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UNDERKRITICITETSEXPERIMENT Två stora subkriticitetsexperiment har varit i fokus under 2005: "Yalina-Booster subcritical experiment" i Minsk "SAD experiment" i Dubna Det nya experimentella programmet vid Yalina-Booster startades under hösten 2005 med en sofistikerad 2-zons-härd: en snabb-neutron-zon och en termisk-neutron-zon. Ett antal experiment har utförts vi anläggningen: "Reaction rates" för olika detektorer vid olika positioner i härden. Mätningar med en pulsad neutronkälla (PNS). "Source jerk"-mätningar (SJ) Brusmätningar Mätningar av neutronflödet vid utkanten av den aktiva härden. Experimenten var framgångsrika trots vissa tekniska brister. Förbättringar av systemet är planerade och förberedda. KTH förberedde ett forskningsprogram för 2005-2006 koordinerat av IAEA, med fokus på Yalina-experiment. Ett integrationsprogram för Yalina-experimenten och det europeiska projektet EUROTRANS har förberetts och implementeras. SAD-experimentet fick stora svårigheter 2005 pga en brand i acceleratorbyggnaden. Samtidigt med återuppbyggnaden av acceleratorn så har ett experimentellt program planerats där SAD-experimentet integreras i EUROTRANS-projektet, under "Domain 2: Experimental Coupling of Accelerator, Spallation Target and Subcritical Core (ECATS)” , se Appendix 15. DYNAMIK OCH KINETIK I ADS Studier av dynamik och kinetik för ADS tillsammans med källeffektivitetsstudier har sammanfattats i två doktorsavhandlingar av Marcus Ericsson (Appendix 8) respektive Per Seltborg (Appendix 9). Några huvudsakliga slutsatser är: Underkritisk drift av reaktorer innebär, i sig själv, en distinkt ökade säkerhet i jämförelse med kritiska reaktorer. Anledningen är en hög stabilitet under drift och ökade marginaler vid insättning av positiv reaktivitet. För ett uranfritt bränsle baserat på aktinider så försämras några viktiga säkerhetsparametrar. En analys av detta visar att användning av sådant bränsle i en kritisk reaktor vore mycket svårgenomförbart. Studier av transienter indikerar att bly-vismuth-kylda reaktorer kan klara sig trots den låga andelen fördröjda neutroner och den höga voidreaktiviteten som aktinidbränslet medför, men eventuellt är en negativ prompt feedback nödvändig för att kompensera den svaga Dopplereffekten vid en prompt kriticitetstransient. 10 Trots att bly-vismuth har en hög kokpunkt så visar dessa studier på vikten av att ha ett lågt värde på voidreaktiviteten. Transientstudierna identifierar ett molybdenbaserat metall-keram-bränsle (CerMet) med goda inbyggda säkerhetsegenskaper. Ett större pinnavstånd föreslås som ett sätt att undvika mekaniska skador vid kylmedelsförlust.
Detaljerade analyser av neutronkinetik och termohydralik visar att punktkinetikapproximationen är tillräcklig även för mycket noggranna transientberäkningar för underkritiska system. Resultaten visar på bättre noggrannhet vid låga keffektiv-värden en effekt av den reducerade känsligheten för störningar i systemets reaktivitet i ett underkritiskt tillstånd. Detta ger en mycket liten spatial störning. En studie av protonbestrålningens tillförlitlighet visade att många avbrott inträffar som en följd av problem med acceleratorn. Det är uppenbart att en stor förbättring i denna tillförlitlighet är nödvändig. KÄLLEFFEKTIVITETSSTUDIER FÖR ADS Ett nytt sätt att beskriva proton-käll-effektiviteten, Ψ*, har utvecklats vid KTH under de senaste åren för att kunna studera energiutbytet för en ADS. Ψ* har studerats för ett antal ADS-modeller. Ψ* definieras i analogi med neutron-käll-effektiviteten, ϕ*, men relaterar härdeffekten direkt till protonkällan, istället för till källneutronerna. Huvudfördelen med Ψ*, istället för den vanligare neutroneffektