study updated in 1991.The radioactivityanalyses cover gamma, strontium and plutoniumemitters.Caesium 137,detected at very low activitylevels in virtually all the 400 samples taken, is thepredominant radionuclide. The last dosimetricanalysis carried out by IRSN concerned 2003.Thetotal “added” dose attributable to fallout fromatmospheric testing is less than 5 µSv per year.IRSN prepares an annual report that is availableon the Institute’s website.Inside a SARA monitor (automatedaerosol radioactivity monitoring device).Environmentalmonitoring in FrenchPolynesiaIn 1962,France set up a radiologicalmonitoring network inPolynesia. Since 1976, theInstitute has itself been82I R S N ANNUAL REPORT 2004

Team from the source expertise unit.Monitoring ionising radiation sourcesConcerning the monitoring of ionisingradiation sources,IRSN carried out thefollowing principle operations in 2004:■ technical examination of 18 initial or renewalrequests for authority to hold or distribute sources,in response to tasking from the competentauthorities (DGSNR,AFSSAPS,DSND,prefectures);■ technical examination of three requests fordispensation from CAMARI (certificate attestingthe ability to handle radioscopy and industrialradiography equipment) at the request of thedepartmental labour directorates;■ provision of advice on four technical or regulatorysubjects associated with the use of ionising radiationsources:- exemption criteria for industrial electricalgenerators;- draft decree on the monitoring of the movementof sources;- European equivalences of the radiation protectionofficer;- categorisation of sealed sources in accordancewith the IAEA and in accordance with EuropeanDirective 2003/122; application to the case ofFrance.In addition,the following statistics for 2004 illustratethe magnitude of the task that has been assignedto IRSN of managing the national inventory ofionising radiation sources:■2,400 authorisations issued, renewed ortransferred between authorities;■ 4,700 requests for the supply of sealed sources;■ 1,500 requests for the supply of unsealed sources;■ 3,300 recovery certificates;■ 460 requests for the export of sources;■ 300 requests for the import of sources.The large number of authorisation requests thatwere subject to modifications in 2004 can beexplained by transfers of skills between authorities.Such changes have to be transferred by IRSN tothe national inventory.I R S N ANNUAL REPORT 200483

RESEARCH AND PUBLIC SERVICE MISSIONSPUBLIC INFORMATIONTravelling exhibition at La Rochelle in June and July 2004.Public informationOne of the IRSN’s missions is to provide information to the public about radiation protection and nuclearsafety. To achieve this, the Institute has developed a range of activities to enable it to provide answers tosociety’s concerns about the technical and health risks associated with nuclear matters. There is also a needto respond to the public’s desire for involvement in the subject. This policy shows that the Institute is ready tolisten to the concerns of society.Information and communicationactivitiesRoad show“Nuclear under closesurveillance”6,500visitors including1,120 students;4 towns visited15conferencesorganised778requests forinformationprocessedvia the contactbox on the website12,000copies ofthe annualreport issuedInformation activities undertaken byIRSN in the field of radiation protectionand nuclear safety have to contributeto the education of the public on risksand their prevention.They also enablethe Institute’s scientific output andactivity to be promoted.Information for the general publicIntended primarily for the general public and forstudents, the road show entitled “Nuclear underclose surveillance” was conceived in partnershipwith DGSNR. This interactive and educationalexhibition addresses by means of panels, models,computer games and videos,the numerous subjectsassociated with nuclear matters: radioactivityand health,nuclear reactors,the Chernobyl accident,the fuel cycle. Each year, it visits any locality thatsubmits a request. In 2004, the exhibition visitedSaint-Dié (Vosges), Metz (Moselle), La Rochelle(Charente-Maritime), Martigues (Bouchesdu-Rhône):a total of 6,500 visitors including1,120 students, during 25 weeks of operation. Inparallel to the exhibition,series of scientific lectureswere organised on subjects of general interest:the Chernobyl accident,radioactive waste,nuclearinstallations and earthquakes, nuclear powerstations under extreme climatic conditions,ionisingradiation and health.IRSN participated in a range of events aimed atraising public awareness of the challenges facedby science. Thus, on 25 May, on the occasion ofthe open day at Croissy-sur-Seine (Yvelines), theInstitute welcomed a large number of visitors toits laboratories in Le Vésinet. Workshops wereavailable on the measurement and monitoring ofOpen day on the Le Vésinet site in May 2004.84I R S N ANNUAL REPORT 2004

Travelling exhibition for junior high school pupils.radioactivity in the environment,intervention andassistance in radiation protection.Similarly, IRSN participated in the “Science Fair”(15-17 October). This event aimed to familiarisevisitors with science and technology and to helpimprove their understanding of the challenges ofresearch. The Institute had a stand in the ScienceVillage installed by the Ministry in the Luxembourggarden.16,000 people visited the Village.IRSN alsotook part in the events organised by the local councilin Clamart (Hauts-de-Seine) during a conferenceon 15 October on nuclear matters and the healthapplications of ionising radiation.Information for professionalsIRSN participates in exhibitions and conferencesto provide information for professionals in theenvironmental, health and nuclear safety fields. In2004,the Institute exhibited its radiation protectionexpert assessment activities at specific conferencesand exhibitions: doctors (MEDEC, 16-19 March),radiologists (open days of the French radiologicalsociety,1-2 October),radiation protection officers(congress of the SFRP, December). At the MEDEC,the Institute jointly organised on 17 March aconference on “health effects resulting fromradiation of the foetus and the infant”. IRSN alsoparticipated in the 11 th Congress of the IRPA (23-28 May), held in Madrid (Spain). At this congress,that every two years brings together the expertsin the field, IRSN scientists presented their recentwork and the Institute had a stand.In addition, the Institute participated in Pollutec(30 November-3 December),a trade fair for environmentalprofessionals, where its stand provideddetails about the services,nuclear-related and otherwise,thatit can offer to industry and local authorities.Finally, the 6th EUROSAFE forum that was held inBerlin on 8 and 9 November 2004:this was organisedby IRSN and GRS and brought together experts innuclear installation safety, waste management,radiation protection and nuclear material safety(see Focus p. 86).InternetThe Internet is a major vehicle for informationand cannot fail to develop further. The Institute’swebsite was created in 2002 and saw its usage risesignificantly in 2004,with more than 690,000 hits,or an average of 25,000 single visitors per month,mainly professionals.The main activity on the sitein 2004 involved a programme of informationpublication and update and improvements in thegraphical identity of the Institute’s thematicsites. In addition to the information provided onthe institutional site, IRSN administers specificsites, mainly linked to databases or projects beingmonitored by the Institute: scientific site, SISERI,CRISTAL,portal on environmental monitoring,etc.Work has also begun on the contact box,to improveit and to ensure that visitors’requests are answeredas well as possible. Finally, consideration is nowbeing given to a rebuild of the site to make it aportal site, structured by the public.IRSN’s stand at the Pollutec exhibition in Lyonin December 2004.Participation in5professional exhibitionsand public events30,000information bookletsand 4,500 trainingpamphlets distributed55,548visits in 2004,to the IRSN’sscientific site,or about 2,000 singlevisitors per monthI R S N ANNUAL REPORT 200485

RESEARCH AND PUBLIC SERVICE MISSIONSPUBLIC INFORMATIONNucléon guides members to help them discover IRSN.EUROSAFE 2004 FORUMOn 8 and 9 November 2004, IRSN and GRS jointlyorganised in Berlin the 6th EUROSAFE forum onthe subject: “Learning from experience – a cornerstoneof nuclear safety.”EUROSAFE is the fruit of a European initiative in 1999 by IRSN andits German opposite number GRS; its aim is to promote convergencein the technical practice of nuclear safety across Europe. It is basedon an annual forum, a half-yearly scientific and technical magazineand a website.The forum was attended by about 450 experts from technical safetyorganisations, research institutes, regulatory authorities, electricitycompanies, industry, public authorities and non-governmental organisationsfrom the European Union, Switzerland and Eastern Europe.Intended to foster closer collaboration between technical safetyorganisations, these scientific and technical days offer the chance eachyear to debate matters relating to experience gained in nuclear safety.The latest work by IRSN, GRS and their partners in the European Unionand Eastern Europe was described.All information on the forum, the texts of the presentations and issuesof the EUROSAFE tribune are available at www.eurosafe-forum.org.The next forum, organised jointly by AVN, IRSN and GRS, will be heldin Brussels on 7 and 8 November 2005.The Eurosafe forum in November 2004 in Berlin.P2_M1_P86ZFOCUSFor scientific communication, the rebuildingof IRSN’s scientific website (http://net-science.irsn.fr/)has been initiated to improve its ergonomics andreadability.The aim of this site is to ensure that the Institute’steams and work are known. The new version isexpected to be on line at the end of the first halfof 2005. Action has also been taken to ensurethat the site is listed by Internet search engines.PublicationsIn 2004, IRSN continued to publish informationdocuments intended for the general public,professionals and scientists. In this way, IRSNprovides the public with a collection of pamphletson radioecology, the transport of radioactivematerials, radon, radioactive waste, etc. In 2004,this collection was supplemented by a newdocument on caesium.A collection entitled “The professionals collection”has also been created and six pamphlets updatedand distributed at the exhibitions and conferencesattended by the Institute. These address thefollowing subjects:■ aiding medical teams following radiologicalaccidents;■ medical exposure to ionising radiation;■ ionising radiation and health;■ services provided in non-nuclear fields;■ operational radiation protection, services andexpert assessments;■ response to a nuclear accident.Similarly,the collection of IRSN scientific bookletshas been updated and developed, and three subcollectionscreated. Lignes directrices consists ofguides or booklets of recommendations, such asthe completely new publication Vos patients et les86I R S N ANNUAL REPORT 2004

Information is provided for the general public bythe IRSN travelling exhibition.rayons, un guide pour les médecins praticiens, atranslation of the ICRP publication Radiation andyour patient:a guide for medical practitioners;IRSNis here fulfilling its public service role by the freedistribution of this guide to the medical world.Colloques contains contributions to the symposiaor conferences organised or jointly organised byIRSN (in 2004 for example ECORAD). Sciences etTechniques brings together the sum total ofknowledge of radiation protection or nuclear safety.These publications are coordinated and for themost part written by IRSN scientists, withparticipation from one or several external authors.The quality of these works is guaranteed by aneditorial committee.Finally, each year IRSN publishes its annual reportdistributed to higher authorities, opinion formersand to points of contact in the press andassociations, both in France and internationally.In 2004, 9,000 copies of the French version of the2003 annual report were produced, and 3,000 ofthe English version.I R S N ANNUAL REPORT 200487

9national nuclearcrisis exercises(civilian sector)2actual mobilisationsof IRSN’s EmergencyResponse Centre24meetings heldby standingadvisory groups88I R S N ANNUAL REPORT 2004

IRSN ACTIVITIES IN 2004Technical support andassistance for publicauthoritiesIRSN carries out its work in a spirit of partnership with the public authorities,whether acting on behalf of the authorities (technical assistance) orproviding technical support.For IRSN, the key to progress in the fields of expert assessment and technical supportlies in the pursuit of technical dialogue with manufacturers and the formalisationof the Institute’s technical approach by publishing policy documents.> 90 Technical support with regard to nuclearand radiological risk> 128 Operational support in the event of a crisisor radiological emergencyI R S N ANNUAL REPORT 200489

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKIRSN analyses technical dossiers supplied by EDF.Technical support with regardto nuclear and radiological riskAt the request of the authorities, IRSN assesses technical dossiers submitted by operators. These dossiersconcern the safety of reactors, plants, transport and dismantling as well as waste management and preventivemeasures with regard to earthquakes. They also concern radiation protection of persons and the environment.The Institute analyses all the risks and draws up reports on the provisions proposed to control them. Those reportsare then transmitted to the authorities or standing expert groups.608technical reportsto the public authorities(excluding defencerelatedactivities)Participations in nearly600BNI inspections107test reports issued oncross-comparison studiesof environmentalradioactivitymeasurements150,000workers monitored byexternal dosimetry21,089radiotoxicologicalanalyses125anthropogammametricanalysesReactor safety analysisIRSN provided support for DGSNR inassessing the operating safety andradiation protection of the 58 reactorson French nuclear power plants. Inparticular, the Institute examined therisks of clogging of sump filters and theprotection of those reactors from externalhazards.It also assessed the safetyof the EPR nuclear reactor projectand followed up experimental reactors.Assessment of pressurised waterreactors (PWR)IRSN provides support, in particular, for theexamination of work and inspection programmesconducted during refuelling shutdowns, theexamination of general operating rules,participationin monitoring inspections and the analysis offeedback.IRSN also contributes to the areas coveredby reactor safety reviews. It examines datasubmitted by EDF on those topics,jointly with EDF,and reactor safety reviews requested by DGSNRin the context of 10-yearly outage programmes.Examination of work and inspection programmesconducted during refuelling and reactor maintenanceshutdownsIn the course of 2004,IRSN conducted examinationsduring some 40 shutdowns lasting between threeand eight weeks.In each case,the Institute studiedthe work and inspection programmes planned bythe operator,followed-up the performance of thoseoperations and examined the results of start-uptests.Examination of general operating rulesThe operator modifies the technical operatingspecifications (STE) and periodic test regulationsaccording to the modifications implemented onreactors and feedback received. IRSN gives itsopinion on the acceptability of these documentsfrom the safety point of view. Moreover, in 2004,IRSN issued about 100 reports on acceptabilityof EDF requests for concessions with regard totechnical operating specifications (STE) for variousreasons (operating contingencies, equipmentunavailability, etc.). In this context, after the heat90I R S N ANNUAL REPORT 2004

The Fessenheim nuclear power plant (Haut-Rhin).wave in summer 2003, IRSN analysed an STEamendment dossier aimed at relaxing someoperating requirements concerning the maximumtempera-ture inside the reactor building and theannual scheduled outage time authorised for thecleaning of some heat exchangers. In the case ofthe latter, IRSN was unable to approve the DGSNRproposal in view of the supporting evidence provided.severity in terms of risks of damage to the reactorcore (see Focus p. 99). Furthermore, IRSN sendsreports on the most significant incidents to theIAEA in accordance with the terms of theinternational “Incident Reporting System”.■A quarterly meeting is held between EDF,DGSNRand IRSN to identify events of a generic natureconcerning power plants and to give advice on how15dose assessmentsby biological dosimetry134assessments of humanradiation protectionReactor safety reviews and corresponding safetyreportsDuring 2004, IRSN continued safety reviews on900-MWe and 1,300-MWe reactors with a viewto conducting third and second 10-yearly outageprogrammes,respectively.Every reactor undergoesa safety review every 10 years.This review entailsverifying that power plants are maintained incompliance with baseline requirements on designand operation, and the study of possible changesin those baselines and corresponding modifications.The purpose of these modifications is to improvereactor safety.They are based on feedback received,new knowledge obtained and new safety provisionsadopted for the most recent reactors wheneverthat is technically feasible and there is a significantgain in terms of safety.Analysis of reactor operation feedbackIRSN examines feedback on reactor operation fromvarious points of view including,in particular,eventsand anomalies.■ The 681 significant events reported by EDF in2004 were examined and are described in acomputer database.The incidents that were mostcharacteristic of safety failings were, or will be,submitted to thorough analysis and, in somecases considered to be precursors, probabilisticstudies will be conducted in order to assess theirINCIDENT AT FESSENHEIMFOCUSAn error in the configuration of a pipe system on4 January 2004, due to inadequate preparationof a servicing operation led to the entry of resinsinto the primary cooling system of reactor 1at the Fessenheim power plant (Haut-Rhin).Although the system was quickly returned to compliance, the resinscaused clogging of the sampling lines resulting in the loss of automaticmonitoring of the concentration of boron in the water in the primarycooling system and several filters on the injection line at primary coolantpump joints which led to loss of the injection function. The numerousfilter replacement operations required to recover the injection functionled to the contamination of seven persons. IRSN examinedthe methods proposed by EDF to shut down the reactor and,more particularly, the risks posed by the presence of the resins inthe systems with regard to cooling (blocking up pipes) and availabilityof the reactor’s shutdown rod cluster control assembly (jamming duringdrop). IRSN then examined the results of inspections on the equipmentconcerned (pumps, measuring sensors, reactor control rods) andthe monitoring programme proposed by EDF to follow up the changesin various parameters during the next operating cycle. IRSNrecommended that EDF should pay special attention to the rod droptime and the fouling of some filters which could be due to the presenceof resin residues. A thorough analysis of this event was started by IRSNand will form the subject of a report in 2005.I R S N ANNUAL REPORT 200491

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKManagement of significant events.A cable fire breaks out in a trough supporting electricpower cables for reactor 2 at the Cattenom power plant(Moselle) during start-up.The fire is brought under control by the fire brigade andthe PUI and the radiological PUI are triggered.The IRSN emergency response centre is mobilised.The reactor is shut down in accordance with the applicableprocedures.to deal with them. In this context, EDF and IRSNdraw on lessons learned from events that haveoccurred in foreign power plants.■ Every three years,an assessment of reactor operationfeedback for power plants in service is presentedto the standing advisory group for nuclear reactors(see Focus p. 94).■ In 2004,IRSN developed statistical event analysistools which can be used to generate indicators inorder to obtain an overview of changes in safetyat power plants in operation.Monitoring inspectionsIn 2004, IRSN supported basic nuclear installationinspectors in the preparation of nearly 300 moni-INCIDENT AT CATTENOMFOCUSA cable fire broke out in a trough supporting electric power cables for reactor 2 at the Cattenom powerplant (Moselle) during start-up on 16 May 2004. The fire was brought into control by the fire brigadeand the internal emergency plan (PUI) was triggered. The IRSN Emergency Response Centre wasmobilised (see Focus p. 129) and the reactor was shut down in accordance with the applicable procedures.Owing to the potential safety consequences of such an incident, IRSN conducted in 2004, a detailed analysis focusing on thefollowing aspects:■ design: the incident was caused by the heating of 6.6 kV cables from the coolant pumps to the condenser. The pump motorsfor the Cattenom plant units required a power of 9 MW, instead of 5 MW as in the case of other 1,300-MWe reactors.The cables were not correctly dimensioned, however, and the trough concerned had recently been closed followingmodification work: as a result, the heat generated could no longer escape satisfactorily. The damaged cables were replacedbefore restarting the reactor and the troughs were re-opened on a temporary basis. It is planned to install cables with a largercross section on the site’s other plant units in order to prevent them overheating;■ management of the fire alert: the rapidity and effectiveness of external emergency actions were evaluated;■ human factors: the control of the reactor in these circumstances was examined;This analysis will form the subject of an IRSN report scheduled for release in 2005. This event was reported to the IAEA.In addition, IRSN assessed the steps taken by EDF for the restarting of the reactor and recommended that a cable and troughtemperature monitoring programme should be implemented by EDF.92I R S N ANNUAL REPORT 2004

Power plant at Belleville-sur-Loire (Cher).toring inspections on EDF reactors. IRSN accompaniedthe inspectors for some of those inspections.INSULATION DEFECT ON VALVEACTUATORSFOCUSRisk of clogging of containmentsump filtersClogging of sumps by debris originating,in particular,fromheat-insulating materials following a breakon the primary cooling system can jeopardisecore cooling in the long term. For this reason, EDFconducted a study on design modifications toprevent this risk. Early in 2004, EDF put forward adossier of assumptions it had adopted in order todefine modifications to be made to all French powerplants:the implementation of those modificationsis scheduled to start in 2005.After examining thisdossier, IRSN presented its conclusions to thestanding advisory group for nuclear reactors on22 December 2004.In drawing up this report,IRSNtook into account the first results of an experimentalpro-gramme it launched to evaluate the risk ofchemical compounds being formed during therecirculation phase in the long term.The advisorygroup decided that some assumptions requiredfurther confirmation by EDF but that the solutionsit had adopted should be implemented as quicklyas possible on power plants.Protection of reactors againstexternal hazardsIn this field, the year 2004 was mainly dedicatedto pursuing safety assessments regarding theprotection of reactors against floods of externalorigin. In this context, the maximum design floodlevels and the dossiers of the plants at Belleville(Cher) and Le Bugey (Ain) were examined. Thesewere considered to be priority sites owing to theconsiderable reinforcement of existing protectionsystems planned by EDF. This provided IRSN withthe opportunity to express its opinion on theAn insulation defect was revealed, in September 2003,by accidental spraying of two valve electrical splice boxeson reactor 2 at the Penly power plant (Seine-Maritime).The valves concerned, located inside the reactor building, must be ableto operate in degraded ambient conditions including, in particular, whenthey are exposed to spraying. In the course of inspections conductedduring the subsequent shutdown of the reactor, in early 2004,the operator detected cuts in the insulating material on the electric wiressupplying power for the valves. The inspection of other actuators subjectto the same qualification requirements revealed a large number of similardefects.These defects were liable to jeopardise the operation of the actuators inan accident situation, i.e., emergency shutdown in safe condition.Furthermore, these defects may have concerned reactors at other powerplants. For this reason, IRSN sent DGSNR a report, in 2004,recommending the inspection of all existing reactors during shutdowns.EDF subsequently confirmed the generic aspect of the defects, this beingdue to incorrect utilisation of the insulation removal tool before makingconnections.Owing to the extent of the corrective work to be performed on reactors,IRSN recommended focusing on the minimum number of actuators ata first stage. The Institute took into account the respective weightsin the probability of core meltdown and of the risk of a defect on a singleactuator leading to failure of an entire electric switchboard and, thus,all the actuators depending upon it.An insulation problem occurred on reactor 2at the Penly nuclear power plant(Seine-Maritime) in September 2003.I R S N ANNUAL REPORT 200493

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKExperts in flooding hazards.EXAMINATION OF FEEDBACKFROM 2000-2002On 2 December 2004, IRSN presented the standingadvisory group for nuclear reactors with its conclusionson the examination of feedback from the operationof PWRs over the period 2000 to 2002.This examination, conducted every three years,provides the opportunity to conduct a transverseinvestigation on safety-related matters highlightedduring the relevant period.The following topics were dealt with in 2004: processingof significant safety-related events, analysis of the applicationof technical operating specifications, analysis of start-up testsand periodic tests, analysis of electrical switchboard failures,measurement deviations from flow and temperature sensors,reliability of diesel generators and feedback from instrumentationand control equipment for 900 MWe and 1,300 MWe plant units.The conclusions of the report submitted to the standing advisorygroup for nuclear reactors (GPR) indicate that EDF must carry outa number of actions in order to improve safety with regard tothe topics examined, especially measurement deviations on flowand temperature sensors.IRSN examines feedback on PWR operation.FOCUSplanned reinforcement measures and on thetemporary measures proposed by EDF to cover theperiod pending the completion of modificationson the plants. The improvement of operatingdocuments was also examined in 2004.Internal emergency plans (PUI)A new standard was defined in 2003 for internalemergency plans at EDF power plants. Work onexamining the corresponding dossiers wasvigorously pursued in 2004:Cruas (Ardèche),Chinon,Le Bugey, Nogent (Aube), Penly (Seine-Maritime),Gravelines (Nord) and Saint-Alban (Isère). Duringthe year, work was completed on the examinationof the EDF dossier recommending the setting upof a specific internal emergency plan organisationto deal with floods liable to affect all the reactorson a single site.Assessment of the safety of the EPRnuclear reactor projectFollowing the drawing up of “Technical Guidelinesfor the Design and Construction”(in October 2000)and pending a request for authorisation to proceed,IRSN is continuing to examine the safety of theEPR project on the basis of technical dossiers:■ connected with the compliance with generalsafety objectives;■ concerning innovative technical solutions (coriumrecovery, computerised instrumentation andcontrol, etc.);■ which have changed since the technical directives(containment with metal liner, etc.);■ describing changes concerning power plants inoperation (with regard to floods, heat waves, etc.),for the EPR project.During 2004,a set of EDF technical dossiers concerningthe EPR project were examined by IRSN and94I R S N ANNUAL REPORT 2004

Aerial view of the future EPR site at Flamanville (Manche).were presented and discussed during meetings ofthe standing advisory group for nuclear reactors.These dossiers concern:■ the Teleperm XS computer platform which willbe used to develop the reactor protection system;■ the new containment design comprising aprestressed concrete internal containment with ametal liner and a concrete external containment;■ improvement of worker radiation protection;■ computerised control principles;■ design of the corium recovery system (seeFocus p.105),to maintain the reactor’s containmentintegrity in accident situations involving coremeltdown;■ accident situations involving heterogeneousdilution of the boron in the primary cooling system;■ the design of the safety injection system;■ the processing of non-qualified multiple equipmentfailures in case of earthquake;■ foreseeable combinations of internal and externalhazards and internal events to be taken into accountfor reactor design.EDF’s technical dossiers concerning allowance forthe risk of impact by a commercial aircraft wereexamined and discussed at a meeting of therestricted group responsible for nuclear reactors.EPR REACTOR: COLLABORATION WITH FINLANDFOCUSIn December 2003, following the decision by the Finnish council of state to build a fifth nuclearreactor in Finland, the operator, TVO, decided to construct an EPR-type reactor and applied tothe Finnish Government for permission to build.The dossier was submitted to technical examination by the Finnish safety authority (STUK) in 2004.STUK held technical discussions with DGSNR and IRSN during 2004 to consider modifications to the EPR projectwhich could be requested by STUK on the basis of Finland’s current regulations regarding the safety of nuclear reactors.These discussions focused, in particular, on theprevention of failures for main pipes of the primaryand secondary systems, the limiting of the consequencesof accidents involving failure of steam generator tubes,the design of the corium recovery system, and digitalinstrumentation and control. Efforts were made toharmonise the positions on these various topics.The Finnish Government granted permission to buildin February 2005. In-depth discussions will be continuedwith STUK during subsequent EPR project developmentand implementation phases in Finland and in France.The EPR project in progress on the Olkiluoto site inFinland.I R S N ANNUAL REPORT 200495

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKDiscussions and explanations on the CABRI installation with an IRSN reactorsafety team.SAFETY OF THE CABRIEXPERIMENTAL REACTORIn 2004, IRSN examined the preliminary safety reportsubmitted by CEA to support its request for modificationof the CABRI installation.This examination covered the following points in particular:■ the design and dimensioning of the pressurised water loop whichwill be placed at the centre of the reactor core;■ the utilisation of zircaloy for the manufacturing of the in-pilesection of that loop;■ the seismic reassessment of the installation;■ the list of operating conditions adopted for the safetydemonstration;■ the radiological consequences of envelope accidents retained.IRSN’s analysis took the specific features of the CABRI reactor intoaccount:■ it is not constantly in operation (a few days a year only);■ the first barrier of the loop is the vessel containing the pressurisedfluid (the experimental rod clad may burst during the test);■ fuel-water interaction could cause a pressure peak in the loop’sprimary system and this must be allowed for when dimensioning it;■ the zircaloy used to manufacture the in-pile section of the loopis a fragile material;■ very high level effluents may be produced by the experiments.This analysis was presented to three meetings of the standingadvisory group for nuclear reactors.FOCUSA report was drawn up by IRSN on the procedureand the qualification of equipment that EDF intendsto use for the EPR reactor.In October 2004,EDF selected the site at Flamanville(Manche) to build a first reactor and submitted adossier with the national commission for publicdebate. Following this stage, EDF is expected toapply for authorisation to build the reactor. It willsupply the preliminary safety report which willthen be examined by IRSN.Follow-up of experimental reactorsIn 2004,IRSN’s appraisal work on research reactorsand fast-neutron reactors mainly concerned CABRI,PHEBUS,the high-flux reactor of the Laüe-LangevinInstitute (RHF) and PHENIX.The analysis of the preliminary safety report onthe CABRI reactor, modified by the installation ofa pressurised water loop,was presented during twomeetings of the standing advisory group for nuclearreactors. In general, the work done involved thedetailed examination of every aspect of thatreactor’s safety by means of an approach similarto that adopted for power reactors while allowingfor specific features of the installation’s operation(see Focus p. 96).96I R S N ANNUAL REPORT 2004

Assessing the safety of the PHENIX reactor.Furthermore,IRSN examined supplementary itemsrequested from the operator of the PHEBUS reactor,regarding shutdown criteria in particular, prior tothe conducting of the PHEBUS-FPT3 test inNovember 2004.In 2004, the Institute also studied the proposalfrom the high-flux reactor operator concerning theseismic classification of equipment and associatedfunctional requirements.This proposal is intendedto respond to a recommendation made by thestanding advisory group in May 2002 during theHFR safety review.modules. In addition, IRSN studied dossiersconcerning, in particular, the failure of a steamgenerator chest in the event of simultaneous failureof a sodium module and a water tube.Furthermore,IRSN evaluated CEA studies conducted to showthat the melting of a fuel assembly could not bepropagated beyond the six nearest assemblies.In January 2003, the restarting of the PHENIXreactor was authorised for a period limited to theequivalent of 720 days operation at full power. Itsdecommissioning is scheduled for 2008. In 2004,IRSN assessed the safety of irradiation experimentsconducted in this reactor, some of which fall intothe category of research operations conducted inthe context of the 1991 law on the managementof high-level long-lived waste.IRSN also examinedthe operator’s demonstrations illustrating theconsequences for the safety of steam generatorsof some “malfunctions” noted on two modules ofa steam generator (especially the deformation ofwater tube spacer grids) and the proposal formore thorough inspections on steam generatorPHEBUS reactor: test device storage pit.I R S N ANNUAL REPORT 200497

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKIRSN conducts civil engineering survey.Support for the safety assessmentof operational reactorsIn 2004, IRSN’s activities in supportof the safety analysis of reactors inoperation were mainly focused on workin the fields of civil engineering,thermal-hydraulics and PSA.Civil engineeringIn preparation for the third 10-yearly outageprogrammes for 900-MWe power plants, IRSNconducted a review of the design and dimensioningof civil engineering works.It assessed the behaviourof some works, such as electrical buildings, in caseof earthquake or explosion of external original.IRSN continued its action on the analysis of thebehaviour of containments allowing for the effectsof ageing of structures and accident situationswhich could affect their tightness.To optimise itscapabilities in digital simulation, IRSN took partin an international exercise for the cross-comparisonof designs and tests, organised by the OECD-NEAwhich considered containment mockups testedin the USA.In the context of feedback on the floods of 1999,lRSN examined the stability of the protective dykeson the sites at Belleville (Cher),Fessenheim (Haut-Rhin) and Le Bugey (Ain) in 2004.In general, IRSN checks on the in-service followupof civil engineering works and EDF’s manner ofdealing with cases of non-compliance identified:equipment or tank anchoring defects, etc.For the follow-up of containments,IRSN examinedthe tests carried out in 2004 on the sites at Golfech(Tarn-et-Garonne) and Cattenom (Moselle).In thecontext of the EPR project, IRSN continued itsexamination of the design of civil engineering works.The installation’s containment and its ability towithstand an intentional impact by a commercialaircraft were covered in reports presented to groupsof experts.Furthermore, regarding the modification ofregulations in line with new scientific knowledge,IRSN continued its work with a view to revisingbasic safety rules concerning the aseismic designof BNIs.Level-1 probabilistic safety studiesProbabilistic safety studies (PSA) assist in assessingthe measures adopted by operators by thesystematic investigation of accident scenarios. Inparticular,they make it easier to weight the importancefor safety of problems identified during designor operation so that high-priority improvementscan be put forward, where applicable. A level-1 PSAcovers scenarios leading to core meltdown anddetermines their frequencies.The year 2004 saw the completion of the level-1PSA for 900-MWe power plants using “event-related”control. The corresponding summary report wascirculated in September 2004.This study is regularlyused for safety assessments including,in particular,to appraise precursor incidents and requests forconcessions with regard to technical operatingspecifications.A revision of the level-1 PSA was begun in 2004to allow for control of the “state-oriented approach”type, using the PANAME method developed by98I R S N ANNUAL REPORT 2004

Thermal-hydraulic studies with the CATHAREcode.IRSN to quantify the reliability of control actions.The information obtained in this study was usedin the safety revision for the third 10-yearly outageprogrammes for 900-MWe power plants.The IRSNstudy thus identified topics for which the advantagesof design or operating modifications should be examinedby EDF.Thermal-hydraulicsIRSN uses the CATHARE code to conduct thermalhydraulicstudies in support of safety analyses inorder to understand physical phenomena that arenot fully mastered or to obtain new tools.In 2004,calculations regarding accidents involvingcomplete loss of steam generator feedwater wereconducted for the future EPR reactor.In the contextof the examination of the in-service strength oftanks for the 900 MWe reactors – a topic that willbe presented to the standing nuclear section in2005 – supplementary calculations were performedin order to assess the envelope characteristic ofthermal-hydraulic studies conducted by EDF.IRSN performed calculations for about 30 level-2PSA front-end phases using SIPA/SCAR simulatorsin 2004.The Institute also pursued its study of the“inherent”dilution phenomenon.This type of bariumCOMPARATIVE STUDY OF PSAs APPLIED TO SAFETY-RELATED EVENTSFOCUSIRSN conducted probabilistic assessments on safety-related events with the most severepotential consequences.About 10 events, occurring in French or foreign power plants, are selected every year. The aim of these studies is to assessthe increase in probability of core meltdown resulting from those events.They help to define measures which could reduce the consequences for safety. These preventive measures may entailorganisation or equipment. As a result of these studies, it can be determined which scenarios out of all those resultingin core meltdown are significantly affected by the eventstudied and, thus, those requiring priority action in orderto reduce possible consequences.In 2004, IRSN completed a comparison of probabilisticanalysis methods applied to events, in cooperation withthe German and Japanese safety operations (GRS and NUPEC,respectively). This exercise, based on three actual significantevents, showed that the three authorities had similarapproaches but that the probabilistic models should preferablybe harmonised.Event quantification meeting at the pressurised water reactorassessment department.I R S N ANNUAL REPORT 200499

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKSIPA simulator development room.dilution may occur in the event of a primary systembreak due to the stopping of the feed – to thecore – of “clear” water (without barium) whichhas accumulated in the water boxes and steamgenerator tubes when natural circulation is resumed(without primary coolant pumps). The studyincluded detailed thermal-hydraulic calculationsand CATHARE calculations simulating the PKLinstallation used to study “inherent”dilution phenomenain the context of OECD projects.Furthermore,to obtain a tool to assess future EDF studies, IRSNbegan studies on steam pipe failure accidents.SIPA 2 simulatorThe SIPA 2 simulator is used at IRSN to preparescenarios for crisis exercises, provide training inreactor physics and control and conduct studieson the thermal-hydraulic behaviour of power plantsand their operation in accident conditions.Two simulator configurations are currently beingused. In one, the boiler (primary and secondarysystems) is simulated by the CATHARE-SIMU codefor 900-MWe and 1,300-MWe reactors and, sinceearly 2004, the other features the simulation ofthe boiler and cooling system in shutdown stateby the CATHARE 2 V2.5 (SCAR) code.The first version is used for training purposes(nine one-week sessions a year on normal operation,design basis accidents and non-design basisaccidents) in the preparation of crisis exercisesunder IRSN responsibility:power plants at Gravelines(Nord), Nogent (Aube) and Le Blayais (Gironde) in2004 and for studies concerning 1,300-MWe powerplants.The second version is used for studies regarding900-MWe power plants with,in 2004,the calculationof accident front-end phases in power operationand shutdown conditions for the 900-MWe level-2PSA, and the study of operation in case of failureof a steam generator tube, in the context of theexamination of the MOX Parity dossier transmittedby EDF (see Focus p. 102).In parallel to these activities, the renovation ofthe SIPA 2 simulator, to begin in 2005, was thoroughlyexamined in 2004.100I R S N ANNUAL REPORT 2004

The Tricastin power plant at Pierrelatte (Drôme).Ageing of pressurised water reactorsIn the context of its work on PWRageing,IRSN conducted studies on theageing of electrical equipment in 2004.These studies covered the followingthree areas:■ assessment of the impact of ageing on the “steadystate”lead batteries, currently used in PWRs, ontheir operability during and after seismic stresses.Indeed, the conservative sizing of some batteriescould lead EDF to seek to use them in conditionsadversely affecting their availability in case ofseismic stresses. Despite a visible deterioration intheir condition following an accelerated ageingsequence,the batteries tested demonstrated goodelectrical and mechanical behaviour both duringand after seismic tests;■ an analysis of changes over time in the reliabilityof certain safety-critical electrical components,based on a statistical analysis of data relating todefects that have occurred during use of thesecomponents;■ an enquiry into the obsolescence and ageing ofelectrical equipment at 15 companies with a rangeof activities. This provided feedback on theirpractices and strategies for managing electricalequipment during utilisation and long-term storage.The difficulties and problems encountered and theassociated ageing phenomena were surveyed.This information will contribute to the assessmentsconducted by IRSN in this field.IRSN conducts studies on the ageing of lead batteries.I R S N ANNUAL REPORT 2004101

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKIRSN experts who took part in the study of the “MOX parity” dossier.Fuel in normal and accident operatingconditionsDefinition:the burnup fraction(expressed as GWj/t)characterisesthe quantity of energyproduced per tonneof fuel.IRSN is providing DGSNR with technicalsupport for the study of fuel managementprovisions proposed by EDFand,in particular,management changesplanned by the operator by 2007.EDF plans to implement new fuel managementmethods:■ MOX parity for 900-MWe CPY power plants(increase in the burnup fraction of MOX fuel to52 GWj/t, fuel assembly mean maximum value);■ GALICE for 1,300-MWe power plants (increasein burnup fraction of UO 2 fuel to 60 GWj/t);■ ALCADE for 1,450-MWe power plants (increasein UO 2 fuel burnup rate to 52 GWj/t).Each new fuel management method is subject toan approval process conducted by DGSNR whichentails three examination phases by IRSN:■ feasibility of the proposed management;■ updating of the safety dossier (revision of safetyreport studies,general refuelling safety assessmentdossier);■ updating of the operation dossier (revision ofgeneral operating rules).In 2004, the safety dossier on MOX Parity management(see Focus p.102) and the feasibility dossierfor GALICE management were prepared.The boosting of fuel performances entails areduction in safety margins. Therefore, demonstratingthe acceptability of a new fuel managementIRSN’S OPINION ON THE “MOX PARITY” DOSSIERFOCUSEDF plans to modify the management of MOX fuels used in combination with UO 2 fuels in 20 reactorsin France by implementing a new management dubbed “MOX Parity”.The reactors concerned are currently operated on the basis of a “hybrid” fuel management: UO 2 fuel assemblies are usedfor four cycles in the reactor compared with three cycles for MOX assemblies.The objective of MOX Parity management is to increase the number of irradiation cycles for MOX fuel assemblies to 4.This new management will require an increase in the enrichment of the MOX fuels and will therefore lead to an increasein the maximum burnup fraction of MOX assemblies.The acceptability of EDF’s proposals were examined between mid-2001 and mid-2004. Following this examination,IRSN’s decision in 2004 went against the implementation of the new management as proposed by EDF. The Institute’sreservations mainly concerned inadequacies in the substantiations provided by EDF as regards the fuel’s satisfactory behaviourin normal operation (maximum thickness of zirconium oxide on claddings, maximum internal pressure of rod during irradiation).Supplementary substantiating data is thus awaited from EDF.102I R S N ANNUAL REPORT 2004

UO 2 pellet constituting the fuel for a PWR.system generally means using new methods forsafety studies relying, in particular, on the use of3D computing tools and so reducing the conservatismintroduced by the uncoupled methods usedfor power plant design.In this context, it is worth mentioning:■ the utilisation of the CATHARE code for theanalysis of loss of coolant accident studies, andthe implementation of the realistic deterministicmethod coupled with a hot rod statistical method;■ the utilisation of a kinetic 3D method for thestudy of control rod ejection accidents.In addition,the implementation of a new managementmay require changes in fuel. In this way, forthe GALICE management, a modification in thefuel product is required in order to comply withdesign criteria: this entails the utilisation of M5alloy as the cladding and structure material for thefuel assembly (AFA 3GLr AA).In 2004,IRSN examinedthe dossiers concerning this fuel assemblywhich must be inserted in the reactor a few yearsbefore a new fuel management can be implemented.IRSN also examined the dossiers regarding foreignfuels acquired by EDF in the context of its fuelprocu-rement diversification policy.This concernedthe ENUSA fuel assemblies loaded in 900-MWeand 1,300-MWe reactors.123456789101112131415Typesof fuel assembly:New2nd cycle3rd cycleR P N M L K J H G F E D C B ARefuelling plan for a pressurised water reactor.I R S N ANNUAL REPORT 2004103

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKSome members of the IRSN severe accident risks analysis andstudy teams.Examination of risks associated with severecore meltdown accidentsThe examination of the risks associatedwith core meltdown accidents forpower reactors is supported by researchand development programmes andpunctuated by meetings of thestanding advisory group for nuclearreactors dealing with specific topicsselected according to advances inknowledge.BASEMAT AT THE FESSENHEIM POWER PLANTWater reactors in serviceIn the context of the safety review for the third10-yearly outage programmes for 900-MWe reactors(VD3 900), IRSN presented the standing advisorygroup meeting on 16 December 2004,with varioustopics concerning core meltdown accidents whichcould lead to modifications in equipment orprocedures during 10-yearly outage programmes.The following points were discussed:managementFOCUSIn the context of the modifications to be made during the third 10-yearly outage programmes,IRSN examined the basemat of the reactors at the Fessenheim power plant (Haut-Rhin) in 2004.This basemat, directly above the reactor pit, is less thick than those in other EDF reactors in service. It therefore follows that,in the case of interaction between the corium and the concrete, the time taken to break through the Fessenheim basematwould be shorter and, as a result, radioactive products (gases and aerosols) would be released to the atmosphere more quickly.IRSN therefore analysed whether it would be usefulto install supplementary devices which would delaypenetration of the basemat in Fessenheim reactors.Using the MEDICIS corium-concrete interaction moduleof the ASTEC V1 software package, IRSN was able toassess the time required to break through the existingbasemat and to show that adding water on the coriumwould not significantly delay the basemat penetrationtime. On the other hand, increasing the basematthickness with a layer of refractory concrete would delaythe penetration of the basemat enough to reach a timecomparable with that for other 900-MWe reactors.IRSN also examined the dosimetric consequences forAerial view of the Fessenheim nuclear power plant(Haut-Rhin).workers who would make this modification.104I R S N ANNUAL REPORT 2004

1 Robustness of reactor pita Collection of coriumbefore door is breached2 Breaching of door for complete removalof corium before reflooding3 Kinetics of corium spreading before reflooding4 Heat resistance of steel structureof spreading chamber floor5 Thermal-hydraulicsLostof cooling systemmaterialProtective laterSpreading chamber1a532Melt plugsFloor cooling4Melt discharge systemIRSN specialists for the design of the EPR coriumrecovery system.Block diagram illustrating corium recovery in the PWR reactor.of the molten core (corium) in the reactor pit, riskassociated with direct heating of the containment,and instrumentation to be installed for themanagement and follow-up of a severe accident.In examining these topics, IRSN relied to a greatextent on the current state of research and, inparticular, studies conducted on the interactionbetween corium and concrete,and the risks of steamexplosion. Some generic studies were conducted inthe context of level-2 PSA development that IRSNundertook for 900-MWe reactors.In addition,IRSN’sexpertise in the field of instrumentation is basedon experience acquired in the context of the PHEBUSprogramme.IRSN recommended that EDF should increase thethickness of the basemat for reactors at theFessenheim power plant (see Focus p.104) and installa corium detection device in the reactor pit, afterthe reactor vessel penetration.Furthermore, as a result of the analysis, EDF wasled to plan a modification of the bolts on theequipment access hatch for CPY type reactors soas to ensure tight sealing for pressure peaks of upto 8 bars. EDF is also to modify the device used todepressurise the primary system via SEBIM valves,including in the case of a severe accident with totalfailure of electric power supplies (mains anddiesel generators).EPR reactor projectIRSN examined the following two topics in 2004:■ the new containment design and its capabilityof maintaining its integrity and tightness afterglobal deflagration of the quantity of hydrogenwhich could be present in the containment in theevent of a low-pressure core meltdown accidentor after a representative fast local deflagration;■ the robustness of the corium recovery conceptproposed by EDF (see Focus).EPR CORIUM RECOVERY SYSTEMFOCUSThe system for the recovery of molten material fromthe core (corium) planned for the EPR reactor representsa significant improvement for safety in case of a coremeltdown accident.Indeed, it would avoid the failure of the basemat and, thus,failure of the containment leaktightness. The corium flowing fromthe reactor vessel after its failure would be collected and received ina dedicated spreading chamber where it would be cooled by a passivewater injection system.Examination in 2004 of the system proposed by EDF led IRSN to identifyseveral points requiring more thorough investigation. The Instituteconducted studies on these points with its own calculation tools whichconfirmed that the system planned by EDF was appropriate to meetthe objectives defined:■ complete collection of the corium in the reactor pit before failureof the door below the reactor pit;■ obtaining of a great enough breach size on failure of the door to allowrapid flow and spread of the corium;■ limited ablation of the sacrificial concrete layer;■ heat resistance of the steel structure of the spreading chamber;■ satisfactory operation of the cooling system under that chamber.Some points should, however, be investigated further, especiallythe failure of the door separating the reactor pit from the spreadingchamber and the analysis of a new device proposed by the designer,the thickness and the nature of the sacrificial concrete in the spreadingchamber and the reliability of the passive basemat cooling devicein that chamber.I R S N ANNUAL REPORT 2004105

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKEurodif’s enrichment plant on the Tricastin site (Drôme).Safety expertise for future reactorsto follow EPRGeneratorTurbineLooking beyond the EPR to futurereactors,IRSN directed efforts in 2004to the study of steps to be taken toprepare expertise on their safety.Among the various projects for reactors andassociated fuel cycle installations currently beingdeveloped in the context of the Generation IVInternational Forum (GIF),it is worth noting projectsfeaturing:■ high or very high temperature reactors (HTR/VHTR)which are helium cooled;■ fast neutron reactors which are gas cooled (GFR)or sodium cooled (SFR).In the case of these reactors, designers are seekingControl rod drive/refuelingpenetrationsSteel reactorvesselimprovements, especially with regard to safety,reduction in waste and resistance to malicious acts.As for the schedule, reactors of this type could notreplace the PWRs of generations II (existing) and III(EPR) and others until the middle of the 21st century.Nevertheless, for some types of reactor, designersenvisage the building of “demonstrators”by 2010-2015.As regards safety expertise,IRSN will initially focuson high or very high temperature reactors,proceedingwith technical exchanges, in particular, withFramatome, which is developing a VHTR project.Furthermore, the Institute will monitor progressmade in the study of gas-cooled fast neutron reactorsand on the development of sodium-cooled fastneutron reactors.In 2004, IRSN established international contactsin the field of future reactors, including with GRSand NRC in particular. IRSN will also take part inthe integrated project for the 6th FPRD on “V/HTR-IP”concerning accident design codes in particular.RecuperatorCompressorAnnularreactor coreIntercoolerShutdownheat exchangerShutdown circulatorPrecoolerGT-MHR module.106I R S N ANNUAL REPORT 2004

Working meeting to express opinions on the safety of installations.Safety of plants, transportand dismantlingIRSN provides technical expertise fordossiers transmitted by nuclear installationoperators and by applicantsfor radioactive material transportpackages.The Institute also studies therisks of dispersal of radioactivematerials and of criticality which areto be found in most installations.IRSNdraws up reports on internal emergencyplans (PUI) for sites containingnuclear installations.Installations “upstream” of cycleIn 2004, IRSN assessed the dossier on the safetyreview of the installation operated by COMURHEXon the Pierrelatte site (Ardèche).In particular,IRSNpointed out inadequacies in the provision madefor the risks of dispersal of radioactive and chemicalmaterials, fire and external hazards.The definition of safety options for the new uraniumenrichment plant (Georges-Besse II) which AREVAplans to build on the Pierrelatte site were examinedby IRSN in 2004. This plant, which is intended toreplace the EURODIF plant,will use the enrichmentprocess based on centrifugation of uranium ingaseous UF 6 form developed by URENCO. Thecentrifugation process considerably decreasesthe quantity of gaseous UF 6 present in the installation,which also reduces the risks of dispersal ofradioactive and chemical materials. As a result ofthe survey conducted, it was concluded that thesafety options proposed by AREVA appear to beacceptable at this stage of the project.The United States is envisaging using MOX fuelassemblies made from weapon grade plutoniumin American nuclear power plants. Four first-offassemblies intended for a PWR in the USA havebeen manufactured in France.This operation,knownas EUROFAB, involves two French installations:the plutonium technology facility (ATPu) for themanufacture of fuel rods and the MELOX plant atMarcoule (Gard) for the manufacture of fuelassemblies. IRSN examined the specific provisionsplanned by the operators of these installations withregard to criticality risks. Indeed, the product usedentails specific criticality risks owing to the highcontent of plutonium 239 and the low content ofplutonium 240.IRSN collaborated with DGSNR in the inspectionof the plant’s manufacturing fuels intended forPWRs in Europe.The information drawn from theseinspections, in terms of comparison of provisionsimplemented to control risks and, in particular, toreduce the doses received by workers, werepresented at an international conference organisedby the IAEA in Beijing (China) in October 2004.This information will be used when the dossier isexamined for the safety review of the French fuelmanufacturing plant in Romans-sur-Isère (Isère).Installations “downstream” of cycleFor installations “downstream” of the fuel cycle, amajor portion of IRSN’s work was dedicated toexamining changes in the operating range ofirradiated fuel reprocessing installations UP2-800and UP3-A and of the COGEMA STE3 waste treatmentinstallation at La Hague (Manche), and theprovisions proposed by COGEMA in that respect.I R S N ANNUAL REPORT 2004107

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKAerial view of the Cogema-La-Hague site (Manche).The decrees published in the OJ on 11 January 2003define the operating range of these installations,and any extension of the operating range in forceis subject to specific authorisation, described as“operational” authorisation, granted by interministerialorder.In the course of 2004,three specificdossiers for the extension of the operating rangewere examined by IRSN and laid to the publicationof three interministerial orders. These concern:■ fuel assemblies, known as UOX3, with a meanspecific burnup fraction for the assembly of lessthan 60 GWj/t and a mean content of uranium 235isotopes before irradiation of less than 4.5%;■ MOX fuel assemblies with a burnup fraction notexceeding 55 GWj/t and a content by weight ofplutonium and americium not exceeding 8.65%for irradiation;■ non-irradiated MOX fuel elements initiallyintended for the SNR 300 fast neutron reactor ofKalkar (Germany), with a plutonium content byweight not exceeding 40%.The technical investigation by IRSN focused, inparticular, on the changes in risks related to heatreleases and radiolysis, risks of external exposure(especially to neutrons in the case of MOX),criticalityrisks and the modification of waste characteristicsas a result of the treatment operations forthose fuels.The Institute reached a favourable opinionon the provisions adopted for the protection ofworkers and the environment.Assessment of internal emergencyplans (PUI)For laboratories and plants,the internal emergencyplans for the CEA Valrhô and Superphenix centres,the COGEMA plant at Pierrelatte and the CEA centreat Fontenay-aux-Roses were analysed.The analysisof the internal emergency plan for the COGEMAplant at Pierrelatte included,in particular,a detailedexamination of the accident situations considered.Safety of radioactive materialtransportTranSAS missionIn 2004, the IAEA arranged a 10-day meeting ofabout 15 foreign experts to assess the organisationof the inspection of radioactive material transportsafety in France,in the context of a TranSAS mission.DGSNR and IRSN, along with the firms with thelargest international transport flows (COGEMAand CIS bio international), were audited.The mission concluded that the French inspectionsystem was suitable for the volume and complexityof transport operations performed.PATRAM conferenceThe 14th PATRAM international conference, heldin Berlin (Germany), was the occasion for muchdiscussion on the five topics presented by IRSN:■ a model for the calculation of the effects of surfacecontamination of packages: the study of thedosimetric impact of contaminations showed thatthe limits in force remain appropriate althoughthe margins for some isotopes were found to belarge;■ radioactive material transport flows andcorresponding doses for workers and the generalpublic: using the data collected, it was possible tospecify the number of transportations of inspectionequipment containing radioactive materials;■ the fire behaviour of two parcel models containingirradiated fuel or vitrified waste, respectively: theduration of fire resistance of these parcels is significantlygreater than the statutory requirements.The108I R S N ANNUAL REPORT 2004

Rail transportation of vitrified waste.results obtained will be used as a transport accidentmanagement tool;■ safety distances to be prescribed in case of atransport accident. These will be integrated indepartmental emergency plans to deal withradioactive material transport accidents;■ a methodology to determine the exemption limitsfor fissile actinides.Study on harmonisation of European practicesregarding certification of package modelsIn 2004,the European Commission financed a studyconducted by IRSN and BAM (Germany) on theharmonisation of European practices with regardto certification of package models for transportof radioactive materials.This study included three phases:■ study of practices in force in France and Germany;■ distribution of a questionnaire covering the mainpoints of those practices to all European Unionmember and candidate countries;■ analysis of answers received in order to draw uprecommendations aimed at achieving greaterharmonisation.In this context, it was proposed that guidelinesshould be drawn up for operators to prepare safetydossiers and for the relevant authorities to assessthose documents,and that standard formats shouldbe defined for safety dossiers, survey reports andcertificates of approval.EUROFAB projectIRSN conducted a technical survey of safety dossiersfor the various types of transport operations, byroad and by sea, for the two package modelsconcerned, FS 47 for plutonium oxide supplied bythe USA and FS 65-900 for the four fabricatedassemblies and supplementary rods.IRSN also went on line with explanations of itsassessment of the risks associated with possibletransport accidents in response to two associations,WISE-Paris and Greenpeace International, andthe results of the study carried out by the Large &Associates consulting firm.Safety of dismantling decommissionednuclear installationsIn the last few years, the main nuclear operators(CEA,EDF,COGEMA) undertook major programmesfor the dismantling of nuclear installations whichwill lead to the decommissioning of some 40 basicnuclear installations by 2025.In the course of 2004,IRSN examined the following,in particular:■ decommissioning and dismantling operations forthe SILOE and SILOETTE experimental reactorson the CEA site at Grenoble (Isère);■ decommissioning and dismantling operationsforthe enriched uranium processing workshops(ATUe) on the CEA Cadarache site(Bouches-du-Rhône);■ decommissioning and dismantlingoperations for the SICN plant at Veurey-Voroize (Isère).On 24 and 31 March 2004, IRSN gaveits opinion on EDF’s strategy for thedismantling of “first generation”reactors,to the standing advisory group for basicnuclear installations other than nuclearreactors and excluding installationsdesigned for long-term storage ofradioactive waste (standing advisoryTechnical examination ofgroup for plants).a safety dossier on an installationin the process of being dismantled.I R S N ANNUAL REPORT 2004109

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKMelox MOX fuel manufacturing plant atBagnols-sur-Cèze (Gard).Assessment of risks of dispersal ofradioactive materialsThe risks of the dispersal of radioactive or toxicmaterials in normal,incident or accident conditionsare the subject of a close study by IRSN.In 2004, specific safety assessments on these riskswere conducted for a variety of installations suchas plants and laboratories (CIS bio international inSaclay, CEA Valduc – Côte-d’Or, FBFC in Romans –Isère, MELOX in Marcoule, COGEMA in La Hague),installations in the process of being dismantled (UP1plant in Marcoule, Superphenix reactor), researchreactors (OSIRIS in Saclay, RHF in Grenoble), theRES reactor at Cadarache and certain other auxiliarybuildings for EDF reactors.Generic topics concerning all nuclear installationswere also studied, such as the quantification ofdischarges which could be caused by an earthquake,taking into account the conditions for cracking ofbuildings and pressure differences caused by wind,gas system leaks and heating of the air insidebuildings.Another noteworthy event in 2004 was IRSN’sparticipation in the drawing up of ISO standards inthe field of containment and, in particular, of astandard concerning the design and operation ofventilation systems in nuclear installations otherthan reactors. IRSN also began collaborating withits Ukrainian counterpart (SSTC) in the field of safetyinstructions to be applied to filtration equipmentfor nuclear installations.Assessments of criticality risksSpecific technical analyses are conducted on criticalityrisks.In 2004,IRSN conducted 104 assessments which ledit to perform comparative calculations and specificstudies to verify the substantiations put forward bynuclear operators in their authorisation requests andto evaluate the safety margins associated withcalculations, according to the level of validation ofthe calculation tools used by the applicants.A studyaimed at specifying the criticality risk in undergroundrepositories for radioactive waste was conducted forchanging scenarios in the very long term.Furthermore, IRSN analysed incidents related tothe criticality risk and provided support for surveillanceinspections and crisis exercises for which questionsof criticality could arise.IRSN also took part in the IAEA’s work on themodification of international regulations on thesafety of radioactive material transport and theOECD’s work on improving criticality calculationmethods.110I R S N ANNUAL REPORT 2004

As part of its appraisal of the storage of highactivitywaste, IRSN is conducting research onthe properties of clay as a potential host rockat Tournemire (Aveyron).Examination of safety dossiers concerningmining waste and participationin the writing of regulationsIRSN’s role includes the safety ofvarious stages of radioactive wastemanagement: processing, packaging,transport,interim storage and disposalfor various categories of waste withall activity levels,mining waste,contaminatedsoil, etc.In 2004, in view of the time limit set by the lawof 1991 for research in the management of highlevellong-lived waste (HLLLW), the Instituteconcentrated its efforts mainly on examiningdossiers concerning this waste.Disposal in deep geologicalformationsThree dossiers on the feasibility of disposal in deepgeological formations, drawn up by ANDRA, wereexamined by IRSN and the conclusions of theseinvestigations were presented to the standingadvisory group for radioactive waste long-termdisposal facilities. These dossiers concerned:■ mechanical disturbances liable to occur in arepository in the clay formation studied by theBure underground laboratory (Meuse/Haute-Marne);■ chemical disturbances in that repository;■ the current position of studies of the benefits ofFrench granite formations as a location for a HLLLWrepository (“2002 granite dossier”).The analysis of the first two dossiers completed afirst cycle for the examination of key points on thesafety of a possible repository, with regard to:■ the qualities of the geological site studied;■ the design features of a repository;■ the questions on safety raised by the operationand reversibility of a repository.The investigations conducted on mechanical andchemical disturbances and their coupled effectsand also on thermal and hydraulic disturbancesresulted in an initial assessment of changes in theperformance of the containment barriers of arepository and of the suitability of the designprovisions envisaged by ANDRA to prevent thosedisturbances and reduce their effects.In conducting its investigation,IRSN relies on its own researchfacilities such as the Tournemireexperimental platform (Aveyron)and takes part in internationalexperimental projects (Mont-Terri) and modelling projects(Decovalex,European projectssuch as SPA, BENIPA, NFPRO).It is in this context that IRSNwas able, in particular, toformulate its opinion regardingtransfers in semipermeablemediums,the potential role ofcolloids in potential radionuclidetransfers in the repository andMeasuring the direction of cracks in athe geological environment,tunnel gallery at Tournemire (Aveyron).I R S N ANNUAL REPORT 2004111

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKVacuum packing of clay samples taken at Tournemire for chemical analysisin the laboratory.MIMAUSA PROGRAMMEand the influence of hydraulic binders on thecontainment properties of clays.The assessment of the “2002 granite dossier” providedthe opportunity to analyse the possible optionsfor a repository in a granite medium and to examinethe capacity of French granites to accommodatesuch a repository. The analysis conducted on thebasis of the bibliographical data contained in theANDRA dossier,originating from French and foreigngranitic sites, led IRSN to consider that thesedeep granitic formations did not have geologicalcharacteristics that were incompatible,in a genericmanner, with a possible repository.IRSN also examined the work and research pro-FOCUSUranium mining activities may have led to modifications in the natural environmentand to radiological marking in the air, water and soil.This marking may be significant without necessarily having notable dosimetric consequences.On the basis of its current and past work, IRSN has precise knowledge about several of these mining sites but only partialdata is available for other sites. For this reason, DPPR, a department of the French Ministry for Ecology and SustainableDevelopment (MEDD), asked IRSN in 2003 to set upa programme aimed at preparing a radiological reporton the environment around uranium mining sites.This programme, called MIMAUSA, is being conductedin close collaboration with COGEMA. Its steering committeeincludes members from MEDD, IRSN, COGEMA and DARPMIBretagnefrom the French Ministry of Economy, Finance and Industry.GuérandeVendéeChâteau-ChinonAlsaceSaint-SymphorienBenaizeGartempeAllierCreuseSaône-et-LoireForezCrouzilleCorrèzeAquitaineAmbertCantalMaurienneAveyronLorèzeLodèvePACAMining areas in France.The concept of “mining areas” was defined in the contextof the MIMAUSA inventory as a means of grouping sets of sitesin geographic areas.The name allocated to each “mining area” can reflect eitherits inclusion within specific administrative boundaries or the nameof a large city, or it can be drawn from a mining title.For the “knowledge assessment” section of this programme,IRSN published a national inventory of uranium mines inJune 2004 and this can be consulted on the following website:www.irsn.org. It lists the sites where uranium ore exploration,extraction or processing activities have been conducted inmainland France. There is a descriptive summary data sheetfor each site.In parallel, IRSN has started collecting detailed informationfocusing on two pilot sites: Gartempe (Haute-Vienne) andAmbert (Puy-de-Dôme).A database containing mapping data is being createdfor the organisation and subsequent consultationof the information provided.112I R S N ANNUAL REPORT 2004

Redevelopment of the mining site at L’Écarpière (Loire-Atlantique).grammes planned by ANDRA in the Bure undergroundlaboratory in support of the application for authorisationto proceed with excavation of the experimental“niche” and galleries for the laboratory.Waste packagesAs regards waste packages, IRSN examined thefollowing three dossiers:■ a first version of the specifications for packagesobtained by bituminisation in the STE3 workshopat the COGEMA plant in La Hague (Manche), ofsludge from the previous STE2 workshop;■ the application for authorisation to continueusing package interim storage cell 124 (E-I-P) atthe COGEMA plant in Marcoule (Gard) beyond thefourth interim storage level;■ an ANDRA dossier giving the inventory of HLLLand MLLL packages for the dimensioning of apossible repository in the clay layer studied at Bure.Disposal facilitiesIn the field of surface disposal facilities for lowand intermediate activity waste, IRSN examinedspecific dossiers concerning the Aube and Manchecentres (statutory monitoring plan, internalemergency plan, resin storage, reception of sealedsources in a surface disposal facility).On the COGEMA uranium ore processing wastedisposal sites, the Institute conducted third-partysurveys of the following in response to a requestfrom DRIRE:■ the radiobiological impact for 2002 of the formerL’Écarpière mining site (Gétigné,Loire-Atlantique);■ the environment monitoring conducted byCOGEMA around the sites at Gueugnon (disposalof ore processing waste) and Bauzot near Issyl’Évêque(disposal of waste slightly contaminatedby natural radionuclides);■ the application for authorisation to store miningdeads and demolition products from the SIMOplant at the open-cast mine on the Bois-Noirs-Limouzat site.Furthermore, on the request of DDASS in Creuse,a study was conducted on a project to set up aswimming facility at a pond on the location of theformer Grands-Champs open-cast mine (village ofGouzon, Creuse). The overall results showed thatusing this site as a swimming facility would notresult in a significant increase in doses receivedcompared with the average level of exposure forinhabitants of Limousin.Regulations on waste safetyIRSN took part in work to revise and draw up policiesconcerning waste safety.In this way,it contributedto work in 2004 aimed at modifying basic safetyregulations III.2.f and III.2.e dealing, respectively,with the safety of disposal of radioactive waste indeep geological formations (III.2.f) and favourablecharacteristics of waste packages with regard totheir acceptance in a surface disposal facility (III.2.e).The Institute is also contributing to the preparationof a reference guide concerning HLLL and MLLLpackages (referred to as “L542”) for which eliminationsystems are currently being studied.In 2004, IRSN drew up a guide concerning a finaldisposal facility for naturally radioactive wastewhose activity level has been increased by theindustrial process that produced it.The aim of thisguide is to provide producers of this type of wasteand, in particular, personnel responsible for thedesign of disposal centres with a method describingthe various steps to be implemented for theassessment of radiological impacts. This work,conducted at the request of MEDD in the contextof a working group comprising representatives ofI R S N ANNUAL REPORT 2004113

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKIRSN’s “human factor” team for reactor safety.the administration along with producers and wastedisposal agents,was presented to the SFRP congressin Marcy-l’Étoile (Rhône) in September 2004.In addition,in 2004,IRSN performed work in supportof authorities involved in radioactive wastemanagement (French and foreign safety authorities,IAEA, etc.) including in particular:■ participation in monitoring inspections of basicnuclear installations as technical support for DGSNRand DSND;■ participation in the work of the IAEA committeeresponsible for examining safety guides concerningradioactive waste management (WASSC);■ participation as consultant in the drawing-up ofsome of those guides (concerning geologicaldisposal in particular);■ the drawing-up, in a Franco-Belgian context andin liaison with ANDRA, of a common position onthe safety approach for geological disposal facilities;■ the training, in response to the IAEA request, ofsafety authorities from East European countriesin the field of surface disposal facilities for radioactivewaste.Human and organisational reliabilitySpecial assessments conducted by IRSNin the field of human and organisationalfactors were centred on three topicsin 2004.Control and supervisionIRSN examined the design principles ofcomputerised control planned for the EPR reactor.These principles are, to a great extent, based onexperience acquired on N4 power plants. Theyhad passed an initial validation by EDF throughtests conducted on mockups with operators.Owingto EDF’s desire to increase the level of responsibilityof the control team, IRSN examined, in particular,the assistance provided to operators by supervisioninterfaces. In the context of the standing advisorygroup for EPR, IRSN stressed that it was essentialthat the control team should retain its power overcontrol and have an overall view of the evolutionof the process, but that it should be provided withsufficient guidance in order to avoid inappropriateactions.Organisation and managementNuclear power plants undergo regular technicalmodifications that have a significant impact onoperating procedures, work organisation and thecompetencies required from agents.IRSN examinedthe method and organisation implemented by EDFto allow for that impact during the design ofthose modifications (see Focus).Furthermore,during the updating of safety reports114I R S N ANNUAL REPORT 2004

Reports presented to the standing advisorygroup on nuclear reactors.for various nuclear installations, IRSN examinedthe manner in which operators dealt with risksassociated with human actions: starting up of theextension of the CEA irradiated fuel study laboratory(Saclay) and the “pit” section of the test reactorat Cadarache, commissioning of the Civaux powerplant (Vienne), safety review of the CABRI reactor,and dismantling of Superphenix.These investigationsfocused on the operational provisions adopted bythe operators to prevent and repair human errorsliable to adversely affect proper control of thesafety of installations.FeedbackTwo safety-related events which occurred in nuclearpower plants were submitted to thorough analysisby IRSN with regard to human and organisationalfactors.This highlighted the fact that a team mayexperience difficulty in rigorously applying a controlprocedure when its view of the trend in operationparameters leads it to believe that the actionsrequired by that procedure are ineffective.INTEGRATION OF HUMAN FACTORSIN THE DESIGN OF MODIFICATIONSTO EDF POWER PLANTSFOCUSThe analysis of actions carried out in the early 2000sindicated that modifications made in power plantsresulted in difficulties for some agents (operatingand local servicing personnel), or even, incidents.During the year 2003, IRSN conducted a retrospective studyof the implementation of nine modification projects. Parties involvedin the projects and the operating staff concerned by thosemodifications were interviewed. The main documents writtenduring the projects were analysed. The study revealed inadequaciesas regards the integration of human factors in the designof modifications.At the end of 2003, EDF began to introduce a procedurefor the analysis of social-organisational and human impactsof modifications (SOH procedure). In 2004, IRSN assessedthis procedure by comparing it, firstly, with the results of its studyof the projects and, secondly, with “good practices” forthe integration of human factors in project control.This assessment showed that the procedure, which was designedto be carried out upstream of modification projects, should be extendedto include a study of the human factors at each stage of projects:analysis of needs, analysis of impacts, specification andimplementation of solution, validation tests, implementation on siteand follow-up during operation. In this context, IRSN emphasisedthe need to provide designers with more training in the fieldof human factors and to improve the assistance provided by the guidesfor this procedure.I R S N ANNUAL REPORT 2004115

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKVentilationsystemVHE filtersBlowingExtractionCablewayElectric equipmentcabinetSmoke(soot and gas)SmokeFire propagation studies.Fire protection of installationsAssessing the fire protection of aninstallation means studying stepsproposed by the operator for prevention,detection and action in order to avoidthe outbreak of fire, to detect andcontrol any fire outbreak that occurs,to limit the fire to within a predefinedvolume and to extinguish it.Fires and explosions, whether they originate frominside the installation or are of external origin (forestfire,lightning,industrial environment or communicationroutes) are possible sources of accidents. Nuclearoperators take steps to prevent or limit fires andexplosions so they cannot result in serious director indirect consequences for personnel, membersof the public and the environment.Assessment workIRSN assesses the validity of the means adoptedand justified by the operator in installation safetydossiers. For this purpose, the Institute can rely onthe results of research – especially research it hasconducted itself –,the results of studies conductedusing design codes in order to gain a better understandingof the phenomena involved, specificFIRE PSAFOCUSIn order to appraise the provisions adopted by EDF, against fire risks and to determine possible waysof improving safety, a specific probabilistic safety assessment (PSA) was made by IRSN for 900-MWereactors.This assessment included a systematic investigation of accident scenarios that could be caused by fire and their frequencieswere determined.The year 2004 saw the completion of the fire PSA version based on the event-related control of accident situations.IRSN also conducted a sensitivity assessment in order to gauge the effect of implementing the fire action plan adoptedby EDF to improve fire protection for 900-MWe and 1,300-MWe reactors.In this way, the critical premises and sequences representing a major part of the risk of core meltdown were identified.For the purposes of this study, fire scenario calculations were performed using the coupled FLAMME_S/SIMEVENT software.The information drawn from the experimental programmes on fire (DIVA 0 and CARMELA) carried out in IRSN installationsare to be integrated during a future update of the PSA. This work focused, in particular, on electrical cabinet fires and firepropagation from one room to adjacent premises.The lessons drawn from the fire PSA were also used for the safety review associated with the third 10-yearly outageprogrammes for 900-MWe power plants.116I R S N ANNUAL REPORT 2004

IRSN personnel in ventilated protective suits take part in fire studies.probabilistic safety studies,international practices,as well as feedback and data drawn from incidentsthat have occurred in nuclear and non-nuclearinstallations.Owing to the specific features of nuclear installations,special care is taken to maintain the availability ofsafety functions in case of fire and to preserve thecontainment of radioactive materials. All the effectsof fire (transfers of hot gases, soot, pressure, etc.)and their consequences on safety-related equipmentare considered. The influence of ventilation onthe development of a fire and on its consequencesis also taken into account in order to examine,in particular,ventilation control strategies in case of fire.The main topics studied by IRSN in 2004 include,above all,the assessment of fire protection provisionsconducted in the context of the definition of setsof modifications to be made during the third 10-yearly outage programmes for 900-MWe reactors,taking into account the results of the probabilisticsafety assessments (PSA) on fire conducted byIRSN (see Focus p. 116). In this context, IRSN alsoexamined the operator’s principles of preventionand protection to control risks concerning thepresence of hydrogen in the buildings of the nuclearisland. Other assessments of explosion risks wereconducted for the industrial implementation of amethod for the chemical dehydrogenation ofreactors in N4 power plants, operations for thedestruction of sodium described in the preliminarysafety report on dismantling of the Superphenixreactor,and risks related to the external environmentfor several nuclear installations. In addition, anassessment of fire risks was conducted in supportof the safety assessment of the Khmelnitski 2 reactorby the Ukrainian safety authority.With the processing of the first results ofexperiments on heat and smoke propagation andstudies on the fire behaviour of sectorisation andcontainment equipment conducted by IRSN in theDIVA and STARMANIA installations, it has beenpossible to obtain a better appraisal of the pressureeffects associated with fire and to reduce theuncertainties in the evaluation of releases of radioactivematerials to the environment during a fire.The suspension coefficients to be considered andthe redeposition and retention coefficients foraerosols in an installation were determined for anumber of materials which could play a part in afire.TPH pit fire in confined and ventilated premises.I R S N ANNUAL REPORT 2004117

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKRadioecological impact studies1001010,10,0110In 2004, IRSN conducted two impactstudies in the field of radioecology forthe public authorities: one concernedthe effects of floods of the Rhône riverin late 2003 and the other examinedthe consequences in France of the abovegroundtesting of nuclear weapons.137Cs1962 1966 1970 1974 197890SrStudy of impact of Rhone river floodsof December 2003In December 2003, the highest water level everrecorded on the Rhône caused flooding as the dykesin the river’s low valley overflowed or gave way.When it is in spate,the Rhône carries large amountsof suspended matter (sediment and swell particleswashed down from the catchment area),which cancontain the major part of the annual flows of someradionuclides. Reflecting the concern of theinhabitants in the areas concerned,CLI in Gard andDRIRE for the PACA region asked the Institute tocarry out a scientific survey and,in addition,DGSNRrequested an assessment of the radiologicalconsequences of the floods. The results of thissurvey were presented to CLI in June 2004 and areport was published in October 2004. They showthat the levels of radioactivity measured in the soilin the flooded areas and in local produce were notsignificantly different from those measured inneighbouring areas.The same applied to the mainchemical pollutants measured in a few samples.10,10,01Le VésinetClermont-FerrandModel of Paris regionModel of Clermont-Ferrand1962 1966 1970 1974 1978Radioactivity of the daily food intake of children aged 8 to 12,between 1961 and 1978: SCPRI measurements in schools intwo French cities and values calculated from the radioactivityreconstituted in various foodstuffs included in their food intake.Impact in France on atmospherictesting of nuclear weaponsFollowing controversy over significant caesium-137activity levels measured in the mountainousMontagne Noire area (Aude) in 2002, the DPPRdepartment of the French environment ministryasked IRSN in 2003 to carry out a survey of thefallout in France from all atmospheric weaponstests. This entailed reconstituting the variationwith respect to time of the activity of the 14 mainradionuclides present in the air, in deposits and in118I R S N ANNUAL REPORT 2004

During flood periods, the Institute takes greaternumbers of samples of river sediments whichmay contain the main part of annualradionuclide flows.the food chain,and then to assess the doses receivedby inhabitants. This survey was based on nearly40,000 results for measurements performed inmainland France between 1961 and 1978. In spiteof the large amount of data available, modellingwas necessary to fill gaps in the sequences ofmeasurements.Data for fruit and vegetables,wheat,milk and meat were used to adjust the transfermodels. The highest activity levels in the air anddeposits were due to those short-lived radionuclides.However,contamination of the food chain by thoseradionuclides remained limited owing to their shorthalf life and their low mobility. Caesium 137 andstrontium 90 were measured in practically all thecompartments of the food chain during this period.Iodine-131 contamination of foodstuffs was conductedin bursts after each test.Overall, for all radionuclides, the activities measuredhardly exceeded 1 to 10 Bq/kg -1 fresh except in leafvegetables and grass where the values rose to asmuch as 1,000 Bq/kg -1 fresh in the early 1960s.At each stage of the calculation, IRSN studied theregional variability in order to modulate the verygeneric assessment of the dosimetric impact ofthe tests proposed by UNSCEAR.In 2004, these results were set out in two reports bythe Institute,presented to a congress and publishedin a magazine.A report concerning dosimetric aspectswill be published in summer 2005.Earthquake and flood risksSeismic hazardIn 2004, the Institute conducted investigationson various dossiers:■ safety option dossier for the Ionisos installationat Sablé (Maine-et-Loire);■ long-term storage of medium- and high-levelwaste from CEA;■ examination of the preliminary safety report forthe Georges-Besse II installation;■ earthquake detectors for the high-flux reactorin Grenoble (Isère);■ safety reviews for 10-yearly outage programmesVD3 900 and VD2 1300.Assessments were also conducted on foreigninstallations: a survey concerning the Chernobylsite was carried out by teams from the Institutethrough RiskAudit, subsidiary of IRSN and GRS,and a study was also carried out on the probabilisticassessment of the seismic risk for the Krskosite (Slovenia) in the context of a EuropeanPHARE project.Flood hazardFollowing the flooding of the Le Blayais site(Gironde) at the end of 1999, EDF conducted areview of the protection arrangements for all itsinstallations and of the methods used to characterisethe flood hazard. Historically, the flood hazardwas defined in the basic safety rule RFS I.2.e bymeans of the maximum design flood levelrepresenting an extreme high water level for sitesnear rivers or the sea.After the flood at Le Blayais,it appeared to be necessary to allow for additionalassociated hazards, such as rain, sea swell andI R S N ANNUAL REPORT 2004119

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKRecording of samples taken from nuclear installations for the analysis ofradioactive releases.ground-water. EDF drew up a dossier for each of itssites with the aim of justifying the protectionprovisions it had taken against external floodingrisks.In addition to the work related to the protectionof reactors, IRSN examined, in 2004, the pointsconsidered for the dimensioning of protective dykesfor the sites at Belleville (Cher) and Le Bugey (Ain).For the Belleville site, this activity more especiallyconcerned the effect of rising groundwater and the“lapping” phenomenon in the case of extreme highwater levels. The Le Bugey site chose the solutionof percolation under the protective structures.Environmental monitoringTechnical support for authorities withregard to environmental monitoringcovers a number of actions:radiologicalanalyses,metrology,cross-comparisonsand assistance with inspections.Monitoring of effluent releases fromnuclear installationsIRSN carried out monitoring of radioactive releasesfrom nuclear installations.This undertaking involveda continuous assessment on the basis of radiologicalanalyses of gaseous and liquid effluent samplestaken from main drains. The objective is both toverify the release values declared by the operatorsand to improve knowledge of the nature and activityof the radionuclides released, along with theirvariations in the course of time, in order to definesuitable environmental monitoring plans.In case of incident or accident,this data is completedby that obtained from samples at stations set upFOCUSSETTING UP THE NATIONAL NETWORK FOR ENVIRONMENT RADIOACTIVITYMEASUREMENTSAn order issued on 17 October 2003 placed the technical management of the National networkfor environmental radioactivity measurements under IRSN’s responsibility.This network will collect the results of measurements conducted over the years by public establishments, governmentdepartments, nuclear operators, local authorities and associations. In particular, IRSN is to provide the secretarial services forthe steering committee prescribed by the order and take charge of the centralisation, processing and archiving of analysisresults. It is also required to make data available to the general public on a website. This network will help to estimatethe doses inhabitants are currently exposed to by the whole range of nuclear activities. In order to join the network, laboratoriesmust be able to guarantee the quality of its measurements by obtaining approval from the French Ministries for Environmentand Health after nomination by an approval commission. In this context, IRSN organised four cross-comparison exercises in2004. The Institute also supervised several working groups for the steering committee and the approval commission in order toregister all the measurements made and draw up the specifications of the future database.A temporary web portal was developed atthe end of the year and will be accessible to the general public in 2005.120I R S N ANNUAL REPORT 2004

Analysis of alkaline elements by atomicabsorption spectrometry.in the environment near the relevant site in orderto quantify the extent of releases and their impacton the environment. In 2004, with the monitoringfacilities used, it was possible to complete theinformation given by the operator regarding theevents during which accidental gaseous releasesof limited size were noted.Study was pursued in 2004 with DGSNR in orderto optimise monitoring by seeking greater relevanceof the radionuclides searched for and a decreasein the number of samples analysed (5,300 in 2004),which will reduce the waste produced by thelaboratory concerned.Metrology to support IRSN missionsAs the radioactivity contained in samples decreasesas time passes owing to the reduction in releases,IRSN is developing increasingly efficient techniquesfor the processing and measurement of radionuclidesfound in samples taken from the environment.Thanks to the competencies developed and themeans used, the Institute is able to process andanalyse radioactivity at low levels (a few tens orhundreds of Bq/kg) and very low levels (a few Bq/kg)in samples taken during radioactivity monitoringoperations, by applying protocols and techniqueswith a COFRAC-approved reference level. In thisway, some 30,000 samples entailing nearly90,000 measurements are processed every year inthe IRSN laboratories on its Le Vésinet site (Yvelines).The measuring facilities used can be mobilised foraccident or post-accident situations if necessary.Conducting of cross-comparisonsThe Institute organises and prepares samples forannual cross-comparison campaigns in the contextof public health code at the request of DGSNR forthe approval of measurement laboratories. Fourcross-comparisons were made in 2004, on theanalysis of low-activity radionuclides of naturalor artificial origin in various environmental matrices(water, algae, plants).Support for inspectionsIn its capacity as technical expert,IRSN provides supportfor basic nuclear installation inspectors conductingunexpected plant inspections,such as at Nogentsur-Seinepower plant (Aube) in January 2004.Technical support in the field of radonIRSN provided support in the following ways in2004:■ some 30 predictive mapping surveys wereconducted by various organisations using a varietyof methods to identity areas concerned by radonin certain French departments, in response torequests from DDASS and DRASS. DGSNR askedIRSN to prepare a report on these surveys and topropose criteria for the classification of geographicareas according to the level of their “radon potential”;■ as the reference organisation on the subject ofradon, IRSN contributed to the work of the Frenchnational commission for the approval of organisationsauthorised to conduct radon activity concentrationmeasurements in locations accessible tothe public;■ IRSN prepared technical data sheets givingexamples of the reduction of radon concentrationsin public, private and industrial buildings. Thesedata sheets were circulated to DDASS and DRASS.I R S N ANNUAL REPORT 2004121

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKOperation to recover a high-level irradiator in a clinic in Toulouse.Radiation protection responseand assistanceIn 2004, public authorities at bothnational and local levels called on IRSNon a dozen occasions for various operationswhich led to the discovery of ionisingradiation in inappropriate locations.One example was the case where radioactive materialwas found in a private home in Huningue (Alsace).At a first stage,these operations consist in establishingthe qualitative and quantitative characteristicsof the radionuclides found and the extent of theareas which may be contaminated.IRSN then undertakesto make the locations safe by placing the contaminatedequipment or sources in appropriatepackaging and storing it pending its subsequentelimination by a suitable process.Other types of operations are also carried out byIRSN,such as:assistance with radiation protectionon tritium-contaminated work sites at Ganagobie(Alpes-de-Haute-Provence), technical support forinspections carried out by public authorities (traincarrying irradiated fuel at Bordeaux railway station)and action taken on radon-contaminated sites.Radiation protection of workersIRSN contributed to the drawing-upof decrees and orders required bymodifications to French regulations onradiation protection of workers.The Institute also participated in the monitoringof the worker exposure and was involved in thescreening of applications for the approval of externaldosimetry laboratories and in the organisation ofcross-comparisons.Impact of changes in regulations onIRSN activitiesChanges in French regulations on worker radiationprotection were stipulated in decree No.2003-296,issued in 2003 and supplemented in 2004 by decreeNo.2004-1489 authorising IRSN to use the nationalpopulation register. IRSN played a part in thedrawing up of these decrees and the relevantimplementation orders which entrust IRSN withkeeping the national inventory of ionising radiationsources (SIGIS) and managing worker monitoringsystem (SISERI).Decree No.2003-296 also mentionsthe Institute’s role in the measurement of individualexternal and internal doses for exposed workers,in the provision of expertise such as surveys ofwork stations and consulting services to assistindustrial doctors and radiation protection officers.It also opens up prospects for studies and researchfor IRSN,such as the processing of dosimetric datafor epidemiological purposes.Follow-up of worker exposureIRSN uses the following two tools to follow upworker exposure:122I R S N ANNUAL REPORT 2004

Passive dosimetry.■ SIEVERT is used to assess doses in flying crew.This system,developed in collaboration with DGACis now operational. The model allowing for solareruptions for the calculation of doses has beenimproved since 2004.■ SISERI centralises all the dosimetric data onexposed workers on a nation-wide basis. 2004was a key year for the setting up of SISERI.The tasksstarted were successfully completed:- fitting out of renovated, secure premises for theteam responsible for running SISERI and computerservers;- installation and acceptance of computer systemwith, in particular, the recovery of data from theearlier database;- testing of the system’s various components (legal,IT,etc.) during the pilot phase (second half of 2004),with a limited number of establishments consultingor transmitting dosimetric data;- communication of information on the system’stime limits, features and statutory provisions tothe various partners and users (industrial medicalofficers and radiation protection officers);- publication in the OJ of:the decree of 30 December2004 authorising IRSN to use the national registerof persons (RNIPP);the order concerning the medicalsupervision form and individual dosimetric dataon workers exposed to ionising radiation; thefavourable opinion issued by CNIL on 24 June 2004regarding the management of confidential data inSISERI. These three statutory instruments werenecessary to officially start up SISERI.The system will come into operation in 2005, whenall contributors and users must be able to accessthe database in accordance with stipulated protocols.Work on the integration of the oldest dosimetricdata in the database will be continued.In this manner,SISERI should soon become an essential tool forthe follow-up of workers exposed in corporateenvironments and a powerful survey tool for theprocessing of the centralised data for the purposesof prevention and protection.Approval and cross-comparisonIn pursuance of the order of 6 December 2003,about four out of 10 external dosimetric laboratoriessubmitted applications to IRSN for approval by theWork Relationship Directorate in 2004. IRSNgives its opinion on the suitability of the equipmentand methods used by those laboratories.The order also requires IRSN to organise a crosscomparisonof the dosimeters proposed by thelaboratories.This cross-comparison was carried outin October 2004.I R S N ANNUAL REPORT 2004123

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKScanner acquisition console at Cochin Hospital.Radiation protection in the medical fieldThe justification of medical acts andthe optimisation of exposures are thetwo principles underlying the protectionof personnel exposed for medicalreasons.These principles are mentionedin the Euratom directive 97/43.In France, they are reflected in decreeNo. 2003-270 of 24 March 2003 andthe corresponding provisions areincluded in the public health code(articles R.1333-55 to 74).Reflection on the actions to be taken for theradiation protection of patients began in 1998 witha study mission entrusted to Professors Bonninand Lacronique concerning measures for theimprovement of patients’ radiation protection,i.e., reducing doses administered to the lowestpossible level, while maintaining the quality ofthe radiological treatment. Thereafter, a workinggroup of experts from institutional bodies andhealth professionals gave recommendationspublished by InVS in 2002.Then, in 2003, DGSNRRADIOGRAPHIC EXAMINATIONS IN SPORTS MEDICINEFOCUSAn order issued on 11 February 2004 defines the nature and frequency of medical examinations,which may be common to all sport disciplines or conducted for a specific sport discipline.Radiographic examinations may be prescribed, such as x-rays of the lumbar spine (front, side, 3/4 views) performed annuallybefore the age of 15 and then every two years, or of the cervical spine (front, side with measurement of the Torg ratio) everytwo years. The Sports Department of the French Ministry for Youth, Sport and Associations asked IRSN in 2004 to conducta study to assess the risks associated with prescribed radiographic examinations.IRSN examined several cases characterised by the morphology and age of the sport practitioner (in order to adaptthe parameters of radiographic examinations) and duration of the sporting career:■ slim or heavily-built sport practitioner;■ adolescent aged under 15 or over 15;■ sporting career of six years or ten years.For each of these cases, the doses received (in mGy) by the most exposed organ, by the thyroid gland and by the reproductiveorgans, and the effective dose (in mSv) were calculated. As regards the individual effective dose received over a whole sportingcareer, they are between 0.4 and 5.6 mSv, i.e., no more than approximately the dose received in a single scanning examination.124I R S N ANNUAL REPORT 2004

Scanner interpretation room.– in close cooperation with the relevant departmentsof IRSN and InVS – drew up an action planfor the monitoring of the exposure of patients toionising radiation of medical origin (PASEPRI).The courses of action adopted meet two objectives:■ improve knowledge of patients’ionising radiationexposure doses so they can be further optimised;■ gather the knowledge required for the subsequentdevelopment of action for the epidemiologicalmonitoring of the effects of ionising radiation onpatients.The relevant actions are classified into six categories:regulations,exposure information system,monitoringof effects of ionising radiation,surveys,the scientifictriality of information/training/technologymonitoring,and research. All these topics concernIRSN to varying degrees and some are actuallyincluded in its missions. Two topics concern IRSNin particular:diagnostic reference levels and medicalexposure observatory.Diagnostic reference levelsThe order of 12 February 2004 specifies in article 5:“IRSN is responsible for collecting the data requiredfor periodic updating of diagnostic reference levels.For this purpose, it receives, from the operator orthe authorised party,the results of the assessmentsconducted in pursuance of articles 2 and 3.” Theexaminations concerned by these provisions includeconventional x-ray examinations (six for adults,four for children), four scanning examinations inFOCUSJOINT IRSN/AVN/GRS GUIDE TO SAFETYASSESSMENTIRSN and its German and Belgian counterparts (GRSand AVN, respectively) have been developing closecollaboration in many fields for several years,including research, safety studies and exchanges of informationon problems encountered in nuclear installations in order to improvetheir competencies in nuclear safety. After in-depth comparisonof the safety assessment practices implemented by the three organisations,they decided to draw up a joint guide to safety assessment.The purpose of this guide is to give recommendations on theperformance of safety analyses with reference to safety dossierssubmitted by nuclear operators. It specifies the rules to be compliedwith in order to ensure the quality of those analyses and stresses,in particular, the objectivity and technical quality of assessmentsas these are essential factors for the credibility of the resultingappraisals. The guide is applicable to assessments for all typesof nuclear installations or activities, including transport and storageof radioactive materials.The work completed in 2004 concerned, in particular, the generalprinciples of conducting safety assessments. This will be followedby more technical aspects concerning safety principles and the keypoints of assessments for the various types of nuclear installationsand activities.I R S N ANNUAL REPORT 2004125

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKPositioning a patient for a scanning examination.adults and 10 nuclear medicine examinations.IRSN’s action in 2004 mainly consisted in presentingthe modes of application of these provisions tohealthcare professionals and updating data sheetsalong with experts from learned scientific societies.Data collection has been started. By late 2004,about 10 nuclear medicine departments (out ofapproximately 300) and one radiology department(out of about 5,000) had sent IRSN the data requiredby the order. In addition, several radiology departmentsasked IRSN for help in validating the dosimetricdata supplied by their installations or measuringthe doses delivered to patients’ skin.STRENGTHENING COOPERATION WITH CHINESE SAFETY AND RADIATIONPROTECTION ORGANISATIONSFOCUSHaving started some twenty years ago when French companies built the Daya Bay nuclear powerplant (China), cooperation between IRSN and its Chinese partners in the field of nuclear safety andradiation protection mainly concerned the training of personnel and the sharing of analysismethods and tools.In 2004, the Chinese authorities and IRSN agreed to give this cooperation a new boost which resulted in the performanceor start-up of several actions in the course of the year. In this context, the Director General of IRSN met the managersof the Chinese safety and radiation protection authority and of nuclear safety assessment and research organisations.In addition, a new programme was arranged to receive Chinese trainees at IRSN and a study was started to promote jointprojects on radiation protection and nuclear safety including the setting up of associated laboratories. Preliminarydiscussions were also held on the association of Chinese organisations with IRSN research programmes such asthe international CABRI programme and the SOURCE TERM programme.126I R S N ANNUAL REPORT 2004

Cardiological radiology installation at CochinHospital.Observatory of medical exposuresto ionising radiationThe frequency of the various radiological examinationsand the corresponding doses must be knownin order to assess what contribution medical exposuremakes to the population’s total exposure.This datais also required in order to meet the increasingpublic demand for information on medical practices,the number of treatment sessions and the correspondingdoses. For this reason, IRSN and InVS areworking together to create an observatory ofmedical exposure to ionising radiation for the purposesof public assessment.In 2004, preliminary work was carried out to drawup an analysis of the data available in France frominstitutional databases (CNAM-TS and SAE). Thisresulted in a count of approximately 44.3 milliontreatment sessions per year including 3.5 millionscanning examinations but the data did not provideany information on the exact nature of the treatmentsessions or their corresponding doses.However,this initial summary forms the basis on which theobservatory will rely for future tasks in two maincategories to be performed in 2005:■ creation of a network of establishments representativeof French practices;■ more specific investigations to obtain moredetailed analyses of practices.HOSTING TRAINEES FROM CHINESESAFETY ORGANISATIONSFOCUSHaving accepted a request for support fromthe IAEA regarding fire protection, IRSN welcomeda representative from China Atomic Energy Authorityand three engineers from Beijing Institute of NuclearEngineering in early May 2004.For two weeks, IRSN agents gave explanations of their methodsof assessment and the standards applied, illustrated by actual analysiscases. This new contact marks the beginning of a collaboration withChinese nuclear organisations in the field of fire and explosionprotection.Furthermore, in the context of collaboration between IRSN andNNSA-NSC, two engineers from the Beijing Nuclear Safety Centre(China) arrived at IRSN in October 2004 for a one-year stay: oneof them working on nuclear power plant safety reviews and the othertaking part in probabilistic safety assessments.IRSN’s fire and explosion protection specialists received a Chinese delegationon 14 May 2004 at the Fontenay-aux-Roses site.I R S N ANNUAL REPORT 2004127

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESOPERATIONAL SUPPORT IN THE EVENTOF A CRISIS OR RADIOLOGICAL EMERGENCYDiscussion between parties in the crisis is facilitated by using maps showingmeasurement points around the accident-affected installation.Operational support in the eventof a crisis or radiological emergencyIn the event of a crisis or radiological emergency, IRSN provides operational support during the emergency phaseitself but also during the post-accident phase. The Institute has the means to deal with all these situations.It implements and sizes them according to the magnitude of the event.In 2004, IRSN took part in the revision of officialtexts related to radiological emergencies and howto deal with them and in the transposition ofEuropean directives in these fields conducted bySGDN.This work particularly involved drawing upan interministerial directive on the action of publicauthorities in the event of a radiological emergencyand on the development of a directive related tothe performance and processing of environmentalradioactive measurements in the event of aradiological emergency. The first directive datesfrom 7 April 2005 and gives IRSN a central role inthe technical coordination and interpretation ofenvironmental radioactivity measurements. Toprepare for this role, the organisation of crisismanagement within IRSN evolved in 2004.EmergenciesIn the event of an emergency,IRSN providespublic authorities with operationalsupport based on fixed and mobilemeans that can be mobilised rapidly:emergency response centre,resourcesfor assessing individual exposure,etc.Developing crisis resourcesRenovating the emergency response centre (CTC)Renovation on the Institute’s CTC started in 2003and was completed in 2004. As well as renovatingthe infrastructures, the premises used for thetechnical units were enlarged and their ergonomicsimproved.Telephone equipment and audiovisualequipment was resized and access to documentationwas facilitated.Improving the duty systemIn 2004, the Institute carried out an overallreorganisation of its on-call system. Former practices,inherited from IPSN and OPRI were harmonisedso as to produce a coordinated,homogenousand coherent system. Moreover, the role of “dutyengineers” was clarified: they are now IRSN’s onlypoint of entry for emergency calls.The system also includes agents who can bemobilised for IRSN’s mobile unit. They will be rushedto the site of the accident in addition to the CTCagents.128I R S N ANNUAL REPORT 2004

PWR InstallationAssessment Unit (CEI REP) x 7• Supervisor• Control• Systems• Thermal-hydraulics• Containment• TIP/KPS• AudioconferenceRadiological ConsequencesUnit (CCR) x2• Design CCR• General CCRManagement Unit(CD) x1• Technical Secretarial Centre (IA)Mobilisationof CTCDutyengineerIncidentmanagement• SecretarySecretarial Unit(CST) x1Operations expertx2IRSN Mobile Unit x2• Measurement Coordination• Measurement FacilitiesRemote monitoring expert (TELERAY, etc.)Monitoring of nuclearmaterial transportx1The duty engineer is IRSN’s sole input point for all types of emergency calls24 hours a day.Organisation, methods and materialsThe crisis organisation,the methods and the expertassessment materials are constantly being improved.Discussions on the expert assessment methods tobe adopted for an accident affecting EDF reactorswere pursued. Material to assist in the expertassessment of the state of installations and theestimation of consequences for laboratories andplants was completed. In addition, in 2004, workwas carried out on emergencies that could affectan installation or ship of the French Navy.This workresulted in the definition and implementation ofa specific organisation for the Unit in charge ofassessing the installation (“CEI-Marine”) in theCTC. The Institute and naval staff entered intodiscussions with a view to drawing up a commonexpert assessment method and developing toolsto estimate the consequences of accidents.Exercises and feedbackIRSN took part in 12 exercises organised by publicauthorities to test the national crisis organisation,via the activation of its CTC and the dispatch ofits mobile unit to the prefecture’s operationalcontrol centre (PCO).It should be emphasized thatthe type of accidents envisaged (military installations,transport)and the subjects dealt with duringthe exercises are more and more diversified,especially during the post-accident phase.Among the lessons learnt from these exercises isthat it is essential to continue developing expertassessment methods.For EDF reactors,this concernsspecific situations (shutdown). For laboratories,plants and transport,we should continue developingpre-calculated data sheets on the three types ofdischarge, the consequences and specific tools.Finally, these exercises emphasized that a greateffort should be devoted to improving coordination,REAL ACTION TAKEN BY THE CTCIRSN’s Emergency response centre (CTC) went intoaction in 2004 when two real incidents affectedEDF’s nuclear power plants:■ on Sunday 16 May, a fire broke out in reactor 2 of the Cattenompower plant (Moselle), causing the destruction of electric cables.As a preventive measure, the operator activated the “safety andradiological” internal emergency plan (PUI). Alerted by DGSNR’swarning device, IRSN’s duty personnel arrived at the CTC at about03.00 p.m. and monitored how the situation was developing.At about 06.00 p.m., in the absence of anything worrying, the CTCwas deactivated and personnel were put on standby in their homesuntil the next day (see Focus p. 92: Incident at Cattenom);■ on Wednesday 23 June at about 07.00 p.m.,a second incident occured atthe Paluel site (Seine-Maritime).1 At about 07.00 p.m., a vastamount of seaweed comes in2 Clogging of the two rotating drumscreens for the cooling water for reactor 34563 Shortly afterwards, emergency shutdown of reactor 2was unavoidable and then reactors 1 and 4 were shut down as a precaution4 At the requests of EDF and DGSNR, IRSN mobilised its Emergency Response Centre (CTC)at about 11.00 p.m. to monitor the development of the situation5 The CTC remained mobilised all night long6 The decision to demobilise was made at about 03.00 p.m. the next day after various reviewsAlthough these two incidents presented little risk as far as reactorsafety was concerned, they showed the CTC’s capacity for reactionand the high level of professional motivation on the part ofthe duty teams.33231FOCUSI R S N ANNUAL REPORT 2004129

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESOPERATIONAL SUPPORT IN THE EVENTOF A CRISIS OR RADIOLOGICAL EMERGENCYDiscussion between the doctor and contamination measurement experts in IRSN’sMaster Gemini mobile laboratory.interpreting environmental measurements andmanaging the post-accident phase. Furthermore,the CTC should renew its mapping tools to be ableto meet the requirements of outside contacts moreeffectively.Fixed operational resources forassessing individual exposureIn the event of a crisis, in addition to its mobileresources,IRSN may have to use the fixed resourceslocated on the sites of Fontenay-aux-Roses (Hautsde-Seine)and Le Vésinet (Yvelines). These resourcesare dedicated to the dosimetric monitoring ofexposed workers and in the event of an accident,suspected external irradiation or internal contamination,they are used to assess the doses receivedby a small number of victims.For each of these resources,theoperational capacities have been estimatedby associating the number of examinations it ispossible to carry out with the acceptable detectionlimits for emergency assessments.The biological assessment of the dose received byexternal irradiation is based on the number of unstablechromosomic anomalies in the circulatingblood lymphocytes.IRSN has implemented a techniquethat can process 200 blood samples in twoEXERCISE IN DEALING WITH VICTIMS OF A RADIOLOGICAL ATTACKFOCUSIRSN took part in exercise R 53 concerning operations to deal with victims of a radiologicalterrorist attack. It was carried out at the Necker Hospital (Paris) on Sunday 10 October 2004and organised by the Paris Public Hospitals, SAMU 75 (mobile accident unit), Police Headquartersof Paris and DGSNR.The Paris Fire Brigade, SPRA and IRSN were invited to take part. The Minister of Health and the representative ofthe Minister of the Interior were present during the exercise.The scenario involved a “dirty” bomb exploding in a public place, leading to the spontaneous arrival at a hospital of50 people, plus three seriously injured people brought by ambulance. The aim of the exercise was to test whetherthe required equipment was in place in the event of radioactive contamination. Personnel from the Necker Hospital NursingCollege played the role of contaminated victims. The tents for receiving victims and for decontamination had been putin place beforehand so that they could be put up quickly.IRSN sent the following personnel to the Necker Hospital:■ two operators to carry out internal contamination tests with the mobile laboratory (Master Gémini);■ three operators to carry out radioactivity tests upstream and downstream of the decontamination chain;■ a doctor to observe operations;■ a specialist at the local emergency control centre called the “Control Tower”;■ a doctor in charge of communication.IRSN was involved in sorting the people who arrived at the hospital and carrying out individual contamination tests.130I R S N ANNUAL REPORT 2004

IRSN experts are called upon to create suitablescenarios for all crisis exercises.weeks with a dose uncertainty of ± 1 Gy. In 2004,a convention of mutual assistance was signed withNRPB (United Kingdom) and BfS (Germany)whereby each signatory can request assistancefrom the two other parties if more than 300 sampleshave to be processed. If those involved need to beprovided with passive dosimeters, IRSN has4,000 dosimeters that it can process in two batchesof 2,000 dosimeters in one and a half days foreach batch.Internal contamination is judged by measuringbodily retention via whole-body radiometry andby measuring radionuclides in excreta (urine,stools).The operational capacity of IRSN’s fixed whole-bodyradiometry resources for measuring pulmonaryretention of actinides,retention of radioactive isotopesof iodine in the thyroid and retention of fissionand activation products in the whole body is presentedin table 1. The operational capacities of IRSNin radiotoxicological analysis are presented in table 2.Depending on the complexity of the exposuresituation and the information available (the physicochemicalcharacteristics of the contaminant forexample), it takes between thirty minutes andfour hours to assess the dose received by a contaminatedperson.FOCUSEXERCISE IN DEALING WITH AN ACCIDENTINVOLVING TRANSPORTED RADIOACTIVEMATERIALOn 30 September 2004, a national crisis exercise wascarried out to simulate a transport accident involvingradioactive material.For the first time, the scenario concerned rail transport. There wassupposed to be a collision between a tanker and a railway wagon loadedwith a package of irradiated fuel from an EDF power plant, at a levelcrossing near Saint-Pierre-des-Corps railway yard (Indre-et-Loire).The expert assessment involved making a diagnostic of the condition ofthe package and forecasting its evolution so as to evaluate theenvironmental consequences of the accident and assess the solutionproposed by the sender for recuperating the package.As well as preparing and coordinating the exercise, IRSN deployedits crisis organisation to provide support to public authorities (itactivated the emergency response centre and sent a mobile unit to thesite of the accident).The exercise highlighted the progress made since the previous exercise,especially in the organisation of the mobile unit, and the main pointsthe Institute needs to improve, i.e., feedback from the site of theaccident, autonomy in means of communication, etc.Setting up an accident scenario.I R S N ANNUAL REPORT 2004131

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESOPERATIONAL SUPPORT IN THE EVENTOF A CRISIS OR RADIOLOGICAL EMERGENCYAt the operational control station, IRSN experts explain the action planto be implemented around the accident-affected installation to representativesof the fire brigade.Operational capacity of IRSN’s fixed whole-body radiometry resourcesPulmonary retention Retention of iodine Retention in the whole bodyof actinides in the thyroid of fission and activation productsRadionuclide 239Pu 241Am U natural 125I 129I 131I 57Co 60Co 134Cs 137CsDetectionlimit (*)(Bq) 13,800 60 750 3 5.2 6.4 100 72 64 100Countingtime 10 minutes 10 minutes 5 minutesOperationalcapacity 210 people per week 210 people per week 560 people per week(*) Detection limits were estimated for a standard man of 70 kg and increased to take into account a possible increase in the ambient background in the case of anaccident.Operational capacity of IRSN’s radiotoxicological medical analysis laboratoryDirect measurement Direct measurement Beta measurement Measurement Weighted measurementof gamma of beta of strontium 90 of alpha of uraniumemitters emitters in urine emitters (natural orin urine in urine in urine or depleted)(3H, 14C, 90Sr) stools in urine(238-239Pu,234-235-238U)Detection limit 16 Bq/l 3,840 Bq/l 1 Bq/l 2 Bq/l 5 µg/lCounting time 15 minutes 7.5 minutes 60 minutes 36 hours (*) Immediate measurementOperational capacity 270 samples 480 samples 60 samples 32 samples 50 samplesper day per day per day per day per day(*) A fixed period of at least three days must be added to the counting time for the pre-processing of the samples.Support in managing post-accidentsituationsTwo working groups were set up withinIRSN to develop proposals for guidelineson the management of post-accidentsituations and a strategy for measuringindividual and environmental radioactivity.The group working on “Guidelines” discussed thelifting of the sheltering directive after a nuclearaccident. Sheltering protects the population fromthe immediate consequences of an accident butcannot be prolonged for very long. A decision hasto be taken on whether to keep the population in132I R S N ANNUAL REPORT 2004

During the exercise, the fire brigade has the taskof taking field samples specified by IRSN.the area concerned or whether to move them awaytemporarily (or even definitively). This difficultsubject has received little attention from theinternational community and cannot be settledwith technical criteria alone. The parties involved(public authorities, elected representatives, thepopulation) would, no doubt, have to confer witheach other in depth during the post-accident phase.During this phase, the radiological risk comesfrom long-term, low-dose rate exposure.The group working on “measuring radioactivity”started by stating the main objectives of the radioactivitymeasurements at the different stages of anuclear or radiological crisis:■ during the emergency phase, the area affectedby the passage of the radioactive plume has to bedetermined,the radioactive release has to be assessedand the various consequences of the accidentevaluated;■ at the beginning of the post-accident phase,measurements enable an initial radiologicalcharacterisation to be made and help publicauthorities take decisions regarding the protectionof the population concerned;■ then, during the post-accident phase, measurementswill make it possible to define contaminatedareas where the maximum levels acceptable forthe marketing and consumption of foodstuffs havebeen exceeded and to define rehabilitation strategiesfor agricultural and built-up areas.Moreover,in 2004,the Institute continued developingcomputer tools for accident situations to measureenvironmental radiation (DATARAD) and producegraphic representations of these results (CARTORAD).This work should allow IRSN to effectively carryout its mission of centralising and interpreting, atnational level, all the results of the contaminationmeasurements taken during the accident situationPIERRELATTE EXERCISEThe main crisis exercise of 2004 was carried out atthe Tricastin site (Drôme) on 18 and 19 November underthe coordination of SGDN.This greatly mobilised the Institute in various ways. In addition toorganising the technical scenario, activating the CTC and sendinga mobile unit to the operational control centre, a new element wasintroduced, i.e., a person was sent the CICNR, placed under the authorityof the Prime Minister, and to a crisis unit set up by the Ministry of theInterior’s COGIC. These inter-governmental units do not systematicallytake part in all exercises.IRSN’s role here is to provide technical advice.Moreover, the Pierrelatte exercise presented a certain numberof characteristics: it was aimed at testing the ability of the nationalcrisis organisation to manage the emergency phase of the accident andalso the start of the post-accident phase. Among the issues addressedwas the lifting of the sheltering directive for populations living nearthe site. During the exercise, IRSN made various recommendations tothe safety authorities (DSND then DGSNR), related to consumptionrestrictions, rehabilitation of contaminated areas, taking a census andchecking the population. This exercise highlighted that IRSN needed toincrease its presence at local level in the event of crises.At the operational control station, IRSN reviews aspectsregarding the measurements taken in the environment.FOCUSI R S N ANNUAL REPORT 2004133

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESOPERATIONAL SUPPORT IN THE EVENTOF A CRISIS OR RADIOLOGICAL EMERGENCYIn IRSN’s truck, equipped with a radioactivity measurement laboratory, 12 peopleat a time can be given thyroid and chest check-ups.CD-ROM – “INFORMATION ON NUCLEARRISK AND HOW IT IS MANAGED”In April 2004, IRSN distributed a CD-ROM on nuclearrisk and how it is managed.The purpose was to provide clear information, accessible tonon-specialists, on nuclear accidents, their possible short - andlong-term consequences and the way an accident situationcan be managed.Indeed, it became clear that all parties concerned should possessthe same knowledge on nuclear risk and how to manage it.FOCUSThis CD-ROM is mainly intended for decentralised bodies in chargeof managing crises – prefectorial bodies, departments in charge ofcivil defence, fire protection, emergency services, departments incharge of health, agriculture and facilities, the police force, etc.It is also intended for CLIs, given the diversity of the missionsthey carry out.In 2004, the Institute supported the distribution of this tool byorganising detailed presentations of the CD-ROM, at the requestof DSND, ANCLI’s Scientific Board, SGDN’s protection andsafety of the State division and the CLI of Nogent-sur-Seine (Aube).and the post-accident situation by the variousteams,especially the fire brigade and the operators.To evaluate how the contamination of the foodchain and the different parts of the biosphere evolveover a period of time, the Institute’s CTC relies ona specialised team located at Cadarache (Bouchesdu-Rhône)that uses impact calculation tools likeASTRAL and cartographic representation softwareprograms.The team can thus integrate the environmentaldata from the field and from modelling.This organisation was tested during the SECNUC,post-accident phase, crisis exercise. It concernedan accidental release from the COGEMA installationsin Pierrelatte (Drôme) on 18 and 19 November 2004.Indeed, IRSN was very involved in the preparationof this exercise, coordinated by the SGDN and theMARN (DDSC). It was also involved in the exercisecarried out in Belleville-sur-Loire (Cher) in March2005.The Institute’s support in this field included:■ preparation of the strategy to measure radioactivityin the environment and in foodstuffs;■ identification of the actions that could be implementedduring the hours following the lifting ofthe sheltering directive;■ development of a draft version of a tool thatwould help IRSN’s CTC decide upon the first actionsneeded for the rehabilitation of agricultural andbuilt-up areas.134I R S N ANNUAL REPORT 2004

The renovation of mobile facilities entails theupdating of a whole range of equipment (vehicles,measuring equipment, data processing equipment).Operational support in case of crisisIRSN provides the State’s decentraliseddepartments with in-the-field operationalsupport for the coordinationand validation of radioactivity measurementsperformed by different operatorsin the environment and on thepopulation.This support concerns the emergency phase andthe post-accident phase.In 2004,for each exercise,the Institute’s mobile unit, composed of a teamto coordinate measurements and a team with amobile measurement system, was mobilised forreal or fictive situations and put at the disposal ofthe site’s operational control centre. During the“transport” exercise at Saint-Pierre-des-Corps(Indre-et-Loire), the unit was reinforced by a unithead who also gave operational radiation protectionadvice to those involved in the exercise.PLAN TO RENEW MOBILE RESOURCESFOCUSIn 2004, IRSN started drawing up a plan to renew its mobile resources. This mainly concernsthe resources needed for the different situations that the Institute may have to deal with.The Institute has a stock of mobile resources, the oldest of which was developed in the 1970s but most of which date backto the 1980s. They are intended for carrying out large-scale anthropogammametric measurements on people likely to have beenexposed to radioactive releases. The purpose of these measurements is to sort the population according to their levelof internal contamination in order to direct them to the suitable medical departments.These resources can also be used to measure radioactivity present in food chain samples or environmental samplesvia γ spectrometry.These resources have been used in France during emergency exercises in which IRSN participated and for various otheroperations: at polluted sites (the Bayard site in Saint-Nicolas-d’Aliermont, Seine-Maritime), to monitor transportation(SNCF wagons), to measure exposure to radioactive fallout from the Chernobyl accident (Saint-Jean-d’Ormont, Vosges,and in the Mercantour) or for incidents involving contamination during the shutdown of nuclear power plants.The stock of mobile operation resources has, on the whole, been maintained in operational condition but due to its age,it is becoming more and more difficult to maintain.I R S N ANNUAL REPORT 2004135

1,714,000personal dosimeterssupplied and used1,019analysesof drinking watercarried out150analysesof foodstuffscarried outAlmost150radiation protectionoperations136I R S N ANNUAL REPORT 2004

IRSN ACTIVITIES IN 2004Contractual servicesof expert appraisal,research and measurementSelling services enables IRSN to turn to account the know-how and specificskills it has acquired in the nuclear field that are applicable to other fieldsof activity. Selling services is also a way of optimising the use of technical platformsdeveloped for research programmes. It also enables the Institute to diversifyits sources of income.Excluding the co-financing of research, the services provided by IRSN correspondto about 5% of its present budget. Once developed, they should not exceed 15%of this budget. Moreover, the Institute is careful to ensure that these services remaincompatible with its mission of support and technical assistance to public authorities.> 138 Services related to statutory requirements> 142 Services not related to statutory requirementsI R S N ANNUAL REPORT 2004137

CONTRACTUAL SERVICES OF EXPERT APPRAISAL,RESEARCH AND MEASUREMENTSERVICES RELATED TO STATUTORYREQUIREMENTSEvaporator room of the water analysis laboratory at Le Vésinet (Yvelines).Services related to statutoryrequirementsRadiological testing of water intendedfor human consumptionThe evolution of regulations aimed atproviding better consumer protectionhas led to a high demand in radioactivitymeasurements of water intended forhuman consumption. IRSN providesradiological water analysis services tomanufacturers and regulatory bodies(DDASS).The radiological quality of water is assessed viatwo parameters:the total indicative dose (TID) andthe tritium activity. The measuring strategy consistsin measuring the tritium activity and the overallactivity of alpha and beta emitting radionuclides.If these activities are less than 100 Bq/l, 0.1 Bq/land 1 Bq/l respectively, the TID is considered asless than 0.1 mSv per year.If this is not the case,furtheranalyses are carried out to identify the natural orartificial radionuclides responsible for theseexcessive values and a dose calculation is conductedfor a consumption of 730 litres of water per year.This dose is then compared with the 0.1 mSv/yeardefined by the Euratom directive, based on theWHO recommendations.The time required to conduct the analyses variesfrom 4 to 12 weeks,depending on the tests.In 2004,about 20% of the cases processed required furtheranalyses.As a result of new regulations,IRSN testedthree times more samples in 2004 than in 2003.Radon detectionWithin the framework of risk management relatedto radon in buildings, IRSN provided detectionservices and conducted further investigations asdefined in the regulations. In 2004, radon measurementswere taken in several establishments opento the public. The IRSN department concerned(Radiation protection Response and AssistanceService) received ISO 9001 certification from AFAQfor studies and expert assessments conducted inradon control.138I R S N ANNUAL REPORT 2004

Cobalt 60 irradiator, “ICO 4000”.Radiation protection of workersDecree 2003-296 of 31 March 2003and the associated application orders,aimed at protecting workers fromionising radiation, have led IRSN to provideservices involving the measurement of individual,external and internal doses in exposed workers,expert assessments involving workstation studiesand consultancy services for industrial physiciansand people skilled in radiation protection.Monitoring external exposureof exposed workersOver 250,000 workers are at risk of external exposureto ionising radiation in France. According toregulations, the monitoring of occupational exposureis conducted via passive dosimetry whateverthe field (medicine, the nuclear industry or not).There are various techniques for measuring doses:photographs,thermoluminescence or trace detection.They result in a wide range of dosimeters adaptedto various radiation fields and variable doses.In 2004, IRSN monitored about 150,000 workersin 18,000 establishments. The breakdown ofdosimeters used for this is as follows:■ 1,600,000 photographic dosimeters;■ 61,000 thermoluminescent dosimeters;■ 53,000 trace-detection dosimeters.Monitoring the internalcontamination of exposed workersAssessing the exposure of workers at risk of internalcontamination is conducted by determining theincorporated activity in the body. Two types ofanalyses are used,i.e.,measurement of incorporatedactivity via whole-body radiometry and measurementof excretion activity via the radiotoxicologicalanalyses of urine and stools. In 2004, IRSN:■conducted 131 whole-body radiometry examinations;■ and regarding radiotoxicological analyses:- 3,889 people were monitored;- 7,790 biological samples were tested (urine,stools,hair, nails, blood);- 21,089 tests were conducted;- 64 different radionuclides were measured duringanalyses.Qualification of measuring installationsIn 2004, IRSN was requested on several occasionsto examine whole-body radiometry installations:Civaux nuclear power plant (Vienne), CEA centresin Valduc (Côte-d’Or) and Grenoble (Isère) in orderto check the calibration quality of these installations.Studying workstations on SNCFtrains transporting radioactivematerialRegulations regarding the rail transport of dangerousgoods require operators to have a radiologicalprotection programme for the transport ofradioactive material.Within this framework,SNCFentered into a contract with IRSN whereby thelatter will carry out dosage measurement campaignsat workstations for the nine types of radioactivematerials transported.In 2004,IRSN characterisedfour types of transported material. The five othertypes will be studied in 2005.I R S N ANNUAL REPORT 2004139

CONTRACTUAL SERVICES OF EXPERT APPRAISAL,RESEARCH AND MEASUREMENTSERVICES RELATED TO STATUTORYREQUIREMENTSApproval of protection equipment by technical centres.Conformity of materials and equipmentIRSN has two technical centres incharge of checking that equipment andmaterials comply with standards (orany other pre-defined baseline).Thesecentres can intervene at the requestof operators,manufacturers or authorities,within the framework of programmesinvolving the developmentof materials or processes or to meetstatutory requirements.In their fields of expertise,they take part in drawingup statutory and normative texts for France andfor other countries.The activities of IRSN’s Technical Centre for RadiologicalProtection Instrumentation Approval (CTHIR)involve individual dosimetry, atmospheric orenvironmental dosimetry,measurements of contamination(water, air, surfaces) and detection ofcriticality accidents.In 2004, CTHIR participated in standardisationworking groups within the framework of the SC45Bsubcommittee in charge of radiation protectioninstrumentation within IEC.2004 saw the publicationof standard IEC 62022 for which the CTHIR wasproject manager. It concerns systems to detectsources of γ radiation transported in vehicles.CTHIRis also part of the French delegation to CENELEC(European standards) and is in charge of transcribingIEC standards into European standards.After analysing test results and technical dossiers,CTHIR gave its opinion on the compliance to relevantstandards of an operational dosimeter and a detectionset for criticality accidents. It calibrated17 probes associated with this type of system – thisis done before they are first put into service or whenthey are returned for maintenance.Examinations on the compliance of radiation protectionequipment are carried out in accordancewith CTHIR’s quality management system whichreceived ISO 9001 certification, version 2000, atthe end of 2002.CTHIR operates the IRMA irradiator (Saclay,Essonne).This installation can irradiate equipment andmaterial within the framework of studies on theirresistance to radiation (dose rate of up to 20 kGy/h).Campaigns conducted in 2004 represent a total oftwenty-eight weeks and were mainly directed at researchunits and manufacturers of radiation detectors.The expertise of IRSN’s Technical Centre for NuclearEquipment Approval (CTHEN) involves the approvalof safety equipment used in the nuclear industry(mainly high-efficiency filters and fire dampers)and the certification of individual protectionequipment.140I R S N ANNUAL REPORT 2004

Operational dosimetry.CTHEN receives notice from the Ministry of Labourto carry out EC type examinations on clothing andgloves intended to protect workers from ionisingradiation or radioactive contamination.Its missionsare governed by an agreement signed on 23 August2004 between IRSN and the Ministry. Two typesof ventilated clothing received “EC” certificationin 2004 and 118 “extended”certificates were issued(following modifications to previously certifiedequipment or associated technical dossier).NON-NUCLEAR THIRD-PARTY EXPERTISEFOCUSExpertise gathered in the field of nuclear safety enables IRSN to conduct critical analyses of studieson the environmental dangers of classified industrial facilities belonging to different sectorsof activities (agri-food industries, fine chemistry, petrochemistry, etc.).Among the 50 or so critical analyses conducted by IRSN in 2004, we can cite those linked to ARKEMA’s sites in Balan (Ain),Carling (Moselle), Saint-Fons (Rhône) and La Chambre (Savoie), Cristal Union’s alcohol distillation plants in Bazancourt(Marne) and Bray-sur-Seine (Seine-et-Marne), Grande Paroisse’s plant in Grandpuits (Seine-et-Marne) that manufacturesammonium nitrate-based fertilisers, SOGIF-Air Liquide’s sites in Fos-sur-Mer (Bouches-du-Rhône), Tavaux (Jura), Richemont(Moselle) and Grand-Synthe (Nord).To conduct these analyses, IRSN relies on its expertise in thefollowing fields: fire, explosion, atmospheric dispersion, commandcontrol, reliability of components, human factors, seismology,flooding, etc.The Institute also takes part in different working groups set upby the Ministry of the Environment and Sustainable Development:technological risk prevention plans, toxicological reference values,a group of third-party expert bodies as well as several sector-basedworking groups (chlorine, LPG, ammonia, flammable liquids, etc.).Finally, IRSN provides the administration with technical supportwhen discussions are held at European level on the bestStaff of the non-nuclear installations safety analysis centre. technologies available in terms of risk prevention.I R S N ANNUAL REPORT 2004141

CONTRACTUAL SERVICES OF EXPERT APPRAISAL,RESEARCH AND MEASUREMENTSERVICES NOT RELATED TO STATUTORYREQUIREMENTSChecking a filter with a radiation measuringassembly.Services not related to statutoryrequirementsStudy regarding the presenceof radionuclides in the Toulouse urban areasewer systemIn 2004,IRSN conducted a study at therequest of the Toulouse water company,Compagnie Générale des Eaux deToulouse (Haute-Garonne), on theorigin of low-level radioactivity foundin the Toulouse urban area sewagesystem.A portable Telehydro probe has been developedto take measurements at precise points along watercourses.This study, in fact, was focused on the presence ofradionuclides in discharges from hospitals usingunsealed sources for diagnostic or radiotherapypurposes.Having a half-life of about eight days,theiodine 131 used was found in waste water, sludgeand incineration residues at water treatment plants.Technical landfill centres could refuse to acceptthese residues owing to the presence of thisradionuclide.The study comprised four successive phases:verification of the origin of the radionuclides witha Telehydro portable detector,identification of thesource (urine or faeces) of the radioactivity, studyof its dilution in the sewer network, and measurementof the dose rate at various points of thepurification plant. The results were presented inDecember 2004 and the study report was deliveredto the customer in February 2005.142I R S N ANNUAL REPORT 2004

The radiological monitoring of nuclear powerplants entails taking samples from allenvironmental milieus.Operational radiation protection servicesIRSN’s services in operational radiationprotection cover all entities possessingor using ionising radiation sources,mainly in France but also in other countries.These services consist in consulting and study activities(sealed or unsealed sources, contaminatedsites), monitoring of equipment and installations(statutory radiation protection inspections,inspectionson the efficiency of VHE filters and iodine traps)and action (such as safetying of sources,radon detectionand measurements) especially in abnormalconditions. In 2004, the Institute provided about150 service missions of all types. Its customersincluded industrial firms in the nuclear field (EDF,COGEMA, DCN) and also public and privateorganisations.Radioecology servicesIRSN provides measurement and studyservices in the radioecological field forindustrial firms and public authorities.Radioecological follow-up of nuclearpower plantsEvery year since 1991, IRSN has conducted radioecologicalmonitoring of French nuclear powerplants for EDF.This entails identifying and characterisingthe marking due to effluent releases fromthose power plants as opposed to radioactivity ofother exogenous origins:atmospheric nuclear testsin the 1960s to 1980s, the Chernobyl accident andreleases from hospitals.This annual study involves the sampling andprocessing of between 600 and 700 samples inland,aquatic,continental and marine environments.IRSN has developed the necessary tools and knowhowin the fields of sampling, sample processingand analysis and in the interpretation of results inorder to take into account the very low activityActivity report (137Cs/134Cs)1000100101Chernobyl falloutMeasurements in effluentsDownstream detection0,11986 1990 1995 2000 2003137Cs/134Cs activity reports measured in continental aquatic samples takendownstream of power plants, from power plant effluents and fallout fromthe Chernobyl accident.levels to be measured. These chronological seriescomplete those supplied by IRSN’s OPERA networkand can be used to annually update the environmentalbaselines for areas near nuclear power plantswhether or not they are affected by releases.I R S N ANNUAL REPORT 2004143

CONTRACTUAL SERVICES OF EXPERT APPRAISAL,RESEARCH AND MEASUREMENTSERVICES NOT RELATED TO STATUTORYREQUIREMENTSTricastin nuclear power plant (Drôme).The services agreement with EDF also encompassesapplied studies,particularly regarding the behaviourof carbon 14,tritium and iodine 129 in the environment.This agreement was renewed for the years2005-2007.Studies around the COGEMA sitein La HagueThe radioecology services contract of several years’standing between IRSN and COGEMA has beenextended to cover two topics concerning theirradiated fuel processing plant in La Hague(Manche). As a result, a first study in 2004 wasconducted to validate the DISPRO calculation codeused to predict the dispersal of radionuclide releasesin the Manche area of France from the La Hagueplant. This required offshore measurementcampaigns off the coast of Nord-Cotentin. A secondstudy concerned granulometric distributions ofaerosols discharged by the stack of plant UP2-800.It showed that the aerosols released were scatteredin the environment in liquid form and probablycontained organic components.Operating method for radon measurementIn the context of its “quality” policy, Gaz de Franceregularly analyses the composition of the gas itdistributes. An operating method to measure radonin natural gas was defined by IRSN. This processinvolves special technical skills which requiredthe training of Gaz de France personnel by IRSN.Services concerning dispersalof contaminantsIRSN provides contractually specifiedservices regarding the ventilation ofinstallations and the dispersal ofradioactive and non-radioactive contaminants(such as malodorous contaminants)in nuclear and non-nuclearfields.These services include studies on the behaviourof installations’ ventilation systems in normal oraccident conditions. They are based on the use ofcalculation codes developed by IRSN (SIMEVENTor FLAMME_S/SIMEVENT when the accidentsituation studied consists in a fire outbreak in ventilatedpremises).Modelling and study workThe modelling used in the SIMEVENT code is basedon an electrical analogy in which the ventilationsystem is divided into nodes (pressure,temperatureand uniform concentrations) connected by branchesrepresenting the behaviour of various items ofequipment (fans, pipes, filters, valves, regulators,etc.). The code simulates air flows in the system144I R S N ANNUAL REPORT 2004

++-LPG storage spheres.in steady-state or transient operating conditions(calculation of pressure values at nodes and flowrate values in branches). It also processes thetransport and retention of gaseous and particulatespecies and the clogging of filters by aerosols.Themain input data is the air resistance values of thevarious resistant equipment (calculated on thebasis of pressure and flow rate values measuredwith the installation in a given state) and theoperating curves for the various fans.Conducting a study with the SIMEVENT code beginswith the modelling of a reference state for theventilation system on the basis of the study ofdrawings, an on-site study and measured resultsgenerally provided by the firm. It is then possibleto calculate the ventilation systems after modificationsto the installation, for example, or thesequences of degraded or accident situations onSchéma de ventilationV1V1Laveur+ -Ventilation drawing.ABC+ DEFGCooling coilBalancing damperHeating coil Isolation damperVHE filterPressure controllerV3V3Check valveFanV2PROBABILISTIC SAFETY ASSESSMENTS APPLIED TO INDUSTRIAL SITESFOCUSOwing to the experience IRSN has acquired on pressurised water reactors, the Ministry of Ecologyand Sustainable Development has entrusted it with a pilot project for the developmentof a probabilistic safety assessment (PSA) for an industrial installation of the Seveso type.The objective of this project is to clarify the contribution that a probabilistic assessment could make to the studyof the safety of industrial installations.The site chosen is the filling centre at Herrlisheim (Alsace), operated by Rhône Gaz, which volunteered for the project.The selected plant receives, stores, packages and ships liquefied petroleum gas (LPG).The study entails identifying the various accident sequences which could lead to a BLEVE and identifying the probabilitiesof those sequences. The scenarios examined feature the occurrence and then the ignition of a gas leak resulting in a fireaffecting, in the short or medium term, one of the storage containers: either a road tanker or a tank wagon.After defining a suitable study procedure for the installation, IRSN performed modelling in 2004 for a case representingthe initiating event leading to BLEVE (leak on an LPG pipe). The method adopted, drawn from the method used for PSAsperformed by IRSN for nuclear power plants, was validated and then generalised to cover all triggering events.The final report will be delivered in 2005.I R S N ANNUAL REPORT 2004145

CONTRACTUAL SERVICES OF EXPERT APPRAISAL,RESEARCH AND MEASUREMENTSERVICES NOT RELATED TO STATUTORYREQUIREMENTSControl panel of the irradiation room for radiobiological studies or high-leveldosimetry.RQPONMLKJIHGFEDCBA-50018000-40018000-300180000Schéma SIMEVENT*500 45035001001 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21SIMEVENT drawing.0600-206000 5800130-50-170 -300 -170 -950 20012500 3000330014500 14500 145005003500-70300-100100-70P105A300P105BP105CP105DP105EP105FF2 F6 F8 F12200100 -200-60014001500150050600-900P105GHOD6 D8 D12N0J2 J4 J6 J8H22000100600-10020001500100360018001950-300 -700N12 N14 N16 N18 N20300NodeChute strength* FanFilter strengthDuct strengthDownstream pressurecontrollerCheck valveAtmospherecontainment in the installation.These calculationsare performed using scenarios and hypotheseswhich are precisely described by the firm in its*150150200L20*-950 -1500 -18004100 4300 4300I20G20E14 E16 E18 E2014500410050K22186000N0specifications. Some studies have the aim ofbalancing the ventilation of an installation bycalculating the position of balancing dampers soas to obtain the desired pressure values in thepremises concerned.As a result of an increase in the number of requestsfor services, five major CEA installations werestudied in 2004. This type of service is of greatinterest to IRSN as it is a means of obtaining usefulfeedback on actual applications of the calculationcodes it has developed.It is important to emphasisethat these services do not constitute a safetydemonstration and that the results obtained in thiscontext do not give any indication of the conclusionsthat may be drawn by IRSN when, in response toa request from a safety authority, it assesses asafety dossier incorporating those results.Dosimetry servicesIRSN’s installations, certified byCOFRAC, specify reference radiationlevels for photons and neutrons.Theyare ideally suited for the provision ofservices in the field of metrology:qualification and calibration of dosimeters andmeasuring instruments for radiation protection.IRSN also performs studies to characterise variousinstallations:determining the dose rates and energyspectra for ionising radiation present in theinstallations examined. IRSN is also called upon inthe field of biological dosimetry to assess dosesreceived in cases where irradiation is suspected.In all fields,it receives requests for its services fromwithin France and other countries.Characterisation of radiation fieldsin installationsCALIBAN installationIn 2004, on request from the CEA centre at Valduc(Côte-d’Or), IRSN carried out a measurementcampaign on the CALIBAN reactor (CEA-Valduc)which is able to generate intense pulses of neutronsand fission gamma rays. The study consisted incharacterising the beam of mixed neutron-gammaradiation produced by the reactor.Proton therapy centreOphthalmic and intercranial tumours are treatedusing proton beams at the Orsay proton therapycentre (Essonne). Secondary radiation, mainly146I R S N ANNUAL REPORT 2004

Measurement with a tissue equivalentproportional counter for the CPO protonbeam line.consisting of high-energy neutrons, is producedsimultaneously and causes additional exposureoutside the beam,during treatment.To assess theseexposures for patients and the doses delivered tothe various electronic systems, IRSN conductedthe mapping of dose rates in the treatment roomin 2004.Krsko reactorIn October 2004,IRSN carried out neutronic measurementsat the Krsko nuclear power plant (Slovenia)on request from the operator.For highly irradiatinglocations,the measurements were performed witha set of Bonner spheres.Reactor of Le Vigilant nuclear submarineTechnicatome is a company with a multi-spheresystem that is almost identical to that at IRSN forneutron spectrometry. This system was used toconduct measurements in 2004 on ISO referencesources from IRSN and then in the environmentof the Le Vigilant nuclear submarine’s boiler roomin order to verify whether the fluence responsefunctions of the spheres in the IRSN system weretransferable to the Technicatome system.Metrology activityIn 2004, the IRSN ionising radiation dosimetrylaboratory, certified by COFRAC for referencephoton beams, issued 53 calibration certificates:nine for IRSN and 44 for external customers. Inaddition,it supplied two test reports in the contextof the approval of dosimetric instruments.Furthermore,in response to demand from some manufacturers,seven weeks were spent perfectingdosimeters with calibrated beams.The IRSN neutron metrology and dosimetrylaboratory, certified by COFRAC for referenceneutron radiation,issued 11 calibration certificates.In addition, IRSN contributed to the EuropeanEVIDOS project which aims to compare theresponses of individual active or passive dosimetersexposed in mixed neutron-photon fieldsrepresenting those encountered in the nuclearindustry.IRSN is responsible for providing neutronenergy spectra and reference magnitudes (doseequivalent Hp(0.07) and Hp(10)).In accordance with regulations, IRSN organised,at the end of 2004, a cross-comparison of dosimeterssupplied by organisations that had appliedfor approval for the assessment of external exposureby means of individual passive dosimeters (516 dosimetersconcerned). As the reference laboratory,IRSN also participated in the cross-comparison ofpassive dosimeters organised by the IAEA.Assessment of activity in biologicaldosimetryThe estimation by biological dosimetry of dosesreceived in cases of suspected or proven radiationis based on the observation of unstable dicentricchromosomal aberrations formed in the lymphocytesof the individuals concerned.Since 1992,theIRSN biological dosimetry laboratory, the onlyrecognised laboratory in France for this type of assessment,has performed more than 200 estimates ofindividual doses, including five in 2004.For cases among the assessments performed in2004, the individuals had been exposed severaltens of years previously for various reasons andwere, in particular, present in locations with highradioactivity. Owing to specific pathologies,these persons consulted a doctor who looked fora link between their pathologies and possibleI R S N ANNUAL REPORT 2004147

CONTRACTUAL SERVICES OF EXPERT APPRAISAL,RESEARCH AND MEASUREMENTSERVICES NOT RELATED TO STATUTORYREQUIREMENTSDevelopment of passive dosimeters.exposure to ionising radiation. In three of the fourcases, the number of chromosomal aberrationsobserved was greater than that for the non-exposedpopulation taken for reference. On the basis ofthese results, it may be considered that theseindividuals were indeed exposed to substances,radioactive or not,which could cause chromosomicaberrations.In four other cases,IRSN was called in for individualswhose dosimeters indicated exposure although thecircumstances of that exposure were not clear.Toconfirm the doses received,the only way of clearingup any doubt is to perform dosimetry on theindividuals themselves:two of them had a positivebiological dose of borderline statistical significanceand two had a biological dose that was not differentfrom zero.IRSN was also asked to carry out a biologicaldosimetry assessment for three persons workingon the demolition site of a former clinic and whomay have been in contact with radium needles. Infact, none of them had been exposed to anysignificant extent.148I R S N ANNUAL REPORT 2004

Reading and interpreting films.Conventional radiology at Cochin Hospital,Paris.Assessment of dose receivedby the foetus during a diagnostic examinationon a pregnant womanIRSN is regularly called upon to conductdosimetric assessments for pregnantwomen who have undergone radiologicalexaminations.When exposure to ionising radiation is envisagedfor a woman of child-bearing age, the consultingdoctor and the doctor who performs the examinationmust check whether she is pregnant. Ifpregnancy is confirmed or cannot be ruled out,special attention must be paid to the justificationfor the examination.Allowance must be made forthe urgency of exposing the woman and the unbornchild. Nevertheless, every year there is a numberof accidental exposures of pregnant women. It istherefore not unusual for medical physicists to beasked to assess the dose received by the foetus.Nearly all these requests concern conventionalCONSULTING AND ASSISTANCE FOR HEALTHCARE PROFESSIONALSFOCUSThe IRSN medical radiation protection assessment unit circulated a leaflet in 2004 to informhealthcare professionals of its missions regarding the radiation protection of patients and workersin the medical field:■ collection and periodic updating of diagnostic reference levels;■ assistance and consulting of healthcare professionals;■ information to healthcare professionals and radiation protection training for personnelin the medical field;■ performance of studies and assessments for healthcare professionals, patientsand, more generally, persons exposed to ionising radiation in the medical field;■ technical support for national authorities and organisations concerned by the radiationprotection of medical personnel and patients;■ contribution to knowledge of medical practices which may result in exposure to ionisingradiation, through an observatory set up in collaboration with InVS.These missions concern about 18,000 professional staff, 130,000 workers and a greatmany patients for an equipment population of approximately 50,000 installations rangingfrom the dentist’s x-ray equipment to the 30-MV linear accelerator. The leaflet was circulated during the French nationalradiology conference days (between 5,000 and 6,000 participants) and conference days for radiation protection officers(nearly 500 participants). These events provided the opportunity to meet professionals requiring advice and assistancein order to implement decree 2003-270 of 24 March 2003 and its implementation orders.I R S N ANNUAL REPORT 2004149

CONTRACTUAL SERVICES OF EXPERT APPRAISAL,RESEARCH AND MEASUREMENTSERVICES NOT RELATED TO STATUTORYREQUIREMENTSControl desk of the interventional radiology department at Cochin Hospital, Paris.radiology and scanning, with the foetus located inthe region examined or not.In 2004, dosimetric assessments were conductedby IRSN on 51 pregnant patients who had undergoneone or more radiological examinations.These caseswere divided between conventional radiology (38)and scanning (23).Reconstitution of the dose received by the foetusis based, as far as possible, on the actual characteristicsof the examination. For this purpose, formsto be filled in by radiologists have been createdfor scanning, conventional radiology, vascularradiology and interventionalradiology. These forms specify allthe parameters required in orderto reconstitute precise doses (typeof installation, detector used, highvoltage,exposure time,charge,doseindex for conventional radiologyand scanning, etc.). Allowing fortechnological developments and,in particular,the complexity of themedical equipment, the data is transmitted withmore or less detail and accuracy by the requestingparties. As a result, the dose values for the foetusare assessed either on the basis of data specific totypical radiological procedures (in cases where littleinformation is known) or by simulation softwareafter entering the exact parameters of the examination.For the assessments conducted in 2004, the estimateddoses range from less than a few micrograys,when the foetus is within the diffused radiation(13 cases) to 55 milligrays (µGy), when the foetusis in the region examined by scanning. For 14cases (27.5%), the dose was less than 1 mGy; for20 cases (39.2%),the dose was between 1 and 10 mGy;for 12 cases (23.5%),it was between 10 et 30 mGy;for five cases (10%), it was between 30 and 55 mGy.Compared with international recommendations andespecially the recommendations in ICRP publication84,these doses are lower than the value of 100 mGybelow which no effect has been demonstratedregardless of the number of weeks into pregnancy.Scanner interpretation console.150I R S N ANNUAL REPORT 2004

The Rovno plant in Ukraine.Collaboration with Eastern EuropeancountriesSince the beginning of the 1990s, theinternational community has developeda high level of collaboration withEastern European countries in order toimprove the safety level of their nuclearinstallations and reinforce the regulationsthey have introduced.Nuclear safety in Eastern European countries is amajor target for IRSN’s international action. Cooperationin this field, in partnership with GRSand in close collaboration with other Europeantechnical safety organisations and those of thecountries concerned, involves in particular thedevelopment of statutory frameworks,the transferof design codes and training in their utilisation,and the conducting of safety assessments.ASSISTANCE TO EASTERN EUROPEAN COUNTRIESFOCUSIRSN took part in about 30 projects providing assistance to Eastern European countries in 2004 inorder to improve the safety of their nuclear installations. In particular, the Institute participated insafety reviews for the RBMK reactors in Lithuania and Russia and the WER reactors in Ukraine.In Lithuania: In 2004, IRSN continued its participation in the safety review for the new emergency shutdown system for reactor 2at the Ignalina power plant whose installation was completed in summer 2004. This review was conducted in the contextof a European project providing support for the Lithuanian safety authority (VATESI) managed by Riskaudit.In Russia, the in-depth review of the safety report on reactor 1 of the Kursk power plant, which began in December 2001,was completed in May 2004. Financed by the nuclear safety fund (NSA) managed by EBRD, the project worth about 1.5 million eurosbrought together some 50 Western experts representing about 10 nuclear safety organisations from seven countries: IRSN (France),GRS (Germany), SERCO Assurance and NNC (United Kingdom), ES Konsult (Sweden), NRG (The Netherlands), AECL (Canada),Scientech and PNNL (United States) and about 50 Russian experts. This in-depth safety analysis led by IRSN, was the firstof this type conducted in Russia for an RBMK type reactor.In Ukraine, the authorities decided in 2003 to commission the two VVER-1000 reactors on the Khmelnitski and Rovno sites(K2-R4) the following year. Their construction had been interrupted during the 1990s. In the context of a European contractsigned by Riskaudit, subsidiary of IRSN and its German counterpart GRS, the two organisations presented the Ukrainian safetyauthority (SNRCU) in 2004 with a report on the safety of these reactors, allowing for modernisations carried out or planned.The Ukrainian operator then submitted, for approval, an improvement plan for the reactors taking into accountthe recommendations expressed. Reactors K2-R4 were placed in service in the second half of 2004. IRSN and its partners arecontinuing to provide SNRCU with technical support in the context of the technical appraisal of requests for authorisationregarding the implementation of modernisations planned after start-up of the two reactors.I R S N ANNUAL REPORT 2004151

CONTRACTUAL SERVICES OF EXPERT APPRAISAL,RESEARCH AND MEASUREMENTSERVICES NOT RELATED TO STATUTORYREQUIREMENTSRISKAUDITRISKAUDIT is a European groupof economic interest (EGEI)founded in 1992 by IPSN and GRSto coordinate joint internationalprojects. Since its founding,RISKAUDIT has managed morethan one hundred projects involvingits two parent establishmentsand other European and Americantechnical safety organisationsin the context of programmesto provide assistance to EasternEuropean countries in nuclearsafety, financed by the EuropeanCommission and EBRD.RISKAUDIT has its headquartersin Fontenay-aux-Roses(Hauts-de-Seine) and twopermanent offices in Moscow(Russia) and Kiev (Ukraine).Second edition of the annual seminar for cooperation on hazardousindustrial sites, on 23 March 2004 in Ville-d’Avray (France), attendedby about 100 key players: experts, industrial firms, nuclear operators,administrations, representatives of associations and professional societies,and members of Local Information Commissions (CLI).Depending on the state of progress of the projectsconcerned,assessments may be focused on definingsafety objectives or requirements, determiningweak points to be corrected,assessing improvementprogrammes,and analysing and evaluating detailedsolutions proposed by operators.This cooperation is mainly carried out in the contextof contracts managed by Riskaudit, a subsidiaryof IRSN and GRS, and financed by the EuropeanCommission (PHARE and TACIS programmes) orby the European Bank for Reconstruction andDevelopment (EBRD).In 2004, IRSN contributed to some 30 projects,mainly in Bulgaria, Lithuania, Russia and Ukraine.Cooperation in this part of the world is seeing newdevelopments with the setting up in Russia and,in the near future,in Ukraine of the “Global partnershipagainst the spread of weapons and materialsof mass destruction”adopted by G8 in 2002.In thiscontext,IRSN took part,in 2004,in the preparationof a number of projects regarding nuclear safety,radioactive source management and physicalprotection of installations and nuclear materials.LithuaniaBelarusRussian FederationCzech Rep.SlovakiaHungaryBulgariaUkraineArmeniaKazakhstanRISKAUDIT’s activities in Central and Eastern European countries.152I R S N ANNUAL REPORT 2004

Designers, manufacturersOperatorsIRSN,R&D on risksIRSN,public expertisePublicauthoritiesParliamentBuildthe relationshipInterested parties(CLI)Civilian societyThe reform of 2002 incorporates safety andradiation protection, separates the functionsof technical policy, study and R&D policy,and operators’ policies.Expertiseand assistancefor civilian societyIRSN embarked upon an approach toinvolve the interested parties that wasconsistent with the guideline adoptedby the government for greater transparencyin the field of nuclear and radiologicalrisk management.The opening up of IRSN’s expertise to civilian societyinvolves,in particular,pilot actions which may leadto the setting up of groups with pluralist expertise,similar to GRNC, in order to deal with complex ordisputed topics. This undertaking also requires participationin national and international networks forinformation, promotion and feedback as well asthe creation of such networks.In order to make headway in this matter, theInstitute organised a second seminar on concertedaction, in March 2004, around the industrial sitesof Ville-d’Avray (Hauts-de-Seine). About onehundred participants (associations, experts,representatives of administrations and nuclear andchemical industries) were able to exchange viewson this occasion with the prospect of a change inthe governance of industrial activities.Furthermore,in the context of their protocol,IRSNand the French national association for localinformation commissions (ANCLI) organised ameeting, on 24 March, to define actual concreteactions.The topics cover, in particular, monitoringof the environment and releases. A survey targetingthree CLI had already ascertained their expectationsin these fields.Acadie, a joint assessment toolIn 1997, the French Ministries of the Environmentand Health entrusted Mrs Sugier with the missionof forming a pluralist group in order to assessthe leukaemia risks which could result fromexposure of the inhabitants of the Nord-Cotentinarea to ionising radiation. The study, conductedby the Nord-Cotentin Radioecology Group, GRNC,led to the design of a calculation tool whichincluded, in particular, a database containingthe parameters of transfer to the environment.Development of this tool continued until,in June 2004, the Acadie software was unveiled.This application for the calculation of internaland external effective doses allows GRNC members(associations, foreign experts, institutions,industrial firms and operators, etc.) to performtheir own dose calculations and to share dataon the assessment of the radiological impact.Furthermore,at the initiative of IRSN,a round tableto discuss the subject of transparency attractedexperts in public debate, CLI members, journalistsand associations.It revealed high expectations withregard to IRSN as a public expertise organisation.1999 2003Publication of resultsand circulation ofthe calculation programto GRNC membersMore than 1 gigabyteof files, utilisationrequiring programmingknowledgeUtilisation byall GRNC membersnot possibleSetting up of anIRSN/COGEMA working groupObjective :Assure the future of the GRNCcalculation programASN, Nuclear safety authorityNew COGEMA order ondischarges stipulating, inArticle 32, that:"The estimation of doses […]is subject to evaluation bythe Nord-Cotentinradioecological group (GRNC)whose opinion is made publicand presented to CSPI."2004Drawing upan effective dosecalculation programthat is easy to use andaccessible to all GRNCmembersManufacture of a dose assessment tool accessible to interested parties.I R S N ANNUAL REPORT 2004153

1crisis exerciserelated tothe securityof installations3crisis exercisesrelated to the safetyof Defence-relatedinstallations198inspectionsrelated to the controlof nuclear materials32support missionscarried out byinternational inspectorsto check nuclear andsensitive materials103technical noticesrelated to the safetyof Defence-relatedinstallations andactivities9meetings of safetycommissions and smallgroups of experts54participationsin national andinternationalworking groupsAerial view of the Charles-de-Gaulle aircraft carrier.154I R S N ANNUAL REPORT 2004

IRSN ACTIVITIES IN 2004Defence nuclearexpertiseIn accordance with the decree relating to IRSN dated 22 February 2002,the Assistant Director General in charge of implementing the Institute’s Defencerelatedmissions, has a specific department, the DEND, which conducts expertappraisals, tests, studies and research related to:the protection and control of nuclear and sensitive materials;the protection of nuclear installations and transportations of radioactivematerials against malicious acts;the safety and radiation protection of Defence-related installations and activities.> 156 Assessing the safety of military nuclear systems,basic nuclear installations and Defence-relatedtransportations> 159 Protection and control of nuclear and sensitive materials> 164 Protecting installations from malicious acts> 166 Managing emergencies caused by malicious actsI R S N ANNUAL REPORT 2004155

DEFENCE NUCLEAR EXPERTISEASSESSING THE SAFETY OF MILITARY NUCLEARSYSTEMS, BASIC NUCLEAR INSTALLATIONSAND DEFENCE-RELATED TRANSPORTATIONSAerial view of the Marcoule site (Gard).Assessing the safety of military nuclearsystems, basic nuclear installationsand Defence-related transportationsTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKOPERATIONAL SUPPORT IN THEEVENT OF A CRISIS ORRADIOLOGICAL EMERGENCYIn 2004, IRSN examined the safety ofinstallations, laboratories and plantsinvolved in National Defence on thebasis of the dossiers transmitted bythe operators concerned, and gave itsrecommendations to the DSND.Activities concerning Defencerelatedlaboratories and plantsIn 2004, IRSN examined the safety of installationsoperated by CEA’s Military Applications Division(CEA/DAM) or by COGEMA. These two operatorsconduct all the operations (production, storage,processing) necessary for the supply of nuclearmaterials for weapons and the manufacture offuel for nuclear propulsion reactors. They are alsoin charge of cleaning up production installationswhich have now been shut down.The risks presentedby these installations are very varied, dependingon the missions assigned to each installation.Different specialists from different IRSN units havetaken part in expert appraisals in fields as variedas civil engineering or risk prevention related tocriticality, fire, exposure to ionising radiation andthe dispersal of radioactive material.For the COGEMA establishment in Marcoule (Gard)and the installations on this site, the Institutetransmitted recommendations to the DSND on thefollowing:■ the implementation of an internal authorisationprocess;■ an authorisation request for releases and watersampling;■ the revision of the operating authorisation forthe conventional waste recycling plant;■ receiving and processing incinerable waste fromdifferent sources.The Institute also monitored operations carriedout in the framework of the definitive shutdownof the UP1 plant. IRSN transmitted recommendationsto DSND on the following:■ cleaning-up of the stores;■ storing of waste created by the definitive shutdownoperations;■ risks associated with cutting operations,includinghot spots;■ work done on an evaporator in the UP1 plant;■ updating of the general operation rules;■ operations to clean up the dissolvers.IRSN monitored the COGEMA establishment inPierrelatte (Drôme) and the installations on this site.Within this framework,IRSN transmitted recommendationson the following:■ introduction of a production line within the recyclingand elaboration plant (URE);■ flooding that occurred in the Rhône valley inDecember 2003;■ commissioning of the processing and salvagingworkshop after improvement works were carried out;■ dismantling operations on annexes of gaseousdiffusion plants (GDP).156I R S N ANNUAL REPORT 2004

Le Vigilant, a French nuclear-powered ballistic missile submarine (SNLE).Activities concerning navalpropulsion reactorsIn 2004,IRSN gave its opinion on the modificationsthat the Navy plans to make to basin 8 at Brest’snaval dockyard,with a view to increasing the dockingcapacity for SNLE such as Le Triomphant.TheInstitute also analysed the radiological surveillanceprogramme drawn up in anticipation of the stopover by Charles-de-Gaulle, the aircraft carrier, inthe port of Le Havre.In 2004, IRSN followed the design process of thenext generation of French nuclear attack submarines(see Focus p. 157) and assessed the latest safetydossiers on Le Vigilant, allowing DSND to issuefavourable recommendations on the final operatingpermit.IRSN examined the safety of the test reactor(RES) in 2004.This installation, located within thearea of the secret basic nuclear installation (INBS)“Nuclear Propulsion”at the CEA centre in Cadarache(Bouches-du-Rhône), will replace the RNG installationcurrently operating.The RES installation is made up of a “pit” part anda “reactor” part, under construction.The “pit” partneeded for reactor operations is already built. Itcan be used to store fuel and other naval propulsionboiler equipment.At the end of 2003, CEA requested a temporaryModel of the reactor test installation underconstruction in Cadarache (Bouches-du-Rhône).permit to use the pit part of the RES installation.To this end,it transmitted a provisional safety reportand general operating rules.In 2004,IRSN examinedhow the civil engineering works behave when subjectedto the different possible stresses.The evaluationsalso concerned:■ the inherent risks at the “reactor” constructionsite (fall of crane, etc.);■ criticality risks associated with the storage of fissilematerials in the different channels of the pit;■ the risk of the fuel dewatering;■ the risks associated with dynamic containmentloss;■ the risk of fire.In addition,IRSN examined the radiation protectionmeasures taken by the operator.The operator tookBARRACUDA PROGRAMMEFOCUSSince 2001, IRSN has supported the control exertedby the DSND on the development of the BARRACUDAprogramme, the next generation of French nuclearattack submarines.Even before the examination of the preliminary safety report scheduledfor 2005, IRSN studied several important safety aspects in 2004 –the architecture of security systems and the risks associated withthe presence of conventional weapons on board a ship, for example.The security systems are designed to bring the nuclear reactor backsafely and maintain it in safe conditions in the event of an accident.To ensure this, IRSN checks that the architecture of these systemsand the design of their components can guarantee a level ofreliability equal to the safety objectives assigned to submarines likeBarracuda. These objectives take into account the fact that thesubmarines will be docked and maintained at the French Navy’snaval bases located in urbanised areas.The DGA made suggestions for procedures and IRSN assessed themand passed them on to the DSND.I R S N ANNUAL REPORT 2004157

DEFENCE NUCLEAR EXPERTISEASSESSING THE SAFETY OF MILITARY NUCLEARSYSTEMS, BASIC NUCLEAR INSTALLATIONSAND DEFENCE-RELATED TRANSPORTATIONSA working meeting for defence nuclear expertise teams.great advantage of the experience acquired in similarstorage installations (EDF spent-fuel pits, port pits,etc.) to optimise the doses used.As the monitoring of operations carried out in the“pit” part requires a lot of human intervention, IRSNexamined the measures taken by the operator regardingpossible human error during handling activities inparticular (ergonomics of bridge control boxes,trainingof agents, organisation of operations, etc.).IRSN’s assessment report was used as a supportdocument in the Reactor Safety Commission meetingon 9 and 10 November 2004 at Cadarache.Activities concerning radioactivesourcesAs part of the gradual implementation of the newregulations on radiation protection (decree No.2001-592 of 5 July 2001),IRSN listed about 10 installationsin 2004 whose radioactive sources now come underDSND control. This number should soon increasefollowing changes to regulations and the resultingtransfer of authority.This concerns installations whoseauthorisation was issued by the CIREA before 2002.For these installations, IRSN monitors movements ofsources by issuing the necessary forms and recordingthe movements in the national inventory of radioactivesources.PUI-related activitiesIn 2004,IRSN transmitted technical recommendationsconcerning the internal emergency plans (PUI). Itexamined:■ the PUI and the accident situations covered by thePUI at COGEMA’s establishment in Pierrelatte;■ INBS’s PUI called “ Basin 8 ” at Brest’s naval dockyard(Finistère).In addition,IRSN analysed the evolution of geo-mechanicalstability at the Mururoa and Fangataufa atolls. Thisexpert assessment particularly concerned the mechanismsresponsible for instabilities observed at theseatolls in the past, the pertinence of the monitoringsystem installed and also the evolution of rockmovements.Crisis exercises involving INBSsand SNMsIRSN took part in three national crisis exercises relatedto “Defence”in 2004. In addition to the main exerciseof the year,which took place in November at COGEMA’sPierrelatte site (see Focus p.133), two exercises werecarried out at Mont-de-Marsan’s air base (Landes) andToulon’s naval base (Var):■ the first simulation involved a weapon in a fire. Ittested relations between the technical units of IRSNand those of the air force;■ the second one concerned a nuclear attack submarine(SNA). Prior to this exercise, work had been carriedout to adapt the CTC organisation and develop specificdocumentation. This work was carried out in closecollaboration with naval staff from the French Navy.158I R S N ANNUAL REPORT 2004

Determining the isotopic compositionof plutonium.Protection and control of nuclearand sensitive materialsThere are several aspects to theprotection and control of nuclear andsensitive materials:physically protecting,monitoring and accounting fornuclear materials, tracking transportationsand applying internationalcontrols on the non-proliferation ofchemical and nuclear weapons.Physical protection of nuclearmaterialsThe physical protection of nuclear materials isensured by a series of material and organisationalmeasures designed to guarantee an in-depthdefence that is appropriate to the risk of theft ordiversion of these materials.These measures includedelaying systems,detecting systems,access controlsystems and response resources.Public authorities, under the responsibility of theMinistry of Industry (HFD), define the requiredobjectives as regards physical protection and verifythat the measures implemented by nuclearoperators and possessors of nuclear materials ensurecompliance with these objectives.IRSN places its technical expertise at the disposalof public authorities to assess the efficiency ofphysical protection measures adopted or proposedby operators and possessors.In this matter,IRSN’s expertise specifically concerns:■ the capacity of installations or equipment toresist theft or diversion of materials;■ the pertinence of procedures for access to nuclearmaterials and the removal of these materials fromtheir containments or from establishments thatpossess them;■ the capacity of systems to detect the loss or theftof nuclear materials.In 2004, IRSN analysed about 80 dossiers sent byoperators and possessors of nuclear materials.In addition, IRSN personnel carry out inspectionsfor the HFD in installations possessing nuclearmaterials.The aim of these inspections is to checkin situ the implementation and operational natureof the measures to protect and control nuclearmaterials and the measures to protect them frommalicious intent (application of articles L.1333 andL.1332 of the Defence Code, respectively). About50 inspections were carried out in 2004. For someof them, the Institute took in situ measurementsof the protection systems’physical characteristics.At international level,in 2004,the Institute directedan IPPAS mission organised by IAEA in Iran. IRSNwas also involved in teaching at internationalcourses on design basis threats in Iran and physicalprotection of research reactors in the Republic ofSouth Africa.Moreover, in cooperation with the United StatesDepartment of Energy (US DOE), IRSN developedan assessment method and training course oninternal threats. The aim of this initiative is tosuggest to the IAEA that a document based on thismethod be published in the “Tecdoc” section withthe associated training course.Monitoring and accountingfor materialsAt the request of HFD,IRSN examines the measurestaken by operators to monitor and account fornuclear material held in installations. It proposesany corrective action it deems necessary,especiallyTECHNICAL SUPPORT WITH REGARD TONUCLEAR AND RADIOLOGICAL RISKI R S N ANNUAL REPORT 2004159

DEFENCE NUCLEAR EXPERTISEPROTECTION AND CONTROL OF NUCLEARAND SENSITIVE MATERIALSMarking of nuclear material packages.regarding the risk of theft, loss or diversion ofsuch materials.IRSN then checks that the operatorstake HFD’s requirements into account and reportsback to HFD.In this respect, the Institute analyses the reportsrequired by regulations and carries out technicalinspections of installations.In particular,it examines the measures implementedby operators to:■ have precise, quantitative and qualitativeinformation on all the nuclear materials that enterand leave the installations;■ track the materials, i.e., always know where theyare located, what they are used for and the operationsthey undergo (movements, transformations,etc.);■ check that the actual stock of materials heldcorresponds to the accounting figures they areobliged to keep updated.In 2004, IRSN analysed about 140 dossiers transmittedby operators within this framework.About30 technical meetings were required to carry outthese analyses. In addition, IRSN produced nearly100 analyses of nuclear material inventory reports.In addition, IRSN personnel carry out inspectionsfor the HFD in installations possessing nuclearmaterials.The aim of these inspections is to ascertainthat regulations applying to the possession of theseIMPACT OF THE NEW EURATOM REGULATION ON NATIONAL CONTROLFOCUSIRSN is responsible for updating the accounting declaration rules on nuclear materials accordingto the requirements of authorities and industrial firms, so that the former can fulfil their role ascontrollers and the latter can comply with their statutory obligations.A specific feature in France is the strong link between the accounting required by the law of July 1980 and that required byEuropean regulations.In 2004, IRSN studied the impact of the latter on the 85,000 annual accounting declarations. IRSN is to study changes thatshould be made to declaration rules because firstly modifications have been made to the information required and declarationmethods, and secondly the control of waste processing facilities has been handed over to EURATOM.The preliminary study underway aims to assess the impact on IRSN’s work load, the modifications that need to be madeto the information system used for national accounting of nuclear materials, and the definition of a new interface withoperators’ information systems.The results of the study will be discussed with the authorities and industrial firms in 2005, so as to come to a precisedefinition of statutory and operational changes. 2006 will be devoted to carrying out these changes, which will includea renovation of national accounting support documents. All this, associated with reinforced training, should be operational forall French nuclear operators at the beginning of 2008.One of the difficulties will be ensuring compatibility between the computer application of national accounting andthe operators’ computer applications, while at the same time coordinating the production start of the different computing tools.160I R S N ANNUAL REPORT 2004

Preparing an irradiated fuel transport convoyin Cherbourg (Manche).materials are respected.For the record,regulationsdistinguish between installations subject to a priorauthorisation and installations subject to a priordeclaration,depending on the nature and quantityof materials possessed.In 2004,IRSN carried out more than 70 inspectionsat installations subject to a prior authorisation,several of which involved physical measurementsto test materials. In addition, the Institute carriedout about 20 technical inspections of installationssubject to a prior declaration.As well as this ongoing activity, IRSN took moretargeted action regarding certain installations,afteranomalies or malfunctions were discovered. Themost notable example is the discovery, in 2004, ofnearly 400 kg of depleted uranium that were notaccounted for in the records. It was found on thesite of a company specialised in metal recovery.Transporting nuclear materialIRSN manages transportation dossiers and tracksthe transportation of nuclear materials on behalfof HFD. Current regulations oblige transportcompanies that have received prior ministerialauthorisation to abide by measures relating to theorganisation of movements and their declaration.Within IRSN,it is the Operational transport section(EOT) that performs this mission. Its scope ofcompetence includes the transportation of nuclearmaterials via road, rail, river, sea or air. Thesetransportations must be declared to EOT fifteen daysbefore the planned date of transport. Thus, about1,700 trans-portations are declared to EOT everyyear. On receipt of the transportation notice, thefollowing checks are carried out:■ the dates and times;■ the appropriateness of the physical protectionin relation to the material being transported;■ the validity of authorisations held by transportersand any of their subcontractors, who also have tobe approved by the Ministry;■ the route taken;■ the members of the team;■ the means of transport, which must also haveobtained ministerial approval according to the natureand quantity of nuclear materials transported.When the transportation is confirmed, EOT givesits consent for the movement of materials andinforms all the authorities and organisationsconcerned (Ministry of Industry [HFD], Ministryof the Interior [including DDSC],Ministry of Finance[customs]). EOT is also responsible for the smoothrunning of very sensitive transpor-tations,to ensurethat nuclear materials are cons-tantly protectedand controlled in an appropriate manner.In 2004, EOT monitored a special internationaltransportation: the transportation of militaryplutonium between the United States and France(EUROFAB operation). On this occasion, EOTprepared the dossiers on the transport equipmentauthorisations and approvals,on the transportationplan approval and on the real-time monitoring ofmovement throughout French territory, includingterritorial waters.International controlson non-proliferationInternational treaties, to fight proliferation or forbidnuclear and chemical weapons of massdestruction, implement supranational systems ofcontrol. In France, IRSN provides assistance andtechnical support to authorities in charge ofI R S N ANNUAL REPORT 2004161

DEFENCE NUCLEAR EXPERTISEPROTECTION AND CONTROL OF NUCLEARAND SENSITIVE MATERIALSChecking nuclear material transport packages.monitoring these inspections.The inspection systems implemented by the Treatyof Non-Proliferation, the Treaty of Rome and theChemical Weapons Convention may be different,but they all involve international officers checking,in declared facilities, the information transmittedby States to international inspection bodies (IAEA,Euratom, OPCW).Within this framework, IRSN acts on behalf ofFrench authorities, collecting and preparing theFrench declarations to inspection bodies.It is also in charge of ensuring the smooth runningof international inspections in French nuclear orchemical facilities.To this end,it prepares the inspections,accompaniesthem (as representative of Frenchauthorities) and negotiates the practical aspects ofthe inspection with the inspection team.As part of the technical support it provides Frenchpublic authorities,IRSN carries out a prior analysisof the technical documentation that sites send tothe inspection bodies. IRSN also assists Frenchauthorities by analysing and keeping up withchanges to national or international regulationsrelating to the fight against proliferation. Whennecessary,it takes part in interministerial work andjoins groups of international experts set up by theOPCW or IAEA.In 2004, IRSN prepared and transmitted to theOPCW:■ the annual declaration on the activities of chemicalsites listed in France in 2003 (over 130);■ the annual declaration on the planned activitiesof chemical sites listed in France in 2005.It processed and sent to the European Commission:■ 610,000 lines declaring movements and stocksof nuclear materials;■ 260 notifications on the import or export ofnuclear materials;■ the programme of activities for the 220 declaredFrench nuclear facilities;■ the list of about 250 French possessors of smallquantities of nuclear materials (plus the value oftheir stocks).It prepared and sent to the IAEA:■ the monthly and six-monthly accounting reportson stocks of nuclear material in France subject tosafeguard agreement measures;■ the monthly and six-monthly accounting reportson the international transfers of crude materialsand ores;■ 500 notifications on the import or export ofnuclear materials;■ France’s initial declaration for the application ofthe additional protocol (see Focus p.163);■ France’s quarterly declarations on the export ofnuclear equipment.IRSN accompanied OPCW’s seven inspections ofFrench,civil,chemical facilities.It also accompaniedverifications carried out on the inventory of nuclearmaterials in 27 French facilities.It took part in opening discussions between theEuropean Commission and French authoritiesconcerning the definition of international proceduresfor inspecting new facilities.As far as regulations are concerned, 2004 saw thearrival of one decree and three amending orders162I R S N ANNUAL REPORT 2004

Manipulation in the Euratom laboratoryat the La Hague plant (Manche).for the application of the Chemical WeaponsConvention.During the same period,draft legislationon the application of the additional French protocolwas transmitted to the Council of State.ADDITIONAL PROTOCOLFOCUSSince 30 April 2004, the effective date of the additionalprotocol to IAEA’s safeguard agreements coveringall the European Union, the control of nuclear materials,initially provided for in the Treaty on the Non-Proliferation of NuclearWeapons of 1970 and the safeguard agreements that followed, hasbeen extended to include research and development and nuclear facilityequipment.The secretariat of the Interministerial Technical Committee has beenput in charge of implementing the additional protocol in France withtechnical support from a specialised IRSN department.In 2004, IRSN put together a declaration manual which was sentto a selection of 1,700 bodies at the beginning of May.Industrial firms and research centres working on various subjectsrelated to the nuclear fuel cycle were contacted but so wereboilermakers, pump and tube manufacturers, etc.At the same time, IRSN provided telephone assistance to industrial firmson a dedicated line.In September, the French declaration was drawn up on the basisof declarations made by the French bodies concerned. This involved agreat deal of compilation work. The declaration was sent to the IAEAon 28 October 2004 within the set deadline, i.e. 180 days from theeffective date of the protocol. For future declarations, IRSN willregularly contact about 150 entities.Recording of operators’ declarationsin accordance with the supplementary protocol.I R S N ANNUAL REPORT 2004163

DEFENCE NUCLEAR EXPERTISEPROTECTING INSTALLATIONSFROM MALICIOUS ACTSNuclear power plant at Dampierre-en-Burly (Loiret).Protecting installationsfrom malicious actsTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKDEFINING AND IMPLEMENTINGNATIONAL AND INTERNATIONALRESEARCH PROGRAMMESAs far as security is concerned, thegeneral context has changed and thishas led the HFD to seek possibleimprovements to regulations relatedto the protection of nuclear installationsfrom malicious acts,given the reassessmentof threats associated with suchacts.Improving regulationsWithin this context, IRSN was associated in thedefinition of a new set of reference threats in 2004.These reference threats specify the characteristicsand resources attributed to aggressors and are usedto size the physical protection systems of nuclearfacilities and check that they are appropriate.TheInstitute also suggested that these regulationsshould include provisions on the protection ofnuclear materials with regard the risks of loss,theftor diversion and provisions on the protection ofnuclear facilities and materials from malicious acts.The aim is to produce a set of coherent protectivemeasures based on a global conception of protectionsystems.IRSN was keen to specify:■ the respective missions and responsibilities ofpublic authorities and operators;■ the protection objectives that operators shouldrespect;■ the general principles to apply when designingand using physical protection systems (defence indepth, material measures, security guards andorganisational measures);■ the nature of the installation areas to be protected,with the associated protection instructions;■ how to manage requirements that could turn outto be contradictory in terms of nuclear safety andphysical protection of installations;■ the approval process of statutory dossiers requiredfrom operators;■ the method and content of protection studies(relating to malicious acts) and security studies(relating to theft of nuclear materials).To be specific,protection studies should be based on a sensitivitystudy aimed at assessing the radiological consequencesof a malicious act and also on a vulnerabilitystudy that assesses how difficult it would be to carryout such an act;■ the scheduled review process that should beimplemented to ensure that the protection systemis appropriate;■ the declaration process for events related tomalicious acts;■ the control and inspection process.Studying and developing assessmenttoolsIn 2004, IRSN continued working on the structuralresistance to malicious acts programme. It aimsto assemble tools that can predict the damage thatweapons or explosives can cause to structuresand equipment.These tools are used when analysingthe dossiers sent in by operators.164I R S N ANNUAL REPORT 2004

Physical protection.There are two stages to this work:■ listing all the possible “targets”and the destructivemeans involved in the reference threats;■ classifying the “targets” and destructive meansinto categories which,once grouped together,defineall the generic cases that have to be dealt with.A matrix of cases is thus produced, made up of“weapon/target” pairs. To give a few examples,reinforced concrete structures, tanks, piping andsome mechanical systems that act as safety devicesare considered as targets.in the far field or the specific approach for loadingin close field;■ numerical models from mechanics calculationcodes. The studies carried out using mechanicscalculation codes are complementary to thoseconducted via analytical methods: numericalsimulation provides more accurate results, makesit possible to introduce more complex and morerealistic models and to determine the evolutionof local parameters.Two categories of tools have been developed:■ simplified tools that are quick to use, based onanalytical methods. Analytical methods are usedto develop numerical simulation tools requiringonly limited resources. The main advantage isthat they are quick to use and this makes it possibleto carry out parametric studies. These methodsusually allow us to correctly determine themagnitude of the stresses we want to study. Forexample, they are used to study how reinforcedconcrete walls react to the blast of an explosionStudying and developing assessment tools for the physicalprotection of installations.I R S N ANNUAL REPORT 2004165

DEFENCE NUCLEAR EXPERTISEMANAGING EMERGENCIES CAUSEDBY MALICIOUS ACTSDefence crisis exercise at a military base.Managing emergencies causedby malicious actsTECHNICAL SUPPORT WITH REGARDTO NUCLEAR AND RADIOLOGICAL RISKExercises relating to the applicationof the July 1980 lawAt the request of HFD,IRSN organises exercises relatedto installation protection. They aim to test thedecision-making process and the coordination andinterfaces between the parties involved (operators,public authorities).Therefore, in 2004, the Institute:■ started to prepare and organise a large-scale exercisethat will take place in 2005;■ examined the lessons to be learnt from a similarexercise held in 2003.IRSN is also in charge of managing crisis situationsrelating to nuclear materials. It organises nuclearmaterial inventory exercises during crisis situationswith a view to testing the effectiveness of the systemset up for this purpose. In 2004, an exercise wasconducted at the CERCA facility in Romans (Isère) andthe ORPHEE facility in Saclay (Essonne) (see Focusp. 167).Defence crisis exercise at a military base.166I R S N ANNUAL REPORT 2004

Nuclear materials inventory crisis cell.CRISIS EXERCISE INVOLVING THE INVENTORYOF NUCLEAR MATERIALSFOCUSThe aim of the exercise is to carry out an unexpected test to check theability of one or more installations to detect the disappearance of nuclearmaterials and thus find out whether the disappearance of the materialscould escape the attention of the operator of the installation in question.To do this, operators have a very short time to carry out an inventory targeted at the typesof materials suspected of being diverted or stolen.Several crisis units are implemented for this purpose:■ at IRSN, a unit grouping together the business managers of the installations concerned anddifferent experts in charge of monitoring, accounting, transporting and ensuring the physicalprotection of the nuclear materials. It reports to the HFD on the evolution of the situation andthe initiatives it takes,■ at the head offices of the operating companies concerned and at the installations, units decideon the action to take and follow the progress of operations. They report on the progress ofverifications to HFD and IRSN.These units communicate with the media in their area of expertise, within the frameworkof simulated media pressure.Operators take the required measures until an accurate view of the situation is obtained.Encrypted networks are used between the different units to exchange classified informationif necessary (isotopic quantity or composition of sensitive nuclear materials for example).The lessons learnt from these exercises enable us to improve the systems that wouldbe implemented in the event of a real crisis (written procedures, means of communication, etc.).The exercise conducted in 2004 enabled us to find a means of improving the identificationof material on one of the sites.I R S N ANNUAL REPORT 2004167

3 and SupportManagement168I R S N ANNUAL REPORT 2004

Management and supportResearchfor understandingI R S N ANNUAL REPORT 2004169

164press requestsprocessed100men/yearin terms of time spenton internationalactivities64people from IRSNparticipated ininternational expertgroups68%of IRSN personnel areengineers, researchersor managerial staff32%of IRSN personnelare technicians oremployees providingtechnical andadministrative support77%of staffare employed by IRSN and23%were seconded from CEAat the end of 2004106people were hiredin 20043,218hours of teaching/trainingwere given1,150,000euros were spent on training126trainees were receivedby IRSN in 2004170I R S N ANNUAL REPORT 2004

MANAGEMENTAND SUPPORTScientific and technicalexcellence> 172 Scientific and technical excellence> 175 Scientific and technical knowledge engineering> 176 Security> 178 Quality: IRSN’s certification projectI R S N ANNUAL REPORT 2004171

SCIENTIFIC AND TECHNICAL EXCELLENCESCIENTIFIC AND TECHNICAL EXCELLENCEMeeting of the central echelon of the department of scientific and technicalexcellence and quality.Scientific and technical excellenceCompetence plays an important rolein ensuring the credibility of theInstitute’s work and earning the trustof its partners,customers and society.This competence lies in the scientificand technical excellence of its teamsand its research and expertiseactivities.Seminar on scientific and technicalexcellenceTherefore,with this in mind,IRSN decided to clarifyits policy and orientations. So on 16 March 2004,IRSN organised a seminar on the scientific andtechnical excellence of its activities in Le Vésinet.After this seminar, the Institute’s orientationsregarding the implementation of a policy ofscientific and technical excellence at IRSN wereformalised. This policy is based on the followingthree objectives:■ promoting scientific and technical excellencewithin the Institute;A PhD student in the radioecology lab using a binocularmicroscope to select larvae.■ implementing an internal system to assess thescientific and technical excellence of the Institute’sactivities;■ developing activities that contribute to IRSN’soutreach. It was presented to the Scientific Boardon 15 November 2004 and to the Board of Directorson 28 January 2005.Debates at the seminar highlighted the advantagesof setting up a committee on scientific excellencethat would coordinate and monitor the progressof action taken to achieve and obtain recognitionof scientific and technical excellence.Launching of targeted scientific andtechnical assessments – a pilot projectTargeted assessments can concern all the Institute’sscientific or technical activities (services, expertappraisals, research, studies). They are conductedby independent experts who have not been involvedin the activity in question and who are from outsidethe Institute if possible.To establish the type of questions to be asked andthe practical details of these assessments inconsultation with the teams concerned,it has beendecided to conduct a certain number of pilotoperations. These assessments concern:■ the results of a research programme;■ a scientific collaboration;■ the reorientation of a research programme;■ an expert appraisal of safety;■ a team.These assessments are in progress and shouldgradually lead to a convergence of ideas on thegeneric aspects of the assessment process,despitethe diversity of subjects and teams concerned172I R S N ANNUAL REPORT 2004

Training throughresearchEvery year, IRSN receives about20 doctorands (18 in 2004) and15 post-doctorand traineeswho contribute to relationswith the academic world.Therefore, most ofthe advisors for theseundertaken at IRSN areresearchers from outsidethe Institute.IRSN wishes to reinforce itstraining through researchinitiative, so in 2004 it startedto draw up a plan aimed atincreasing the number of newtheses to 30 per year andthe number of post-doctorandplacements to 30 per year.At the same time, the Instituteencourages its researchers tosupport the authorisation tosupervise research (ASR), thusshowing its willingness to openup to the world of universityresearch.(phasing of assessments,support documents,natureof questioning, etc.).Establishing indicators for an overallscientific and technical assessmentScientific and technical assessment with theestablishment of indicators is another approach –these indicators must be in-house tools for attainingimprovement objectives. They should be used toposition the Institute in relation to the outsideworld. They should finally contribute to therecognition of the scientific and technical qualityof its production.Links are being initiated with the Observatoiredes sciences et des techniques. The aim is to enterinto the circle of research organisations currentlyDiscussion between a PhD student and his tutor inthe Cadarache radioecology and ecotoxicologylaboratory (Bouches-du-Rhône).trying to standardise indicators to make them ascomparable as possible.Implementing action to promotecross-unit scientific awarenessIn-house scientific and technical awareness actionsare gradually being organised in order to shareknowledge and better identify, coordinate anduse the cross-departmental action of the operationalunits.In 2004, two subjects were defined for which thereis a need of experience exchange within the Institute:the use of MONTE-CARLO codes and the use ofexperimental designs. In 2004, a state of the artwas conducted on the MONTE-CARLO codes.Draft version of a scientific andtechnical excellence programmeThe aim of implementing such programme is toensure a better understanding, transparency andrecognition of the Institute’s activities, thusspecifically contributing to the promotion ofscientific and technical excellence,to its implementationand its recognition by the outside world:■ training through research and teaching;■ scientific activities;■ scientific and technical assessment;■ outside recognition;■ exploratory research.This programme is also a management tool,allowingus to set objectives when strategic orientationshave to be developed, to monitor the progress ofthe action taken to achieve these objectives or tosuggest changes.I R S N ANNUAL REPORT 2004173

SCIENTIFIC AND TECHNICAL EXCELLENCESCIENTIFIC AND TECHNICAL EXCELLENCESecretaries from DESTQ (Department for Scientific and TechnicalEvaluation and Quality) at the reception desk of the seminar on scientificand technical excellence on 16 March 2004.Relations with universities andscientific organisationsThese are essential for a research body like IRSN.Although the Institute is orientated towardsacquiring knowledge related to its expertise,outsideexperts should be allowed to give their opinion onthis research, to analyse it, evaluate it and enrichit with new ideas. Given the very wide scope of itsmissions, the Institute should call upon outsideskills to complement its own skills. Formingrelationships with universities is a good way ofdeveloping and improving the skills that are usefuland essential to IRSN.Through these relationships,IRSN experts can take part in the training given atthese universities and Grandes écoles and in thisway enable the Institute to acquire a reputation,attract young people and fulfil its training mission.When studies are carried out jointly with Universities,Grandes écoles and CNRS laboratories,cooperation agreements concerning the jointresearch and the hosting of trainees are signed. In2004, cooperation agreements were signed withvarious universities (see box).Within the frameworkof the national cooperation agreement with theCNRS signed in 2003, eight specific agreementson various subjects were signed with different CNRSlaboratories: “comparison of numerical modelsfor calculating percolation through dykes”,“modellingof geo-chemical perturbations in the near field ofwaste stored in a deep clay repository”, “paleoseismicityof Middle Durance fault in the regionof Manosque”, “characterisation of sources andprocesses at the origin of natural radioactive tracers(U 234 ,U 238 ,Ra 222 ) in a fractured environment”, etc.Agreements between IRSN and universities signed in 2004■ 6 January: agreement with the Institute of Nuclear Physics, Lyon, a CNRS / University of Lyon 1 joint research unit (UMR).■ 13 January: agreement with FAST, a CNRS / University of Paris 6 joint research unit (UMR).■ 19 January: agreement with the laboratory of fluid mechanics and acoustics, a CNRS / École centrale de Lyonjoint research unit (UMR).■ 28 January: agreement with the Toulouse Institute of Fluid Mechanics, a CNRS / INP Toulouse joint research unit (UMR).■ 28 January: framework agreement with the University of Pau.■ 18 March: agreement with Géosciences Rennes (UMR / CNRS).■ 30 March: agreement with the laboratory of hydrosystem ecology, (CNRS / University of Toulouse 3 UMR).■ 17 May: framework agreement with the ARMINES association.■ 17 May: agreement with CEREGE (CNRS / UMR).■ 4 August: agreement with the department of civil engineering and construction (CNRS / ENTPE UMR).■ 2 November: framework agreement with the University of Versailles - Saint-Quentin.■ 24 November: agreement with the laboratory of analysis, topology, probability (CNRS / University of Aix-Marseilles 1 UMR).174I R S N ANNUAL REPORT 2004

Library of the Scientific Information ResourcesCentre.Scientific and technicalknowledge engineeringActivities in scientific and technicalknowledge engineering (ICST) concerntwo main fields:scientific and technicalinformation (STI) and management ofIRSN’s archives. The purpose is tofacilitate and expand access to IRSN’sscientific and technical documentationthat engineers and researchers needto fulfil their missions.In 2004, several projects were launched to meetthese two objectives.The Centre for Scientific Information Resources (CRIS)completely reorganised its Intranet site to makeits range of services more accessible.A club for CRISusers was set up to improve these services. Therewere discussions on the possibility of extending accessto include electronic journals.The CRIS,in collaborationwith the club of users,chose an online bibliographicaldatabase. This tool completes the bibliographicaldatabases made available to IRSN personnel.The Archives project was also launched in 2004.Indeed, IRSN has kept the archives of the formerIPSN and OPRI.The project involves collecting the12 km of existing archives in order to present theFrench Department of Archives and CEA (of whichIPSN was a division) with a statement,and to providethe Institute with a tool that will allow the gradualintroduction of a sustainable archive managementorganisation. At the end of 2004, an inventory ofmore than 50% of the archives had been drawn up.Finally, IRSN set up an organisation allowing it todraw up annual reports on training through research,teaching and publications.These reports providedseveral of the figures presented in this report.I R S N ANNUAL REPORT 2004175

SCIENTIFIC AND TECHNICAL EXCELLENCESECURITYActive sample laboratory: radiological check to verify the non-contamination of afume chamber laboratory.Security200420032002IRSN security indicators4.352.9Industrial accident frequency rate*for IRSN employeesSeverity rate**0.030.03*Number of accidents with work stoppagemultiplied by one million and dividedby the number of hours worked.**Number of working days lost multipliedby 1,000 and divided by the numberof hours worked.00In terms of security,the action undertakenby IRSN in 2004 concern boththe security of facilities and the securityof personnel.Bringing the Institute’s facilities andactivities up to standard, IRSN conductsmost of its activities in facilities inherited from theformer OPRI and CEA, some of which require a lotof work to bring them up to technical and regulatorystandards. In order to define priorities, a majoraction plan was drawn up in 2004 concerningfacilities presenting a high level of risk and whichplay a strategic role in the Institute’s missions.Work started at the Le Vésinet site (Yvelines),with the renovation of electrical installations andthe ventilation of facilities for measuring environmentalradioactivity.Authorisations allowing laboratories to possessand use radioactive sources within the frameworkof the Institute’s research programmes were alsobrought up to standard. In 2004, 80% of theselaboratories (excluding activities conducted inauthorised ICPEs) obtained the necessary authorisationsfrom the DGSNR in accordance with thePublic Health Code. It should be noted that IRSNinherited more than 1,300 radioactive sources,including 900 that are unusable and for which adisposal provision was drawn up at the time of CEAand IPSN’s separation. In 2004, an agreement wassigned with all the source suppliers,mainly the CEA(80% of the sources requiring disposal), and thisallowed 20% to be eliminated.Staff trainingIn 2004, 764 employees followed a basic-securitytraining course, 450 of whom followed it becausethey were newcomers to the Institute.In addition to these general training courses,specifictraining courses are organised, mainly within theInstitute. In 2004, 93 employees were trained inradiation protection and 31 in the transportationof radioactive material.Radiation protection of workersThe Institute took several initiatives to implementthe decree of 31 March 2003 relating to labourprotection. For example, it appointed radiationprotection officers (RPO) for the sites in Le Vésinet,Agen (Lot-et-Garonne) and Les Angles (Vaucluse).Security at the sitesA local security team was set up at the Le Vésinetsite in 2004, which enabled us to make a precisediagnosis of risks and an assessment of the facilities’compliance with regulations.Preventive action wastargeted at outside companies working on thesite and at the reduction of fire risks.This involvedthe systematic implementation of prevention plansand security protocols during the loading andunloading of dangerous goods by outside companiesand the reduction of fire loads within the facilities.At Cadarache (Bouches-du-Rhône), operations atthe classified facility for environmental protection176I R S N ANNUAL REPORT 2004

The Institute’s regulatedfacilities and activitiesChecking the dose rate on a radioactive sample.were taken over by the Institute and new facilitiessubject to an authorisation (AMANDE and EPICUR)were commissioned.This led the Prefect to requestan in-depth revision of the 1986 bylaw whichapplied to the Institute. In 2004, the Inspectorateof listed facilities wrote the draft general requirementson the basis of the updated description ofthe activities and releases of IRSN’s facilities.Activities subject to the Code of the Environment(amended decree of 21 September 1977 relating toclassified installations for the protection ofthe environment (ICPE),■ ICPEs subject to an authorisation:- 11, 9 of which are covered by sections 1,700 (useor storage of radioactive substances).■ ICPEs commissioned:- CEZANE AMANDE, a facility that producesneutron radiation beams within the framework ofdosimetry programmes (Cadarache);- EPICUR, a cobalt-60 irradiator used to assessthe behaviour of iodine under radiolysis orradiation (Cadarache).■ ICPEs subject to declaration:- 15, 14 of which are covered by sections 1,700.■ ICPEs commissioned:- gammametric test bench to analyse rocks andstudy radionuclide transfer mechanisms in the soiland subsoil (Fontenay-aux-Roses, Hauts-de-Seine).Activities subject to the Code of Public Health(amended decree of 4 April 2002 relating tothe protection of persons from ionising radiation).Number of permit requests filed with the DGSNRin 2004: 19.Number of permits issued: 14 (5 are being examined).Personnel exposed to ionising radiation:■ category A: 114;■ category B: 678.I R S N ANNUAL REPORT 2004177

SCIENTIFIC AND TECHNICAL EXCELLENCEQUALITY2004 20052006PREPARATION• Improvement loop tools• Process definition• Organisation• Quality policy• TrainingBUILDINGTHE PROCESSES• Process managers• Objectives and indicators• Deployment ofimprovement loopOPTIMISINGQUALITY SYSTEM• Improvement plans• Dealing with differences• Internal auditsCERTIFICATIONSTATE OF THINGS• Self-evaluations• Management reviews• Improvement plansIMPROVING QUALITYSYSTEM IN FORCE• Improvement plans• Dealing with differences• Internal auditsMOCK AUDIT ANDCORRECTIONSSUBMITTINGCERTIFICATION DOSSIERBE AWARE OFTHE DIFFERENCE BETWEENTHE CURRENT QSAND THE TARGETED QSDEFINE IMPROVEMENT ACTIONSMIGRATE CURRENT QSTO THE TARGETED QSRUN THE IMPROVEMENTLOOP> CERTIFIABLE QSThe main stages of the certification project.Quality: IRSN’s Certification projectLaunched in the summer of 2003, theCertification project consists in implementinga management system basedon quality at IRSN with a view toobtaining ISO 9001 certification forthe Institute by 2006. In 2004, thefoundations of this project were laid.The main results of the work carried out withinthis framework in 2004 are:■ a detailed schedule of the project was drawn up,taking into account the tasks falling to the Institute’sdifferent quality managers and the tasks relatedto the deployment of the system in all the units;■ most of the unit heads and quality managersreceived training in the Process approach and therequirements of standard ISO 9001;■ efforts went into making personnel aware of theaction undertaken,i.e.,the quality Intranet site wasreorganised and several brochures were preparedpresenting the various aspects of this action tostaff;■ the three main aspects of the Institute’s qualitypolicy were explained: satisfying its partners andRENEWAL OF ACCREDITATIONS FOR THE SAMPLE ANALYSIS DEPARTMENTFOCUSThe IRSN department in charge of sample processing and metrology for the environment (STEME)obtained the renewal of its COFRAC accreditations until 2009, according to the baseline of standard NF ENISO 17025, for programmes 135 “Laboratory analysis of radionuclides present in all types of samples from the environment”,and 99/4 “Analysis of chemical contaminants in animals, in their products and the foodstuffs intended for humans andanimals: radionuclides”.COFRAC accreditation offers companies, consumers and public authorities a guarantee of confidence in the servicesprovided. As a signatory of the multilateral, European, mutual recognition agreement for tests, calibrations and certificationand equivalent international agreements, the COFRAC is also a passport to exportation.Preparing renewal audits involves putting together a large number of documents.Activities covered by accreditation include:■ the measurement of tritium in fresh water and sea water;■ the measurement of global beta radioactivity index (air-aerosol);■ the measurement of alpha 238 Pu, 239 + 240 Pu, 241 Am emitting radionuclides in water;■ the measurement of 14 C in solid samples;■ the measurement of gamma emitting radionuclides in fresh water, solid samples and aerosol sampling filters.Audits to monitor accreditation will be held in 2005 and the scope will be extended to include the measurement of uraniumin water.178I R S N ANNUAL REPORT 2004

AuditsIn 2004, 21 internal audits werecarried out at IRSN. Theseaudits were a continuation ofthe work that had been carriedout in previous years.Among these, we find twointer-relating audits: the one,preparatory to the auditcarried out in spring 2004 bythe IAEA on the French baselinefor the radioactive materialtransport safety, and the onefrom the Reactor section ofthe process Elaboration ofa notice for a standing advisorygroup. Moreover, to anticipatethe gradual increase inthe audit programme linked tothe Certification project,the team of auditors has beenconsiderably strengthened.AccreditationsandcertificationsThe IRSN currently has sixaccredited units (ISO 17025)and two certified units(ISO 9001 version 2000).In 2004, we saw the renewal ofaccreditations held bythe ionising radiationdosimetry laboratory (forthe calibration of measuringinstruments used in photondosimetry) and the departmentin charge of sample processingand metrology forthe environment(see Focus p.178).customers (internal and external), demonstrating theprofessional nature of its various activities and in somecases, the benefits to society of its activities;■ IRSN’s quality organisation was clarified.This is basedon the distinction between the line of action, composedof the chain of command in charge of defining and implementingthe system’s various measures (presenting thestate of things,defining objectives and indicators,drawingup action plans, implementing improvements, etc.) andthe network of different quality managers in charge ofcoordinating,developing and monitoring the system andproviding method support to the Institute’s differentunits;■ each unit, at various levels of hierarchy (Institute,management,department,etc.) drew up a quality inventorytaking stock of the existing situation and comparingit to the standard requirements. After the inventories,these same units held management reviews at whichaction plans appropriate for each unit were drawn up;■ on 27 September 2004, IRSN’s management reviewwas held and the Institute’s plan of action until the nextmanagement review was drawn up.I R S N ANNUAL REPORT 2004179

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MANAGEMENTAND SUPPORTCommunication> 182 CommunicationI R S N ANNUAL REPORT 2004181

COMMUNICATIONCOMMUNICATIONIRSN web portal.CommunicationIntranet portal.There are three main fields of communicationat IRSN:in-house communication,information to the public on nuclearand radiological risk and reputationbuildingand promotion of the Institute,a multi-skilled public expert.In-house communicationIt helps encourage a sense of belonging to IRSNby developing a shared culture.The main initiative of the year in the field of inhousecommunication is the creation of Repères IRSN,the quarterly 16-page house journal containing a4-page supplement for each operational department.This medium aims to inform people of allthe different jobs and activities at the Institute, tohelp them understand the new organisation andthe strategy of IRSN. Four issues were publishedand circulated betweenFebruary and December2004. A readershipsurvey was conductedand the conclusionswere quite positive:people read RepèresIRSN and look forwardto it. They appreciatethe content and theregularity of itspublication.As far as the Intranet isconcerned,efforts wereput into providing informationon daily life at the Institute and on moreregular updating, via more dynamic sections. Wewill continue our efforts to make the Intranet abetter organised and more widely used interactivetool.Finally, in 2004, the construction of the Institutealso led to the creation of its visual identity witha new logo: development of a graphic charter, aneditorial charter and the deployment of these toolsvia stationary,signposting,outfits worn by responsepersonnel,etc.In-house support on the use of thesecharters was given at the Institute’s different sites.InformationThe aim is to provide information of reference thatis explanatory, educational and documentary, andsuited to every audience. Relations with the pressalso have to be conducted by fulfilling their requirements.As far as informing the public is concerned, IRSNcontinued action with the general public andprofessionals in 2004 (see Part 2,Public informationchapter).As far as media relations are concerned,the Institutepromptly responded to press requests (164 requestsand six TV reports), gave its own news (15 pressreleases) and provided in-depth informationallowing a better understanding of events.As wellas the Institute’s real-time watch on the mediaand on public debate on nuclear matters, relationswith the media also included a meeting with the182I R S N ANNUAL REPORT 2004

IRSN’s house journal.AJE in 2004 and the organisation of two press trips:to Chernobyl (Ukraine) for the FGI closing conference(5 and 6 October),and to Cadarache (Bouches-du-Rhône),for the last test in the PHEBUS-FP programme(18 November).low level radioactive elements, etc.) and five cardson “training” (radon metrology in buildings, etc.)were distributed, especially during the shows andconferences the Institute attended.Reputation-building and promotionThis should help establish the reputation of theInstitute:■ as a scientific expert working for public authorities,operators and society in France and Europe;■ as an organisation that encourages exchangeswith civil society;■ as an expert that helps people understand nuclearand radiological risks.In 2004, the Institute’s reputation-building andpromotional action included the publication oftechnical data cards highlighting the services thatthe Institute provides,i.e.,10 data cards on “products”(radiotoxicological analyses, quantification ofPart of the communication team and the communicationmanagement network at IRSN.I R S N ANNUAL REPORT 2004183

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MANAGEMENTAND SUPPORTHuman resourcesand social relations> 186 Human resources and social relationsI R S N ANNUAL REPORT 2004185

HUMAN RESOURCES AND SOCIAL RELATIONSHUMAN RESOURCES AND SOCIAL RELATIONSWelcoming young people and PhD students.Human resourcesand social relationsMore than60 years50 to60 years40 to50 years36 to40 years31 to35 years25 to30 yearsLess than25 yearsPyramid of ages175 150 125 100 75 50 25MenWomenHuman resources: an active policy tosupport the development of IRSNSignificant initiatives were undertakenin terms of human resources managementin 2004. In line with the orientationsdefined by the Institute, theyare based on the key objective: usingcompetence as the basis of humanresources policy.Discussions were initiated andactions launchedIRSN’s management of human resources is in linewith the Institute’s global project.Within this framework,several schemes were launched in 2004:■ developing a line of Experts: IRSN wishes todevelop its employees’ career prospects and offernew and motivating careers through the creationof a line of Experts. Employees who distinguishthemselves through their recognised skills andnoteworthy productions will be appointed to theposition of Expert. Their position shall be definedthrough missions fully contributing to the accomplishmentof objectives set out in the Institute’sscientific and technical policy and its recognitionwithin the international scientific community;■ strengthening management: IRSN reaffirmedthe central role that unit managers play in makingthe Institute’s strategy operational and inmotivating their teams to achieve this.In this spirit,individual and collective interviews were organisedwith managers in 2004. These should lead to atraining programme on how to assume hierarchicalresponsibilities;■ managerial staff pay: after improvements to thepay grid of employees and non-managerial staffin 2003,discussions and negotiations started in 2004on how to simplify and boost the pay system formanagerial staff, engineers and researchers. IRSNwants to be able to attract young people, betterreward those who assume responsibilities,possessexpertise and achieve personal results and it wantsto motivate its staff throughout their career.The policy governing human resources managementwas redefined, and initiatives concerning its mainprocesses were taken in 2004.The aim was to defineor revise these processes and then formalise themto make them clearer and more effective.■ Recruitment: the recruitment process wascompletely reformulated – simplification of theadministrative management of dossiers and clearerfollow-up by operational units. The Director ofHuman Resources will systematically interview theapplicants who have been pre-selected by thedepartments.This will provide managers with adviceand a wider point of view, thus helping themmake their decision.■ The annual interview: the annual interview isa good individual and collective management tool.It has been completely redefined to effectively186I R S N ANNUAL REPORT 2004

meet IRSN’s priorities and ensure the dynamicmanagement of its human resources.■ Mobility: in 2004,employees joined organisationsoutside IRSN in order to pursue and enlarge theircareers. Mobility is one of IRSN’s main objectives,and it intends to sign agreements with researchbodies in France or abroad.This will make it moreopen to the scientific community and contributeto the development of relations with its mainpartners.An evolving workforceOn 31 December 2004,IRSN had 1,471 employeesfor a target workforce of 1,515 positions: 77% ofthe employees are under permanent contract (CDI)with IRSN, and 23% are seconded to the Institutefrom CEA. Managerial staff, engineers and researchersrepresent more than two thirds of the totalworkforce and the average age is quite young,with48% of women and 38% of men between 25 and35 years of age. Women represent 45% of IRSN’shuman resources.Social policyIRSN’s social environment was clearly defined in2003 (Board of Directors, Works Committee,personnel representatives, occupational safety,health and working conditions committee (CHSCT),etc.), and the company-wide agreement signed in2003, together with a series of additional agreementssigned in 2003 and 2004,provide employeeswith a high level of protection within a context ofactive and constructive industrial relations.During 2004, negotiations between managementand labour were held according to a fixed schedule.They concerned the choice of a new mutual insurancecompany offering a much better cover of healthexpenses for the same cost, the signing of anagreement on non-managerial staff pay grids, andthe signing of a salary settlement for 2004.The works committee and personnel representativesheld regular meetings in 2004.This represented atotal of more than 40 meetings. The workscommittee has been directly in charge of all itsmissions since 1 January 2004 so its work load hasincreased.2004 also saw a gradual increase in the openingof IRSN’s company saving plans.At the end of 2004,just over 20% of employees subscribed to them.Moreover,the Institute defined its housing assistancepolicy and chose two partner-collector organisations.Finally,a direct loan system for personnel has enabledabout 15 employees to receive financial aid tobuy a house/flat or a vehicle.Receiving young peopleIn 2004,IRSN received 63 young researchers undera thesis contract, 18 of whom were hired during theyear. During the same period, 27 post-doctorandsworked at the Institute,12 of whom arrived in 2004.IRSN provided 107 higher-education students withplacements, 74 of whom were post-graduatestudents or coming from engineering schools.The Institute signed eight new contracts of apprenticeshipand two contracts of qualification.These youngpeople are mainly preparing senior technician orengineering diplomas in electronics,chemistry andinformation technology.Breakdownaccording to sexMen 55%Women 45%Breakdown according tosocioprofessional categoryEngineers, researchers andmanagerial staff 68%Non-managerial staff 32%I R S N ANNUAL REPORT 2004187

HUMAN RESOURCES AND SOCIAL RELATIONSHUMAN RESOURCES AND SOCIAL RELATIONSINSER, training management software.Breakdownof training hoursper field in 2004Economy, management 2%IT 13%Languages 18%Management, communication 5%Project quality 9%Security 10%Science and Technology 43%Continuing professionaldevelopmentFurther professional training contributes to thedevelopment of the skills that the Institute requiresfor its different fields of activities. 40,000 traininghours were given in 2004, for a total teaching costof 1,150,000 euros.Two particular points are to be noted for 2004:■ the implementation of new software to managetraining:in the second half of 2004,the acquisitionand installation of dedicated software enabled usto prepare an inventory of the training needs for2005. Training courses on the centralised anddecentralised use of this software were given andthis will be continued in 2005, especially forreporting requirements;■ a consolidation of scientific and technical training:scientific and technical training represented 40%of training hours and 42% of teaching costs.188I R S N ANNUAL REPORT 2004

Glossary[ A ]ACT Advanced Communication Tool –■networking tool used withinthe framework of the SARNETADN Accord européen pour le transport■de marchandises Dangereuses par voie deNavigation extérieure (European provisionsconcerning the international carriage ofdangerous goods by inland waterway)AECL Atomic Energy of Canada Limited■AFA 3GLr AA Advanced Fuel Assembly■(2nd generation assembly) – name given toa certain type of fuel assemblyAFAQ Association Française d’Assurance■de la Qualité (French Quality AssuranceAssociation)AFSSAPS Agence Française de Sécurité■SAnitaire des Produits de Santé (FrenchAgency for the Safety of Health Products)AJE Association of journalists specialised■in the environmentAlpha (α) Radiation composed of helium 4■nuclei, highly ionising but not verypenetrating. A sheet of paper is sufficientto stop alpha radiationAMANDE Accélérateur pour la Métrologie■et les Applications NEutroniques enDosimétrie Externe (Accelerator formetrology and neutronics applications forexternal dosimetry) – IRSN, CadaracheANCLI Association Nationale des■Commissions Locales d’Information(French association of local informationcommissions)ANDRA Agence Nationale pour la gestion■des Déchets RAdioactifs (French Nationalagency for radioactive waste management)ANTHRO-Si Prototype of a whole-body■counting measurement system that canrapidly determine the radiation ofradionuclides incorporated by a personAplasia ■ Arrest or insufficiency inthe development of a tissue or organAREVA Industrial group including■the companies AREVA T and D, COGEMA,FRAMATOME, FBFC, COGEMA logistics,ANP, TECHNICATOME and FCIARMINES ■ Association for contractualresearch, partner of French EngineeringSchoolsASR ■ Authorisation to Supervise ResearchASTEC ■ Accident Source Term EvaluationCode – Scientific software used to simulatea core meltdown accident in a water reactor,from the initiating event to the release ofradioactive products out of the containment.It is developed jointly by IRSN and GRSASTRAL ASsistance Technique en■Radioprotection post-AccidenteLle(Technical assistance in post-accidentradiological protection). Quantifyingthe transfer of radioactive elements tothe agricultural environment followinga nuclear accident.ASTRID ■ Assessment of Source Term foremergency Response based on InstallationDataATPu Plutonium technology facility■(COGEMA)ATUe Enriched uranium treatment■workshopAVN Association Vinçotte Nucléaire■(Association Vinçotte Nuclear) - Belgium[ B ]B 4 C Boron carbide used as a neutron■absorber in the control rods that equip themost recent French reactors as well as theboiling water reactors in service in EuropeBADIMIS Computer database related to■the suspension of radionuclidesBAM BundesAnstalt für Materialforschung■und -prüfung (German Federal) – Institutefor materials research and testingBARRACUDA Programme dedicated to■the next generation of French nuclearattack submarinesBasemat Foundation of reactors in nuclear■power plantsBECARRE Essais de dégradation de Barres■En CArbure de boRe et RElâchementsassociés (Tests on the degradation of boroncarbide control rods and associated releases)Becquerel (Bq) Official international unit■for radioactivity measurement.The becquerelis equal to one disintegration per secondBeta (β) Radiation composed of electrons■of negative or positive charge.A few-millimetre air screen or a simplesheet of aluminium can stop this type ofradiationBiokinetics Refers to all the accumulation■and excretion kinetics of an element in anorganismBLEVE Boiling Liquid Expanding Vapour■ExplosionBNI Basic Nuclear Installation■BORIS Bioavailability Of Radionuclides In■Soils. European project aiming to study thebehaviour of radionuclides in formerRussian nuclear weapon complexes whereliquid radioactive waste was injected in-depthI R S N ANNUAL REPORT 2004189

Burnup fraction Thermal energy produced■by nuclear fissions in a fuel mass unit. It ismeasured in megawatts-day per ton (MWj/t)BWR Boiling Water Reactor■[ C ]CABRI Test reactor concerning fuel safety■used by IRSNCABRI REP-Na Water reactor with sodium■loopCABRI-CIP CABRI International Program■with water loopCaesium (Cs, atomic number 55) Noble,■toxic metal whose characteristics arecomparable to those of potassiumCALIBAN Experimental reactor■(CEA-Valduc), which can produce intensepulses of neutrons and fission gamma raysCallovo-Oxfordian Layer of sedimentary■rock from the Jurassic period (160 millionyears) which is the layer studied in the BurelaboratoryCAMARI Certificat d’Aptitude à Manipuler■des Appareils de Radiographie oude radioscopie Industrielle (Certificateattesting the ability to handle radioscopyand industrial radiography equipment)CANEL Experimental installation for■the instrumentation of radiologicalprotection, which can reproduce neutronspectra like those found at workstationsin facilities (IRSN, Cadarache)CARMELA IRSN research program on fires■in nuclear facilities aimed at gainingfurther insight into electrical cabinet firesCARMELO Combustion ARMoires■ÉLectriques essais glObaux (Global testelectrical cabinet combustion)CAROL CAmargue-RhÔne-Languedoc,■project for studying the distribution of artificialradionuclides in the Lower-Rhône regionCARTORAD Software used to map■radioactive measurementsCASTEAUR CAlcul Simplifié des Transferts■dans les cours d’EAUx Récepteurs(Simplified calculation of transfers inreceiving waterways). Simplified calculationof transfers of radioactive elements intoreceiving waterways for impact studieson accidental releases like routine releasesfrom fuel cycle plantsCATHARE Advanced thermal-hydraulic■calculation code used to studythe behaviour of pressurised water reactorsin accident situationsCATHARE-SIMU Version of the CATHARE■code adapted to the SIPA simulatorCDI Open-ended contract■CEA Commissariat à l’Énergie Atomique■(French atomic energy commission)CENELEC European committee for■electrotechnical standardisationCERCA Company for the study and the■realisation of atomic fuels (Romans – Isère)CESAR Software of the ASTEC system■simulating the thermal-hydraulics ofthe primary and secondary systems ina water reactorCHIP Experimental program on■“Iodine chemistry in the primary system”of a PWR during a core meltdown accidentCHRONIC RAD EPID Research project■carried out within the framework of 6th FPRDand dealing with epidemiological cancersassociated with chronic exposure toionising radiationCHSCT Comité d’Hygiène de Sécurité et■des Conditions de Travail (Health, safety andworking conditions committee)CICNR Comité Interministériel pour■la gestion des Crises Nucléaires et Radiologiques(Interministerial committee for the managementof nuclear and radiological crises)CIEMAT Centro de Investigaciones■Energéticas, MedioAmbientales yTecnológicas (Research centre for energy,environment and technology), Madrid – SpainCIP Competitivity and Innovation■framework ProgrammeCIREA Commission Interministérielle des■RadioÉléments Artificiels (Interministerialcommission for artificial radioelements)CIS bio international Company that■develops biomedical technologies forindustrial and commercial purposesCLI Commission Locale d’Information■(Local information commission)CMS Cote Majorée de Sécurité (Maximum■design flood level)CNAM-TS Caisse Nationale d’Assurance■Maladie – Travailleurs Salariés (Frenchemployee’s national health insurance fund)CNES Centre National d’Études Spatiales■(French space agency)CNRS Centre National de la Recherche■Scientifique (French national organisationfor scientific research)COFRAC Comité français d’accréditation■(French accreditation committee)COGEMA Compagnie générale des■matières nucléaires (French generalcompany for nuclear materials)190I R S N ANNUAL REPORT 2004

COGIC Centre opérationnel de gestion■interministérielle des crises (Interministerialoperational crisis management centre)COMURHEX Company that converts■Uranium into metal or hexafluorideCONRAD Radiological consequences –■software used to simulate the dispersionof accidental radionuclide releases intothe atmosphere and the short-term impactContainment Building or reactor building.■Leaktight concrete building housing thereactor pressure vessel, primary system,steam generators and main auxiliariesensuring reactor safetyCORE COoperation for the REhabilitation■of living conditions in contaminated areas –programme concerning 15 Byelorussiavillages, financed by the UNDP, the WorldBank, the EC, the diplomatic representationsin Minsk and Belarus. CORE operatorsinclude Médecins du Monde, Patrimoinesans Frontières, University of Caen,National Agronomic Training Institute ofParis-Grignon, IRSN, CEPN, the FrenchMinistry of Agriculture, FERT, À tous ventsdu monde, MutadisCOWAM 2 COmmunity WAste■Management 2 – research programmeinitiated as part of the 6th FPRD, coordinatedby Mutadis and in which IRSN participates.The programme aims to improvethe governance of radioactive wastemanagement and storage in EuropeCPHR Centro de Protección e Higiene de las■Radiaciones (Centre for health andprotection against radiation). Scientific andtechnical unit of the Nuclear EnergyAgency based in HavanaCRIS IRSN centre for scientific■information resourcesCRISTAL New French criticality package■developed as part of a joint projectbetween IRSN, CEA and COGEMA. It aimsat assessing the criticality risk in all nuclearfuel cycle plants and transport packageswhere fissile materials are usedCriticality Risk of uncontrolled fission■phenomena in fissile materialsCriticality accident Uncontrolled chain■fission reaction triggered in anenvironment containing fissile materialssuch as uranium-235 or plutonium-239CRPPH Committee on Radiation■Protection and Public Health (NEA)CRSSA Centre de Recherches du Service de■Santé des Armées (Army health serviceresearch centre)CTB Centre de Traitement des Brûlés■(Treatment Centre for Burn victims)Percy hospital, ClamartCTC IRSN’s emergency response centre■CTGF/CCN2 Connective Tissue Growth■FactorCTHEN Centre Technique d’Homologation■des Équipements Nucléaires (TechnicalCentre for nuclear equipment approval)CTHIR Centre Technique d’Homologation■de l’Instrumentation de Radioprotection(Technical centre for the radiologicalinstrumentation approval)[ D ]DAM Direction des Applications Militaires■du CEA (CEA’s military applications division)DARPMI Direction de l’Action Régionale et■des PMI (Department for regional actionand small and medium sized firms)DATANET SARNET experimental database■networkDATARAD Database of radioactivity■measurementsDCN DCN company, former shipbuilding■division of the DGA (French defenceprocurement agency)DDASS Direction Départementale des■Affaires Sanitaires et Sociales (Frenchdepartment direction of health and socialaffairs)DDSC Direction de la Défense et de la■Sécurité Civiles – Ministère de l’Intérieur(French directorate of civil defence andsecurity – Ministry of the Interior)DECOVALEX DEvelopment of COupled■models and their VALidation againstEXperimentsDEND Direction de l’Expertise Nucléaire■de Défense (Department for nucleardefence expertise) - IRSNDGA Direction Générale pour l’Armement■(French defence procurement agency)DGAC Direction Générale de l’Aviation■Civile (French Civil Aviation Authority)DGSNR Direction Générale de la Sûreté■Nucléaire et de la Radioprotection(French department for nuclear safetyand radiation protection)DISCO German experimental programme■on the direct heating of the reactorcontainment when corium is ejected out ofthe vessel – DISpersion of Contaminationtest bench (IRSN – Saclay)DISPRO Near-field dispersion■DIVA Dispositif expérimental pour■l’Incendie, la Ventilation et l’AérocontaminationI R S N ANNUAL REPORT 2004191

(Experimental system for fire, ventilationand air contamination)DM1 Modifying decision No.1 of IRSN budget■Dosimetry Detection, by assessment or■measurement, of the dose of radiation(radioactivity) absorbed by a substance ora personDOSMAX DoSimetry of aircrew exposure■during solar Maximum. Researchprogramme conducted as part of the 5th FPRDand in which IRSN took partDPPR Direction de la Prévention des■Pollutions et des Risques majeursdu ministère de l’Écologie et duDéveloppement durable (French departmentfor the prevention of pollution and risksfrom the Ministry of Environment andSustainable Development)DRASS Direction Régionale des Affaires■Sanitaires et Sociales (French regionaldepartment of health and social affairs)DRIRE Direction Régionale de l’Industrie,■de la Recherche et de l’Environnement(Regional directorate of industry, researchand environment)DRT Direction des Relations du Travail■(Staff relations branch)DSND Delegate for nuclear safety and■radiation protection for activities andinstallations related to defence[ E ]EBRD European Bank for Reconstruction■and DevelopmentEC European Commission■ECC European Community Commission■ECORAD International Conference■involving eco-toxicology and radioactivityEDF Électricité de France (French national■electric utility)EDZ Excavation Disturbed Zone■EMRAS Environment Modelling for■Radiation SafetyENUSA Empresa Nacional del Uranio, SA■(Spain) – Spanish nuclear organisation –(Industrias Avanzadas S.A.)ENVIRHOM IRSN research programme■aimed at studying radionuclide accumulationprocesses and the biological effects, duringthis accumulation, induced in the livingorganisms of plants, animals and humanssubjected to chronic exposureEORTC European Organisation for■Research and Treatment of CancerEOT Operational transport section (IRSN)■EPICUR A cobalt-60 irradiator used to■assess the behaviour of iodine underradiolysis (Cadarache)EPR European Pressurised Reactor■EPR Electron Paramagnetic Resonance■(France)EPRD Forecast statement of revenue and■expenditureEPRI Electric Power and Research Institute (US)■EPS2 Level-2 probabilistic safety■assessment. IRSN is currently assessing the900 MWe reactorsERICA Environmental Risk from Ionising■Contaminants Assessments andmanagementES Konsult Consulting firm specialised in■risk assessment, safety, quality assurance(Sweden)ESTRO European Society for Therapeutic■Radiology and OncologyEURANOS European approach to nuclear■and radiological emergency managementEURATOM European Atomic Energy■CommunityEURODIF European uranium enrichment■by gaseous diffusion plant(COGEMA, Pierrelatte – France)EUROFAB The project named EUROFAB■(for “FABrication en EUROpe”) is part ofthe programme for disposal of Russian andAmerican military plutonium exceedingdefence requirementsEUROSTRATAFORM European margin■strata formation – research programmeof the 5th FPRDEVIDOS Evaluation of individual■dosimetry in mixed neuton-proton fields –research programme financed bythe European Community withinthe framework of 5th FPRDEXTREME Research programme aimed at■studying the consequences of extremeclimatic events on the transfers ofradioactivity between in the compartmentsof the environment[ F ]FASSET Framework for ASSessment of■Environmental ImpacTFBFC Société Franco-Belge de Fabrication■de Combustibles (Franco-Belgian fuelmanufacturer)FGI French-German Initiative for■Chernobyl192I R S N ANNUAL REPORT 2004

FIRST Further Improvement of Radiotherapy■of cancer through side-effect reduction byinnovative application of adult Stem cellstransplantation for prevention andTreatment of deterministic radiationeffectsFLAMME_S Software developed by IRSN■that simulates in a simple manner theevolution of carbonated product fires ininstallations made up of mechanicallyventilated, confined premisesFLAMME_S/SIMEVENT FLAMME_S■software combined with SIMEVENTsoftware that simulates a fire in a groupof premises connected by a ventilationsystem and doorsFLIP Feux de Liquide en Interaction avec une■Paroi (Liquid fuel fire interacting with a wall)FPRD Framework Programme for Research■and Development (European Community)FPT-3 PHEBUS FP test dedicated■to studying the effects of B 4 C onthe degradation of a reactor core andon the release of fission productsFS 65 900 Fresh MOX fuel shipping■containerFuel assembly Cluster of fuel rods,■connected with a metallic structure,used in nuclear reactorsFzK Forschungszentrum Karlsruhe –■German advanced nuclear research centre[ G ]GALICE Name of a fuel management■method used in French power plantsGamma (γ) Highly penetrating but not■very ionising electromagnetic radiation,emitted by the disintegration of radionuclides.This type of radiation is stopped byconcrete or lead screensGATeL Génération Automatique de Tests à■partir d’une description Lustre(Automatic generation of tests froma lustre description)GDP Gaseous Diffusion Plants■(INBS Pierrelatte)GEIE Groupement Européen d’Intérêt■Économique (European economic interestgrouping)GIF Generation IV International Forum■GLP-2 Glucagon-Like Peptide■GP Standing advisory group■GPR Standing advisory group of experts■for nuclear reactorsGPU Standing advisory group of experts■for plantsGRNC Groupe Radioécologie du Nord-Cotentin■(Nord-Cotentin radioecology group)GRS Gesellschaft für Anlagen – und■Reaktorsicherheit (Germany)GWj/t Fuel burnup rate. Giga Watt days■per tonne of fuel. The customary unit formeasuring fuel assembly irradiation, i.e.,the energy extracted from the assembly inthe reactor per tonne of initial uranium[ H ]HAEA Hungarian Atomic Energy Authority■Hematopoietic cells Cells where red blood■cells are formedHFD Haut Fonctionnaire de Défense du■ministère de l’Économie, des Finances et del’Industrie (French Senior Defence Officialof the Ministry for Economy, Finance andIndustry)HLLL High-Level and Long-Lived■HLLLW High-Level and Long-Lived Waste■HRD Human Resources Division■HTR/VHTR High Temperature Reactor/Very■High Temperature Reactor (United Kingdom)[ i ]IAEA International Atomic Energy Agency■IARC International Agency for Research on■CancerICARE-CATHARE Software that accurately■describes the reactor core degradation upuntil tank rupture during a core meltdownaccidentICPE Installation Classée pour■la Protection de l’Environnement(Classified installations for the protectionof the environment)ICRP International Commission on■Radiological ProtectionICSBEP International Criticality Safety■Benchmark Evaluation ProjectICST Ingénierie de la Connaissance■Scientifique et Technique (Scientific andtechnical knowledge engineering)IEC International Electrotechnical■CommissionIFREMER Institut Français de Recherche■pour l’Exploitation de la MER (French researchinstitute for exploitation of the sea)IGR Institut Gustave-Roussy (Gustave■Roussy Institute) - FranceI R S N ANNUAL REPORT 2004193

INBS Secret basic nuclear installation■INERIS Institut National de l’Environnement■industriel et des RISques (French nationalinstitute for the industrial environment andhazards)InVS Institut de Veille Sanitaire■(French health watch institute)IPPAS International Physical Protection■Advisory ServiceIPS 47 OECD/CSNI’s International Standard■Problem dedicated to calculations on the THAItests carried out in Germany and TOSQUANIPSN Institut de Protection et de Sûreté■Nucléaire (French institute for protectionand nuclear safety)IRMA Cobalt-60 IRradiation unit with test■facilities to study the behaviour ofMaterials and equipment to irradiation(IRSN – Saclay)IRPA International Radiation Protection■AssociationIRSN Institut de Radioprotection et■de Sûreté Nucléaire (French Institute forradiological protection and nuclear safety)ISIS Calculation software that precisely■simulates the progress of a fire, gas, smokeand structures in confined spaces withmechanical ventilationISO International Standard Organisation■ISO 9001 European standard for quality■management systemsIsotopes Elements whose atoms have the■same number of electrons and protons, buta different number of neutrons. They havethe same name and the same chemicalproperties. Around 325 natural isotopesand 1,200 artificially created isotopes arecurrently listedIUR International Union of Radiology■IUR International Union of Radioecology■[ K ]K2-R4 Abbreviations for phase 2 of the■Khmelnitsky power plant and phase 4 ofthe Rovno power plant, both in UkrainekV KiloVolt■[ L ]LERISS Laboratoire d’Étude et de Recherche■en Instrumentation Signaux et Systèmes(Laboratory that carries out studies andresearch in signals and systems instrumentation)LFI Initial finance law■LMND Laboratoire de Métrologie et de■Dosimétrie des Neutrons (Laboratory forNeutron Metrology and Dosimetry),IRSN – CadaracheLPG Liquified Petroleum Gas■[ M ]M5 Type of pressurised water fuel cladding■MARN French nuclear risk management■aid committeeMCNP (Monte-Carlo N-Particule■Transport). Monte-Carlo code forsimulating the transportation of differentparticles: neutrons, photons, electrons,coupled neutrongamma.This code, developedin Los Alamos (USA), is the same as theTRIPOLI-4 code, developed by CEA (France)MEDD Ministère de l’Écologie et du■Développement Durable (French Ministryfor Ecology and Sustainable Development)MEDEC French health exhibition■MEDICIS ■ ASTEC system software used tosimulate ablation of the basemat bya melted reactor coreMELODIE Model for the long-term■assessment of buried radioactive wasteMELOX MOX fuel manufacturing plant■(COGEMA Marcoule – France)Mesenchymal Relating to embryonic■connective tissuemGy Milli Gray – unit of absorbed■radiation dose of the International Systemof UnitsMIMAUSA Memory and IMpact of■urAniUm mines: Summary and ArchivesMLLL Medium-Level Long-Lived■MORET Monte-Carlo code for simulation■of neutron transport (multi-groupapproximation) to calculate the effectivemultiplication factor (Keff) of 3-D complexsystemsMOX Fuel of uranium (natural or depleted)■and plutonium oxidesMOZART ■ Analytic tests to studythe oxidation kinetics of clads under airMRI Magnetic Resonance Imaging■mSv Milli Sievert – unit derived from dose■equivalent of the International System of UnitsMWe MegaWatt electric■194I R S N ANNUAL REPORT 2004

[ N ]N4 N4 series – series of 1,450-MWe■pressurised water reactors operated by EDFNAIMORI Novel Approaches in■the Management Of the Radiation Injury -European projectNEA OECD Nuclear Energy Agency■NF-PRO Near Field Processes■NNC National Nuclear Corporation -■Firm of nuclear services consultants(United Kingdom)NNSA-NSC National Nuclear Safety■Administration (United States) –Nuclear safety centre (China)NOD-SCID Line of immunodeficient mice■(non obese-diabetic/severe combinedimmunodeficiency)NRC Nuclear Regulatory Commission■(United States)NRG Nuclear Research and consultancy■Group (The Netherlands)NRPB National Radiological Protection■Board (United Kingdom)NSA Nuclear Security Agency (United■States)NSRR Nuclear Safety Research Reactor■(Japan)Nuclear fuel Fissile material (capable of■undergoing a fission reaction) used ina reactor to develop a nuclear chainreaction. After being used in a nuclearreactor, this is referred to as irradiated fuelNuclear island Assembly comprising■the nuclear boiler, the installations relatingto the fuel and the equipment needed tooperate and ensure the securityof this assemblyNuclear materials Materials which could■be used to manufacture a nuclear explosivedevice. They are defined according to theirfissile (for a fission device), fusible (for athermonuclear bomb), or fertile (capacityto produce fissile or fusible materials)characteristics. French legislation covers sixnuclear materials: plutonium, uranium,thorium, tritium, deuterium and lithium 6(deuterium and lithium 6 are not radioactive)Nuclear safety Set of measures taken■at all levels of design, construction, operationand decommissioning of the nuclearinstallations to prevent accidents and limittheir effectsNUPEC Nuclear Power Engineering■Corporation – Japanese nuclear safetyorganisation[ O ]OECD Organisation for Economic■Cooperation and DevelopmentOECD/CSNI Organisation for Economic■Cooperation and Development/Committeeon the Safety of Nuclear InstallationsOECD/NEA OECD Nuclear Energy Agency■OEDIPE Tool for assessment of■personalised internal doseOJ Official Journal■OPCW Organisation for the Prohibition■of Chemical WeaponsOPERA IRSN permanent environmental■radioactivity observatoryOPRI Office de Protection contre les■Rayonnements Ionisants (French office forprotection against ionising radiation)ORME Observatoire Régional■Méditerranéen de l’Environnement(French mediterranean environmentobservatory)ORPHEE Experimental, pool-type nuclear■reactor with a rated power of 14 MWth(CEA Saclay – France)[ P ]P4 Plant series comprising eight,■1,300-MWe, water-pressurised reactorsat Paluel, Flamanville and Saint-AlbanP’4 Plant series comprising twelve,■1,300-MWe, water-pressurised reactors –the most recent French reactorsPACA Provence-Alpes-Côte-d’Azur region■(France)PANAME Method developed by IRSN to■quantify the reliability of operating actionsPASEPRI Action plans for the monitoring of■patient exposure to ionising radiationPATRAM International symposium■on PAckaging and Transportationof RAdioactive MaterialsPCO Operational control centre■PCRDT Framework Programme for■Technological Research and DevelopmentPHARE Poland-Hungary Assistance for■Reconstruction of the Economy – Europeanassistance programme for reconstructionof polish and hungarian economiesPHEBUS FPT3 FPT-3 test of the PHEBUS-FP■programmePHEBUS-FP IRSN experimental programme■on the degradation of a nuclear reactorcore and the release of Fission Products (FP)I R S N ANNUAL REPORT 2004195

PHENIX 250-MWe fast neutron reactor■PIC Common interest program■PICSEL Propagation of solid fuel fire in■a laboratory and plant environmentPIV Particule Image Velocimetry■PKL Primar KreisLauf – test loop used for■inherent dilution phenomenaPlant unit Power production unit including■a boiler and a turbo-generator set. A nuclearplant unit is mainly defined by its type ofreactor and the power of its turbo-generatorPlutonium (Pu, atomic number 94).■Transuranic chemical element. The isotope239 has a half life of 24,110 yearsPN3 “Trace detector” dosimeter for■neutronsPNNL Pacific Northwest National■Laboratory (United States)POLLUTEC International trade fair for■environment-related equipment,technologies and services for industryPPI Special response plan■Primary system Reactor coolant system■operating in a closed loop, comprisinga series of components ensuring thecoolant fluid circulation used to extractthe heat given off by the reactor corePRISME Propagation of a fire for■elementary, multi-premises scenariosPSA Probabilistic Safety Assessment■PUI Internal emergency plan■PWR Pressurised Water Reactor■[ Q ]QUENCH German experimental■programme aimed at studying hydrogenproduction during the degradationof a reactor core[ R ]Radiation protection Set of measures■intended to ensure health protection ofthe population and workers using ionisingradiation sourcesRadioactivity Property of certain chemical■elements whose nuclei spontaneouslydisintegrate into other elements emittingionising radiationRadioelement Natural or artificial■radioactive elementRadionuclide Radioactive isotope of an■elementRASSC Radiological Safety Standards■Committee (IAEA)RBMK Graphite reactors from■the ex-Soviet UnionRECI RECombiner of Iodine – experimental■system used to assess the influence ofrecombiners on the chemistry of iodinein the containment (IRSN, Saclay – France)REMOTRANS REMObilisation, long■distance TRANsport and bioavailability ofradionuclides in marine sedimentsREP-Na Experimental programme in■the sodium loop of the CABRI reactoraimed at studying the behaviour of fuelduring a power transientRES Test reactor■RHF Laüe Langevin Institute’s high-flux■reactor (France)RIA Reactivity Insertion Accident■RNG New generation reactor■RNIPP Répertoire National Individuel des■Personnes Physiques (National register of persons)RPO Radiation Protection Officer■[ S ]SAE Annual statistics for public and■private health establishmentsSARA Automated monitoring of aerosol■radioactivitySARNET Severe Accident Research■NETwork of excellence – a Europeannetwork of excellence on water reactorcore meltdown accidents – 6th FPRD projectSATURNE Experimental installation with■an extractor hood aimed at studyingthe progress of a fireSC 45B “SECNUC exercise” –■“Nuclear Safety” exerciseSCANAIR Software used to calculate■an RIA-type transient developed by IRSNSDMV Synchronised Distributed Mapped■ValuesSEBIM Brand of valves■SECNUC Nuclear safety■SEVESO The Seveso accident, that happened■in Italy in 1976, gave its name to a Europeandirective on industrial accident risksSFR Société Française de Radiologie■(French radiology organisation)SFRP Société Française de RadioProtection■(French society for radiation protection)SGDN Secrétariat Général de la Défense■Nationale (French general secretariat fornational defence)SICN Industrial nuclear fuel company■(CEAI) (nuclear fuel fabrication plant)196I R S N ANNUAL REPORT 2004

SIEVERT Information and assessment■system of the exposure to cosmic radiationduring flightsSIGIS Information and management■system for the national inventoryof ionising radiation sourcesSIGMA Graphite block containing■radioactive sources, producing a “realistic”field of mainly thermal neutrons(IRSN, Cadarache – France)SILOE Pool-type reactor (CEA/Grenoble)■SILOETTE Pool-type teaching reactor■(CEA/Grenoble)SIMEVENT Software simulating aeraulics■in a ventilation system developed as partof a joint project between IRSN, SGN andCOGEMASIMO Mining company in western France■(CEA)SIPA Pressurised water reactor accident■simulator developed and used by IRSNSIPA/SCAR “Simulator CATHARE Release” –■a joint project conducted by IRSN and EDFaimed at integrating the thermal-hydrauliccode CATHARE 2 into IRSN’s SIPA 2 simulatorSISERI Ionising radiation exposure■monitoring information systemSKI Swedish nuclear power inspectorate■SNA Nuclear attack submarine■SNCF Société Nationale des Chemins■de Fer français (French national railwaycompany)SNLE Nuclear-powered ballistic missile■submarineSNM Military nuclear system■SNR Fast breeder reactor■SNRCU State Nuclear Regulatory■Commitee of UkraineSSD Department for the safety of■radioactive waste (IRSN)SSI Swedish radiation protection authority■SSTC State Scientific and Technical Centre■(Ukraine)STARMANIA Station for the study of■airborne contamination transfer andmechanical strength under incident andaccident conditions (IRSN Saclay – France)STE Technical operating specifications,■effluent treatment centreSTI Scientific and Technical Information■STUK Stäteilyturvakeskus – Radiation and■nuclear safety authority (Finland)SUNSET Statistical calculation tool that,■when combined with software that simulatesphysical phenomena, can be used to studythe effect on chosen calculated responsesof uncertainty concerning some parametersand data entered into the softwareSYLVIA Software system used to study■ventilation, fire and air contaminationSYMBIOSE Systemic approach■for modelling the fate of chemicalsin biosphere and ecosystems[ T ]TACIS Technical Assistance for■Commonwealth of Independent States –European assistance programme forthe reconstruction of economies inthe new independent statesTID Total Indicative Dose■TONUS Code developed by the CEA■on behalf of IRSN that uses models thatgovern the distribution of hydrogenin the containmentTOSQAN TonuS Qualification ANalytique –■Experimental containment used toreproduce a small-scale accident scenarioenacting a hydrogen risk in a nuclearreactor containment (IRSN Saclay – France)TPO Thrombopoïetin■TranSAS Transport Safety Appraisal Service■TRG Translational Research Group■TVO Teollisuuden Voima Oy –■Finnish electricity company[ U ]■UF 6 Uranium hexafluorideUNSCEAR United Nations Scientific■Committee on the Effects of AtomicRadiationUOX3 Fuels with an initial U 235 content■of 4.5 % and a burnup fraction of 60 GWj/tUP1 Biggest plant for the reprocessing■of spent nuclear fuels with a viewto them being recycled in France(Cogema Marcoule – France)UP2-800 Irradiated nuclear fuel■reprocessing plant located at the Site inLa Hague (Cogema – France)[ V ]VHE ■ Very High Efficiency[ W ]WHO ■ World Health OrganisationI R S N ANNUAL REPORT 2004197

Contents1. News, strategy and organisation . . . . . . . . . .02> Foreword by J.-F. Lacronique and J. Repussard . . . . . . . . .04> Foreword by M. Brière . . . . . . . . . . . . . . . . . . . .06> IRSN missions . . . . . . . . . . . . . . . . . . . . . . .07> IRSN in 2004: Report and perspectives . . . . . . . . . . . .08> Main events . . . . . . . . . . . . . . . . . . . . . . . .10> Organisation: A short description of IRSN . . . . . . . . . . .14> Activity 2004 : Key figures . . . . . . . . . . . . . . . . .15> The Board of Directors . . . . . . . . . . . . . . . . . . .16> The Scientific Board . . . . . . . . . . . . . . . . . . . . .17> Organisation chart . . . . . . . . . . . . . . . . . . . . .18> IRSN sites . . . . . . . . . . . . . . . . . . . . . . . . .192. Activities in 2004 . . . . . . . . . . . . . . . . . . . .20Description of programmes . . . . . . . . . . . . . .22Research and public service missions . . . . . . . .28> Defining and implementing nationaland international research programmes . . . . . . . . . .30• Support for the safety assessment of operational reactors .30• Research into the ageing of PWR . . . . . . . . . . . . .31• The fuel and its management duringnormal and accident operating conditions . . . . . . . . .31[ Modelling of irradiated fuel behaviour in a reactivityinsertion accident (RIA) ] . . . . . . . . . . . . . . . . . . 32• Modifications to the CABRI installation . . . . . . . . . .34• Research work into severe accidentswith core meltdown . . . . . . . . . . . . . . . . . . .35[ SOURCE TERM programme ] . . . . . . . . . . . . . . . . 36[ FPT-3: final test under the PHEBUS-FP programme ] . . . . . . . 38[ TOSQAN programme ] . . . . . . . . . . . . . . . . . . 39• Safety of plants, transport and dismantling . . . . . . . .40[ CRISTAL V1.0: new version of the CRISTAL package ] . . . . . . . 41• Waste-related research activity . . . . . . . . . . . . . .43[ Innovations in the MELODIE software ] . . . . . . . . . . . . 44• Incorporation of human factors in the design processes . .46• Research activity in the fire and aerodispersion fields . . .46[ Behaviour of uranium hexafluoride (UF 6 )] . . . . . . . . . . .47[ PRISME experimental programme ] . . . . . . . . . . . . . 48[ PICSEL experimental programme ] . . . . . . . . . . . . . . 49[ SYLVIA software platform ] . . . . . . . . . . . . . . . . 50• Research on earthquakes . . . . . . . . . . . . . . . . .50• Radioecology research . . . . . . . . . . . . . . . . . .51[ Launch of the ERICA European programme ] . . . . . . . . . . 51[ Launch of the EXTREME project ] . . . . . . . . . . . . . . 52[ The ECORAD congress ] . . . . . . . . . . . . . . . . . . 53• Research into the metrology of radionuclidesin the environment . . . . . . . . . . . . . . . . . . .54• Influence of exposure chronicity on the behaviourand toxicity of radionuclides:the ENVIRHOM programme . . . . . . . . . . . . . . .55• Research activity on radon . . . . . . . . . . . . . . . .58[ Understanding the radon concentration mechanismsin buildings ] . . . . . . . . . . . . . . . . . . . . . . . 58[ Use of radon as a geological probe ] . . . . . . . . . . . . . 59• Epidemiology of nuclear workers . . . . . . . . . . . . .60[ Coordination of European projects on the epidemiologyof ionising radiation ] . . . . . . . . . . . . . . . . . . . 61• Improvements in radiation protection . . . . . . . . . .62[ ANTHRO-Si project ] . . . . . . . . . . . . . . . . . . . 63[ Cosmic radiation: the DOSMAX project ] . . . . . . . . . . . 65• The AMANDE installation . . . . . . . . . . . . . . . .66• The radioprotection of patients: consequencesof radiotherapy on healthy tissue presentin the radiation field . . . . . . . . . . . . . . . . . . .67[ European moves in medical radiation protection ] . . . . . . . . 67• Irradiation and contamination accidents . . . . . . . . .68[ Improvements in the diagnosis of cutaneousradiation syndrome ] . . . . . . . . . . . . . . . . . . . 69[ European FIRST Project ] . . . . . . . . . . . . . . . . . 72• Management of post-accident situations . . . . . . . . .73• International cooperation to improve controlover radiological and nuclear risks . . . . . . . . . . . .73[ International conference on the FGI results ] . . . . . . . . . . 74[ Development of cooperation between IRSN and the NRC ] . . . . 75[ End of the European ASTRID project ] . . . . . . . . . . . . . 76• New recommendations concerning radiation protection . .77> Contributing to training in radiation protection . . . . . .78• An activity to help prevent risks and their possibleconsequences . . . . . . . . . . . . . . . . . . . . . .78[ Training on radon ] . . . . . . . . . . . . . . . . . . . . 79> Permanent monitoring in matters of radiation protection .81• Radiological monitoring of the environment . . . . . . . .81• Monitoring ionising radiation sources . . . . . . . . . . .83> Public information . . . . . . . . . . . . . . . . . . . .84• Information and communication activities . . . . . . . .84[ EUROSAFE 2004 forum ] . . . . . . . . . . . . . . . . . 86198I R S N ANNUAL REPORT 2004

Technical support and assistance for publicauthorities . . . . . . . . . . . . . . . . . . . . . . .88> Technical support with regard to nuclearand radiological risk . . . . . . . . . . . . . . . . . . . .90• Reactor safety analysis . . . . . . . . . . . . . . . . . .90[Incident at Fessenheim ] . . . . . . . . . . . . . . . . . . 91[ Incident at Cattenom ] . . . . . . . . . . . . . . . . . . 92[ Insulation defect on valve actuators ] . . . . . . . . . . . . 93[ Examination of feedback from 2000-2002 ] . . . . . . . . . . 94[ EPR Reactor: collaboration with Finland ] . . . . . . . . . . . 95[ Safety of the CABRI experimental reactor ] . . . . . . . . . . 96• Support for the safety assessment of operational reactors .98[ Comparative study of PSAs applied to safety-related events ] . . . 99• Ageing of pressurised water reactors . . . . . . . . . . .101• Fuel in normal and accident operating conditions . . . . .102[ IRSN’s opinion on the “MOX Parity” dossier ] . . . . . . . . . 102• Examination of risks associated with severecore meltdown accidents . . . . . . . . . . . . . . . .104[ Basemat at the Fessenheim power plant ] . . . . . . . . . . 104[ EPR corium recovery system ] . . . . . . . . . . . . . . . 105• Safety expertise for future reactors to follow EPR . . . . .106• Safety of plants, transport and dismantling . . . . . . . .107• Examination of safety dossiers concerning mining wasteand participation in the writing of regulations . . . . . .111[ MIMAUSA programme ] . . . . . . . . . . . . . . . . . 112• Human and organisational reliability . . . . . . . . . . .114[ Integration of human factors in the design of modificationsto EDF power plants ] . . . . . . . . . . . . . . . . . . . 115• Fire protection of installations . . . . . . . . . . . . . .116[Fire PSA] . . . . . . . . . . . . . . . . . . . . . . .116• Radioecological impact studies . . . . . . . . . . . . .118• Earthquake and flood risks . . . . . . . . . . . . . . .119• Environmental monitoring . . . . . . . . . . . . . . .120[ Setting up the national network for environment radioactivitymeasurements ] . . . . . . . . . . . . . . . . . . . . . 120• Technical support in the field of radon . . . . . . . . . .121• Radiation protection response and assistance . . . . . .122• Radiation protection of workers . . . . . . . . . . . . .122• Radiation protection in the medical field . . . . . . . . .124[ Radiographic examinations in sports medicine ] . . . . . . . . 124[ Joint IRSN/AVN/GRS guide to safety assessment ] . . . . . . 125[ Strengthening cooperation with Chinese safetyand radiation protection organisations ] . . . . . . . . . . . 126[ Hosting trainees from Chinese safety organisations ] . . . . . . 127> Operational support in the event of a crisis or radiologicalemergency . . . . . . . . . . . . . . . . . . . . . . . .128• Emergencies . . . . . . . . . . . . . . . . . . . . . .128[ Real action taken by the CTC ] . . . . . . . . . . . . . . . 129[ Exercise in dealing with victims of a radiological attack ] . . . . 130[ Exercise in dealing with an accident involving transportedradioactive material ] . . . . . . . . . . . . . . . . . . . 131• Support in managing post-accident situations . . . . . .132[ Pierrelatte exercise ] . . . . . . . . . . . . . . . . . . . 133[ CD-Rom – “Information on nuclear risk and how it is managed” ] . . 134• Operational support in case of crisis . . . . . . . . . . .135[ Plan to renew mobile resources ] . . . . . . . . . . . . . . 135Contractual services of expert appraisal,research and measurement . . . . . . . . . . . . . .136> Services related to statutory requirements . . . . . . . .138• Radiological testing of water intendedfor human consumption . . . . . . . . . . . . . . . .138• Radon detection . . . . . . . . . . . . . . . . . . . .138• Radiation protection of workers . . . . . . . . . . . . .139• Conformity of materials and equipment . . . . . . . . .140[ Non-nuclear third-party expertise ] . . . . . . . . . . . . . 141> Services not related to statutory requirements . . . . . .142• Study regarding the presence of radionuclidesin the Toulouse urban area sewer system . . . . . . . . .142• Operational radiation protection services . . . . . . . .143• Radioecology services . . . . . . . . . . . . . . . . .143• Operating method for radon measurement . . . . . . .144• Services concerning dispersal of contaminants . . . . . .144[ Probabilistic safety assessments applied to industrial sites ] . . . . 145• Dosimetry services . . . . . . . . . . . . . . . . . . .146• Assessment of dose received by the foetusduring a diagnostic examination on a pregnant woman . .149[ Consulting and assistance for healthcare professionals ] . . . . . 149• Collaboration with Eastern European countries . . . . . .151[ Assistance to Eastern European countries ] . . . . . . . . . . 151• Expertise and assistance for civilian society . . . . . . .153Defence nuclear expertise . . . . . . . . . . . . . . .154> Assessing the safety of military nuclear systems,basic nuclear installations and Defence-relatedtransportations . . . . . . . . . . . . . . . . . . . . .156[ BARRACUDA programme ] . . . . . . . . . . . . . . . . 157> Protection and control of nuclear and sensitive materials . 159[ Impact of the new Euratom regulation on national control ] . . . 160[ Additional protocol ] . . . . . . . . . . . . . . . . . . . 163> Protecting installations from malicious acts . . . . . . . .164> Managing emergencies caused by malicious acts . . . . .166[ Crisis exercise involving the inventory of nuclear materials ] . . . 1673. Management and support . . . . . . . . . . . . . .168> Scientific and technical excellence . . . . . . . . . . . .170• Scientific and technical knowledge engineering . . . . . . .175• Security . . . . . . . . . . . . . . . . . . . . . . . .176• Quality: IRSN’s Certification project . . . . . . . . . . . .178[ Renewal of accreditations for the sample analysis department ] . . 178> Communication . . . . . . . . . . . . . . . . . . . . .180> Human resources and social relations . . . . . . . . . . .184I R S N ANNUAL REPORT 2004199

EDITORIAL COORDINATIONDepartment for Strategy, Development and External RelationsEDITORIAL COMMITTEESG/DAF: D. DemeillersDESTQ: F. BretheauDEI: N. Chaptal-GradozDPAM: B. AdroguerDSR: A. DumasDSDRE: E. MurDCOM: M.L. de Heaulme, H. FabreDEND: J. Jalouneix, D. FranquardDRPH: J. Aigueperse, J. BrenotDSU: P. Cousinou, S. ClavelleAUTHORSIRSN with the assistance of Camille Jaunet (La Clé des mots)PRODUCTION COORDINATIONCommunications DepartmentGRAPHIC DESIGN AND COORDINATIONPRODUCTION ASSISTANCELAO Conseil, ré(craie)actionPRINTINGOPAGPHOTO CREDITSAREVA: page 42 (diagram) ■ AREVA / Geoffray Yann: pages 40 (top) and 103 ■ AREVA / Jean-Marie Taillat: pages 113 (top) and 156 ■ AREVA /Les films de Roger Leenhardt: page 109 (top) ■ CEA: page 101 (bottom and band) ■ Claude Cieutat: page 142 (top) ■ Cogema / Jean-Marie Taillat:page 110 ■ DGA (French defence procurement agency): page 157(top) ■ DR: page 106 ■ EDF Multimedia Library / Claude Cieutat: page 31(right) ■ EDF Multimedia Library / Guillaume Lemarchal: page 31 (left) ■ EDF Multimedia Library / Guy Jaumotte: page 93 (bottom) ■ EDFMultimedia Library / Marc Moreau: page 104 (bottom)■ EDF Multimedia Library / Mario Guerra: page 164 ■ EDF Multimedia Library / Philippe Brault:page 95 (top) ■ EDF Multimedia Library / Serge Lohner: page 91 ■ Éric Couderc: page 54 ■ F. Parozzi / CESI: page 75 ■ GRS: pages 74, 86(bottom) ■ French Navy / Romain Veyrié: page 154 ■ Gunther Vincent: pages 26 (middle), 76, 94 (bottom), 96 (top), 97 (top and band), 99(top and band), 102, 128 ■ IRSN: pages 18, 25 (middle), 26 (left), 38 (bottom), 49 (bottom), 53 (bottom), 77, 108 (band), 116 (band), 117(bottom), 122, 127 (bottom), 131 (bottom), 142 (bottom and band), 145, 147, 152, 159-162, 163 (top), 174 ■ IRSN / Claude Cieutat: page 82(top) ■ Stéphane Jungers: pages 92, 103, 105, 106, 116, 129 (bottom), 143, 152, 153 ■ KhNPP Photo: page 151 ■ Mickaël Lafontan: pages 2,5, 18, 20, 22 (left and band), 23 (left), 24 (left), 25 (left), 26 (right), 28, 39 (bottom and band), 41, 42 (top and band), 44 (bottom), 47, 53 (topand band), 58- 61,63, 64, 65 (right), 67-72, 83 (profile), 88-90 (top), 92, 93 (top), 94 (top), 99 (bottom), 100, 104 (top), 107, 109 (bottomand band),114, 115, 123 (top)-125, 126, 127 (top and band), 129 (band), 130, 131 (top and band), 132, 133 (bottom), 134 (top), 136, 139,140, 141 (top), 146, 148, 149 (right), 150, 157 (band), 158, 163 (bottom and band), 165 (bottom), 167 (left), 168, 183, 184, 186, 187, 188(profile) ■ Olivier Seignette: pages 6, 18, 22 (right), 23 (middle), 24 (middle and right), 25 (right), 27 (right), 30, 32-37, 38 (top and band),39 (top), 40 (band), 43, 44 (top and band), 45, 46, 48, 49 (top and band), 50-52, 55-57, 62 (band), 65 (left), 66, 78-81, 82 (bottom and band),90 (band), 94 (band), 96 (band), 97 (bottom), 98, 101 (top), 105, 111, 112, 117 (top and band), 118-121, 123 (band), 133 (top and band),134 (band), 135, 138, 141 (bottom), 143, 144, 149 (left), 165 (top and band), 170, 172, 173, 175-177, 179, 180, 184 ■ Olivier Seignette /Mickaël Lafontan: pages 85 (bottom) and 86 (top) ■ SIRPA Air: pages 23 (right), 166 ■ SMO: page 108 (top) ■ Technicatome: page 157(bottom) ■ Thomas Gogny: pages 27 (left), 84, 85 (top and band), 87 ■ TVO: page 95 (bottom)© Communication IRSNN° ISSN: 1762-0600200I R S N ANNUAL REPORT 2004

Finance Ledger ofthe Annual Report2004

Didier Demeillers,Director in charge of Financial Matters

Contents04 > Management report08 > Profit & loss account10 > Balance sheet12 > Intermediate management balances13 > Self-financing capacity14 > Variation in liquid funds15 > Forecast and completion reconciliationBreakdown of resources(in M€)MEDD subsidy 201.9MINDEF subsidy 2.7Other subsidies 2Own resources 35.2Miscellaneous 3.8

[ FINANCE LEDGER OF THE ANNUAL REPORT 2004 ]Management reportLaw 2001-398 of 9 May 2001 creating the French health and environmental safety agency merged, in article 5,within a public establishment of industrial and commercial nature named IRSN, part of the Office for protectionagainst ionising radiation and the Institute of protection and nuclear safety.1. Evolution of the InstituteAfter the 2002 financial year, limited to ten months(from 28 February to 31 December) and not incorporatingthe accounts of OPRI and IPSN,the 2003 financial yearreally marked the accounting and financial birth ofthe Institute with a normal twelve-months period andincorporation in the closing balance sheet of the assetsand liabilities of OPRI and IPSN.The end of 2003 alsosaw finalisation of the new organisation of the Institute.It was transcribed into the Institute’s budget at thebeginning of 2004 and was adjusted at the DM1 ofJune 2004.This has affected the whole financial year,more particularly certain investments whose completionwas delayed.In addition,installation of monitoring per process andlaunching of steps towards ISO 9001 version 2000certification by 2007,marks a stage in the continuousimprovement process involving Institute managementas a whole.Consistent with this quality orientation,major progresshas been made in improving budgetary piloting ofactivities, both in forecasting and in realisation, witha finer monitoring of activities by using a budgetarypresentation per client. This economic and financialsupervision system will be completed in 2005 byimplementing a decision information system,currentlyin the course of installation, and the launching ofcost accounting revision which will enable refinementof cost price relevance.The main features of the 2004 financial year, apartfrom extraordinary items, are:■ observance of balances presented for the approval ofthe Board of Directors with the EPRD 2004;■ a budget realisation rate of 97.5%, a variation of7 M€ due,as to 2.5 M€,to delays in completing certaininvestments, and as to 4 M€, to a fall in costs and asmaller sales figure.At the end of the year, extraordinary items disruptedthe 2004 balances:■ non-payment by MEDD of the counterpart of thebudget deficit consequent on the tax system implementedon creation of the Institute,budgeted for in EPRDat 9.2 M€ inc. VAT;■ cancellation, in the sum of 1.5 M€ inc.VAT, of thebalance of receivable income, established in 2002 atan initial amount of 22.5 M€.MEDDsubsidyMINDEFsubsidyOthersubsidiesOwnresourcesMiscellaneousOperating income(in M€)215200175150125100755020032004252. Profit & loss account analysis2.1. Income2.1.1.Operating income net of tax rose 10.1 M€ incomparison with 2003 (+ 4.3%).It totalled 245.6 M€, including:■ 201.9 M€ for the MEDD subsidy,representing,afterdeduction of VAT, the entire allowance shown in LFI,up by 3.8 M€ in comparison with the precedingaccounting period in which a cancellation was effectedduring the year;■ 2.7 M€ in respect of the agreement with the ministryof Defence, as against 2 M€ in 2003;■ 2 M€ for other subsidies, in particular from localauthorities, the level of which stays much the samefrom year to year;■ 35.2 M€ of own resources from expert activities orco-financing of research programmes. The fall insuch resources in relation to DM1,balanced by a reductionin expenditure of the same amount, is explainedmostly by disruption, linked on the one hand to thereorganisation adjustment for the whole of 2004,andon the other hand to uncertainties resulting from theending on 27 February 2005,of the option period fixedfor operators seconded from CEA. However, thisfinancing source rose by 3.7 M€ in comparison with4FINANCE LEDGER OF THE I R S N ANNUAL REPORT 2004

that of the previous year, consistent with theorientation adopted for diversification of resources;■ 3.8 M€ sundry income, including 3.3 M€ fromcancellation of accruals established in previous financialyears, 0.1 M€ for industrial property royalties and0.4 M€, sundry income on current management.2.1.2.Total financial income was 1.4 M€, as against 1 M€in 2003. The DM1 provided for 0.4 M€. The strongincrease in this income is explained by the imbalancebetween the regular payment of subsidies, whichaccounts for 85% of IRSN resources, and the concentrationof payments at the end of the financial year,resulting in particular from the difficulties encounteredin separating the activities of the Institute from thoseof CEA.The stated increase in income, 1 M€, has beenposted completely to working capital consolidation.2.1.3.Extraordinary income, particularly high in 2003(25.2 M€), came down to 6.7 M€ in 2004. 6.5 M€relates to the portion of investment subsidies transferredto the Profit & loss account.The balance, 0.2 M€,corresponds to sundry current management transactions.Total income for the 2004 financial year is therefore253.8 M€,as against 261.7 M€ the previous year,thereduction resulting exclusively from extraordinaryoperations.2.2. Charges2.2.1.Financial year operating charges fell by 15 M€ incomparison with 2003 (-5.8%), to 246 M€.They are broken down as follows:■ overall personnel charges, including employeesseconded from CEA:102.3 M€,against a DM1 forecastof 104.5 M€. This reduction of 2.2 M€ is explainedby the deferring of recruitment plans and is to be reconciledwith the non-realisation of 4 M€ of services sold;■ taxes: 4.1 M€ as against 4.8 M€ in 2003, including1.6 M€ tax on remuneration, and 1.3 M€ made upby a provision for contingencies as the method fordetermining business tax is not yet known. Thisvaluation has been revised downwards and justifiesthe reduction in this item from one year to the next;■ depreciation of 13.6 M€ is lower than the DM1forecast taking into account the delay in certainoperations, and a particularly large reduction incomparison with the 2003 provision, due to theageing of equipment whose replacement financinghas not been ensured.The provision allowance represents a total of 2.9 M€including 1 M€ for the dispute following the fuelpollution of the Le Vésinet site and 1.9 M€ for wastetreatment costs;■ purchases of goods and services was 121.9 M€,asagainst 125 M€ in 2003. This variation is not verysignificant.It simply reflects fluctuations in activities;■ other charges were 1.2 M€, including 0.9 M€ for cancellationof accruals established in previous financial years.2.2.2.The financial charge and the charge paid for profitstax (fixed annual taxation) are cited as a reminder.The cancellation of the balance of accruals (10.7 M€inc.VAT) made up by the MEDD subsidy for the 2002financial year constitutes the main portion ofextraordinary charges of 13.7 M€. For information,a comparable cancellation of 2.9 M€was applied in 2003.Total charges for 2004 were therefore 259.8 M€, asagainst 261.3 M€ for the preceding financial year.2.3. Result and financing2.3.1.The financial year resulted in a loss of 6 M€, asagainst a forecast profit of 1 M€ according to therevised decision of EPRD, and a profit of 0.4 M€in 2003.The variation with the DM1 results from thetaking over of an OPRI VAT adjustment of 2.2 M€ andespecially the non-payment by MEDD of 9.2 M€ ofthe tax deficit.These extraordinary charges have beenpartly compensated by a higher level of financialincome,a reduced depreciation charge for the financialyear and the balance of 2003 accruals unused in 2004.2.3.2.The self-financing capacity of the Institute,whichwas 10 M€ in EPRD,has reduced,due to extraordinaryoperations, to 5.1 M€ as against 10.3 M€ in 2003.Consequently, financing of investments at 16 M€ isbalanced by a large debit of 10.8 M€ on workingDetails of income(in M€)50 100 150 200 2502003200420032004OperatingincomeFinancialincomeExceptionalincomeOperating charges(in M€)25 50 75 100 125 150TaxesDetails of charges(in M€)50 100 150 200 250 30020032004PersonnelDepreciation/ProvisionsPurchasesgoods-servicesOperatingchargesOtherchargesFINANCE LEDGER OF THE I R S N ANNUAL REPORT 20045

[ FINANCE LEDGER OF THE ANNUAL REPORT 2004 ]capital,whereas the debit was already 3.2 M€ in 2003.It should be noted that the ex-OPRI investments of1.5 M€,and loans to personnel of 1.2 M€,which EPRDenvisaged financing by debit from working capital,were not entirely realised and will be deferred to thenext financial year for an amount of 0.73 M€. In thesame spirit, certain investments whose financingappeared in EPRD 2004 and for which a delay inrealisation did not enable the expenditure to be madein its entirety, will be deferred to the next financialyear and will therefore be financed in 2005 by a debiton working capital, excessive in relation to 2004.2.3.3.Despite the fact that IRSN has maintained, apart fromextraordinary items,the equilibrium forecast by EPRD,the financial year shows a new debit from workingcapital of 10.8 M€.Invested capitalin M€3.1. Liabilities3.1.1.After taking into account the loss recorded in 2004,invested capital comprises a net balance of 34.6 M€,12.3 M€ of investment subsidies and 12.4 M€ ofprovisions, namely a total of 59.3 M€, as against 67.9 M€at the end of the previous financial year.3.1.2.Net balance 34.6 (58%)Investment subsidies 12.3 (21%)Provisions 12.4 (21%)3. Balance sheet analysisShort-term debts of 62.6 M€, as against 100.7 M€the previous year, comprise 16.6 M€ tax and socialdebts, 2.4 M€ advances on pending orders, 40.6 M€Analysis ofshort-term debts in M€Tax and social debts 16.6 (27%)Debts to suppliers 40.6 (64%)Sundry debts 5.4 (9%)debts to suppliers and 3 M€ sundry debts. The“suppliers” item has returned to an acceptable levelin comparison with 2003,which finished with accrualsof more than 70 M€. IRSN indeed achieved anhonourable level in the period taken to pay suppliersin 2004 and has progressively regularised its modeof operation with CEA, allowing a more natural paceof payment.This situation will reduce the cash reservesof the Institute, the weakness of which now requiresearly payment of the subsidy or recourse to externalfinancing (bank overdraft).3.2. Assets3.2.1.Tied-up assets at 50.1 M€, as against 47.9 M€ theprevious year, are itemised as a gross amount of88.8 M€ and depreciation of 39.7 M€.This weak variation in tied-up assets represents ageingequipment of the Institute and weakness in the currentlevel of investments. As a reminder, the researchreactors, which remain the property of CEA inaccordance with the Institute incorporation decree,therefore do not appear in the balance sheet, but aredirectly taken by the Institute as operating charges.6FINANCE LEDGER OF THE I R S N ANNUAL REPORT 2004

3.2.2.Current assets are 71.8 M€, as against 120.7 M€ theprevious financial year, and are made up as to 13.5 M€cash, 9.8 M€ advances on orders; client receivables arestable at 29.8 M€ and finally the balance of 18.7 M€being sundry receivables, mostly VAT. There was asignificant fall in cash reserves from 44.1 M€ at theend of 2003 to 13.5 M€ at the end of 2004 (see opposite).This is explained, apart from the financial year deficit,by the progressive regularisation of the relationship withCEA, of whom IRSN is one of its major customers.The2004 financial year therefore finished with workingcapital reduced to approximately 9 M€ as against 20 M€on 1 January.Current assets in M€Cash 13.5 (19%)Advances 9.8 (13,5%)Receivables 29.8 (41,5%)Sundry receivables 18.7 (26%)Details of assets in M€Fixed assets 50.1 (41%)Current assets 71.8 (59%)ConclusionApart from extraordinary items, 2004 was in strictconformity with the commitments undertaken byIRSN before the Board of Directors in observing fundamentalequilibrium in terms of results and effects onworking capital.The evolution of the balance sheet is contrasting whilethe head of the balance sheet has worsened dueto the strong dip in working capital, there isnonetheless a marked improvement at the end ofthe balance sheet, with the reduction in time takento pay suppliers, the result of progressive standardisationof the operation of the Institute.Extraordinary items have been partially compensatedby the improvement in financial income and a lowerthan forecast depreciation allowance, but the debitfrom working capital weakens the Institute’scapitalisation,and discussions are in progress withthe authorities in order to determine the procedureto be implemented for reinforcing the financialstanding of the Institute on a long-term basis.The change of tax system, with the application of aprorata VAT regime on 1 January 2005, will eliminateas from that date, all other things being equal, thebudget deficit resulting from the tax system set upduring the creation of the Institute.FINANCE LEDGER OF THE I R S N ANNUAL REPORT 20047

[ FINANCE LEDGER OF THE ANNUAL REPORT 2004 ]Profit & loss accountIncomeIncome (excluding tax) 2004 2003 2002 (10 months)Operating income 245,598,908.63 235,482,280.96 213,374,879.80Net total turnover 35,164,526.17 35,590,211.96 34,611,537.36Operating subsidies 206,681,399.76 198,098,871.94 178,524,198.90Write-backs on depreciation and provisions 80,417.64 20,504.32Transfers of charges 36,839.37 25,349.47 130,164.47Other income 3,635,725.69 1,747,343.27 108,979.07Financial income 1,446,579.93 1,018,763.58 1,203,877.45Other interest and equivalent income 8,710.77 0.00 31.94Financial write-backs on provisions and transfer of chargesPositive exchange differences 19,953.00 38,568.13 29,626.39Net income on sale of negotiable investment securities 1,417,916.16 980,195.45 1,174,219.12Extraordinary income 6,721,564.71 25,211,622.50 5,446.82Investment subsidies transferred to financial year profit & loss account 6,554,482.13 18,742,326.22 5,446.82Management operations 167,082.58 6,469,296.28 0.00TOTAL INCOME 253,767,053.27 261,712,667.04 214,584,204.07Debit balance = loss 6,045,350.60OVERALL TOTAL 259,812,403.87 261,712,667.04 214,584,204.07In euros (€)8FINANCE LEDGER OF THE I R S N ANNUAL REPORT 2004

ChargesCharges (excluding tax) 2004 2003 2002 (10 months)Operating charges 245,997,066.23 261,015,076.71 200,437,180.89Third-party consumption for financial year 158,454,902.47 182,831,266.23 171,834,080.29Tax, rates and equivalent payments 2,776,145.74 1,381,124.89 3,454,953.91Personnel charges 65,805,418.98 45,440,248.53 25,120,486.08Depreciation and provision allowances 17,771,491.98 28,404,363.46 0.00Other charges 1,189,107.06 2,958,073.60 27,660.61Financial charges 33,456.39 21,155.29 46,546.63Interest and equivalent charges 9,805.48 1,881.88 27,264.98Negative exchange differences 13,650.91 19,199.31 19,281.65Net charges on sale of negotiable investment securities 10,000.00 74.10Extraordinary charges 13,763,131.25 260,535.00 3,822.36Management operations 13,763,131.25 35.00 3,822.36Capital operations 500.00Depreciation and provision allowances 260,000.00Tax on profit 18,750.00 0.00 0.00Fixed annual taxation 18,750.00TOTAL CHARGES 259,812,403.87 261,296,767.00 200,487,549.88Credit balance = profit 415,900.04 14,096,654.19OVERALL TOTAL 259,812,403.87 261,712,667.04 214,584,204.07In euros (€)N.B.: The “personnel charges” item varies with the arrival of CEA employees opting for IRSN. This increase is compensated for by a decrease in “third-partyconsumption”.FINANCE LEDGER OF THE I R S N ANNUAL REPORT 20049

[ FINANCE LEDGER OF THE ANNUAL REPORT 2004 ]Balance sheetAssets2004 2003 2002Gross Depreciation Net Net Netand provisionsIntangible fixed assets 7,217,293.11 5,475,146.01 1,742,147.10 1,845,335.08 1,470,315.23Tangible fixed assets 80,366,590.83 33,176,186.78 47,190,404.05 45,435,018.48 13,251,907.41Financial fixed assets 1,196,078.27 1,196,078.27 635,212.81 - 7,092.29TIED-UP ASSETS 88,779,962.21 38,651,332.79 50,128,629.42 47,915,566.37 14,715,130.35Stock and work-in-progress 34,943.08Advances and deposits paid 9,824,069.06 9,824,069.06 7,758,726.96 27,572,585.76Operating receivablesClient receivables 29,970,112.77 143,207.83 29,826,904.94 28,178,006.45 35,551,849.76Other receivables 18,533,312.85 18,533,312.85 79,899,947.86 54,839,848.1448,503,425.62 143,207.83 48,360,217.79 108,077,954.31 90,391,697.90Sundry receivables 1,069.28 1,069.28 1,069.28Negotiable investment securities 10,938,217.44 10,938,217.44 33,680,806.20 47,177,335.17Liquid assets 2,565,411.71 2,565,411.71 10,370,525.94 348,995.30Prepaid charges 72,469.00 72,469.00 241,517.33CURRENT ASSETS 71,904,662.11 143,207.83 71,761,454.28 160,165,543.10 165,490,614.13OVERALL TOTAL 160,684,624.32 38,794,540.62 121,890,083.70 208,081,109.47 180,205,744.48In euros (€)N.B.: The 2002 balance sheet does not incorporate transfer of accounts from OPRI and IPSN.10FINANCE LEDGER OF THE I R S N ANNUAL REPORT 2004

Liabilities2004 2003 2002Shareholders’ equityAllocation 8,782,859.59 8,782,859.59Reserves 31,844,160.61 31,428,260.57Financial year result (profit or loss) - 6,045,350.60 415,900.04 14,096,654.19Net worth 34,581,669.60 40,627,020.20 14,096 654.19Investment subsidies 12,297,019.86 18,851,501.99TOTAL I 46,878,689.46 59,478,522.19 14,096,654.19Contingent liability provisionRisk provision 1,260,000.00 260,000.00Taxation provision 1,300,000.00Provision for charges 9,882,369.57 8,150,000.00TOTAL II 12,442,369.57 8,410,000.00 0.00DebtsFinancial debts 312.42 136,537.10 - 248,851.80Advances and deposits received 2,426,504.71 2,426,504.71 2,426,504.71Supplier debts 33,998,794.86 79,002,887.85 84,339,390.84Tax and social security debts 16,649,279.72 11,409,966.28 54,797,484.67Other 39,514,301.48Debts on fixed assets and related accounts 6,583,920.72 5,386,816.45 6,767,579.81Other debts 2,792,448.24 2,197,809.41 17,909,218.06Regularisation accountsDeferred income 117,764.00 117,764.00 117,764.00TOTAL III 62,569,024.67 140,192,587.28 166,109,090.29OVERALL TOTAL (I+II+III) 121,890,083.70 208,081,109.47 180,205,744.48In euros (€)N.B.: The 2002 balance sheet does not incorporate transfer of accounts from OPRI and IPSN.FINANCE LEDGER OF THE I R S N ANNUAL REPORT 200411

[ FINANCE LEDGER OF THE ANNUAL REPORT 2004 ]Intermediate management balances31/12/2004 31/12/2003 Variation %Joint financing and own receipts 35,164,526.17 35,590,211.96 - 425,685.79 -1.20 %Operating subsidies 206,681,399.76 198,098,871.94 8,582,527.82 4.33 %FINANCIAL YEAR PRODUCTION 241,845,925.93 233,689,083.90 8,156,842.03 3.49 %Third-party consumption 158,454,902.47 182,831,266.23 - 24,376,363.76 -1.33 %ADDED VALUE 83,391,023.46 50,857,817.67 32,533,205.79 63.97 %Taxes and rates 2,776,145.74 1,381,124.89 1,395,020.85 101.01 %Personnel charges 65,805,418.98 45,440,248.53 20,365,170.45 44.82 %GROSS OPERATING SURPLUS 14,809,458.74 4,036,444.25 10,773,014.49 266.89 %Write-backs, transfers of charges 117,257.01 45,853.79 71,403.22 15.72 %Other income 3,635,725.69 1,747,343.27 1,888,382.42 10.07 %Depreciation and provision allowances 17,771,491.98 28,404,363.46 - 10,632,871.48 - 37.43 %Write-backs on equipment subsidies 6,554,482.06 2,958,073.60 -1,768,966.54 - 59.80 %OPERATING CHARGES 6,156,324.53 - 6,790,469.53 12,946,794.06 -190.66 %Financial income 1,446,579.39 21,155.29 12,301.10 5.15 %CURRENT PRE-TAX RESULT 7,569,448.07 - 5,792,861.24 13,362,309.31 - 230.67 %Extraordinary income 167,082.58 6,469,296.28 -6,302,213.70 -97.42 %Extraordinary charges 13,763,131.25 260,535.00 13,502,596.25 5,182.64 %EXTRAORDINARY RESULT -13,596,048.67 6,208,761.28 -19,804,809.95 - 318.98 %Tax on profit 18,750.00 18,750.00 -FINANCIAL YEAR RESULT - 6,045,350.60 415,900.04 - 6,461,250.64 -1,553.56 %In euros (€)N.B.: The subsidy paid by MEDD has been withdrawn on financial year production.12FINANCE LEDGER OF THE I R S N ANNUAL REPORT 2004

Self-financing capacityCalculation from GOS 2004 2003 VariationSubtraction methodGross operating surplus 14,809,458.74 4,030,431.43 10,779,027.31+ transfer of operating charges 36,839.37 25,349.47 11,489.90+ other operating income 3,635,725.69 1,747,343.27 1,888,382.42- other operating charges 1,189,107.06 2,952,060.78 -1,762,953.72+ financial income (a) 1,446,579.93 1,018,763.58 427,816.35± proportion of result on joint operation 0.00 0.00 0.00- financial charges (b) 33,456.39 21,155.29 12,301.10+ extraordinary income ( c) 167,082.58 6,469,296.28 - 6,302,213.70- extraordinary charges (d) 13,763,131.25 535.00 13,762,596.25- tax on profit (if appropriate) 18,750.00 0.00 18,750.00SFC 5,091,241.61 10,317,432.96 - 5,226,191.35In euros (€)(a) excluding write backs on provisions(b) excluding allowances for depreciation and financial provisions(c) excluding - income from fixed asset sales- proportion of investment subsidies related to financial year result- depreciation neutralising (account 776)- write-backs on extraordinary provisions(d) excluding - book value of fixed assets sold- allowances for depreciation and extraordinary provisionsCalculation from net result 2004 2003 VariationAddition methodFinancial year net result - 6,045,350.60 415,900.04 - 6,461,250.64+ depreciation and provision allowances 17,771,491.98 28,664,363.46 -10,892,871.48- write-backs on provisions 80,417.64 20,504.32 59,913.32- net result on fixed asset sales 0.00 0.00 0.00- proportion of investment subsidies transferredto profit and loss account 6,554,482.13 18,742,326.22 -12,187,844.09- income from neutralising 0.00 0.00 0.00SFC 5,091,241.61 10,317,432.96 - 5,226,191.35In euros (€)FINANCE LEDGER OF THE I R S N ANNUAL REPORT 200413

[ FINANCE LEDGER OF THE ANNUAL REPORT 2004 ]Variation in liquid funds2003 2004 VariationCONTRIBUTIONS TO WORKING CAPITAL - - -WITHDRAWALS FROM WORKING CAPITAL - 3,211,987.17 - 10,838,704.97 - 7,626,717.80FLUCTUATIONS OVER PREVIOUS FINANCIAL YEAR 24,283,067.65 - - 24,283,067.65+ Variation in operational current assets - 1,755,813.10 - 57,807,437.60 - 56,051,624.50- Variation in operational debts - 9,209,719.90 - 79,279,081.03 - 70,069,361.13= Variation in operational working capital requirement 7,453,906.80 21,471,643.43 14,017,736.63+ Variation in other debit balances- Variation in other credit balances - 17,092,172.01 1,762,645.41 18,854,817.42= Variation in non-operational working capital requirement 17,092,172.01 - 1,762,645.41 - 18,854,817.42(1) + (2) = variation in working capital requirementor net redemption of working capital 24,546,078.81 19,708,998.02 - 4,837,080.79VARIATION IN LIQUID FUNDS - 3,474,998.33 - 30,547,702.99 - 27,072,704.66In euros (€)14FINANCE LEDGER OF THE I R S N ANNUAL REPORT 2004

Forecast and completion reconciliation2004 2004 VariationProfit & loss account Budget Actual Actual/BudgetINCOMESale of services 41,147,000.00 35,164,526.17 - 5,982,473.83Public subsidies (c/74) 204,627,000.00 206,681,399.76 2,054,399.76Other operating income 12,948,000.00 5,286,227.57 - 7,661,772.43Internal transactions 6,490,000.00 6,634,899.77 144,899.77TOTAL INCOME 265,212,000.00 253,767,053.27 -11,444,946.73CHARGESPersonnel charges 104,544,000.00 65,805,418.98 -38,738,581.02Other operating charges 144,147,000.00 176,235,492.91 32,088,492.91Internal transactions 15,600,000.00 17,771,491.98 2,171,491.98TOTAL CHARGES 264,291,000.00 259,812,403.87 - 4,478,596.13RESULT (PROFIT) 921,000.00 - 921,000.00RESULT (LOSS) 6,045,350.60 6,045,350.60TOTAL PROFIT & LOSS ACCOUNT BALANCE 265,212,000.00 259,812,403.87 - 5,399,596.13Transfer of result to SFC tableRESULT 921,000.00 - 6,045,350.60 - 6,966,350.60Depreciation provision allowances 15,600,000.00 17,771,491.98 2,171,491.98Proportion of subsidies transferred to result - 6,554,482.13 - 6,554,482.13Write-backs on depreciation and provisions - 6,490,000.00 - 80,417.64 6,409,582.36SELF-FINANCING CAPACITY 10,031,000.00 5,091,241.61 - 4,939,758.39Summary financing tableSELF-FINANCING CAPACITY 10,031,000.00 5,091,241.61 - 4,939,758.39Tangible and intangible fixed asset acquisitions - 17,165,000.00 - 15,261,954.13 1,903,045.87Financial fixed assets - 1,200,000.00 - 563,672.28 636,327.72Financial debt repayment - 132,000.00 - 136,224.68 - 4,224.68TOTAL APPROPRIATIONS - 18,497,000.00 - 15,961,851.09 2,535,148.91Public investment subsidies -Other resources (excluding internal transactions) 31,904.51 31,904.51TOTAL RESOURCES - 31,904.51 31,904.51CONTRIBUTIONS TO WORKING CAPITAL - 8,466,000.00 - 10,838,704.97 - 2,372,704.97In euros (€)FINANCE LEDGER OF THE I R S N ANNUAL REPORT 200415

Head office77-83, avenue du Général-de-Gaulle92140 Clamart – FranceTelephone+33 (0)1 58 35 88 88MailB.P. 17 - 92262 Fontenay-aux-Roses Cedex – FranceIRSN websitewww.irsn.org

IRSN sitesClamart (IRSN head office)77-83, avenue du Général-de-Gaulle92140 Clamart – FranceTel. +33 (0)1 58 35 88 88AgenB.P. 2747002 Agen CedexTel. +33 (0)5 53 48 01 60CadaracheB.P. 313115 Saint-Paul-lez-Durance CedexTel. +33 (0)4 42 19 91 00Fontenay-aux-RosesB.P. 1792262 Fontenay-aux-Roses CedexTel. +33 (0)1 58 35 88 88La Seyne-sur-MerZone portuaire BregaillonB.P. 33083507 La Seyne-sur-Mer CedexTel. +33 (0)4 94 30 48 29Le Vésinet31, rue de l'ÉcluseB.P. 3578116 Le VésinetTel. +33 (0)1 30 15 52 00Les Angles – Avignon550, rue de la Tramontane – Les AnglesB.P. 70 29530402 Villeneuve Avignon CedexTel. +33 (0)4 90 26 11 00Mahina (Tahiti)B.P. 519Tahiti Papeete, Polynésie françaiseTel. +33 (0)06 89 54 00 25Octeville – CherbourgRue Max-Pol FouchetB.P. 1050130 OctevilleTel. +33 (0)2 33 01 41 00OrsayBois-des-Rames (bât. 501)91400 OrsayTel. +33 (0)1 69 85 58 40PierrelatteB.P. 16626702 Pierrelatte CedexTel. +33 (0)4 75 50 40 00SaclayB.P. 6891192 Gif-sur-Yvette CedexTel. +33 (0)1 69 08 60 00

Head office77-83, avenue du Général-de-Gaulle92140 Clamart – FranceTelephone+33 (0)1 58 35 88 88MailB.P. 17 - 92262 Fontenay-aux-Roses Cedex – FranceIRSN websitewww.irsn.org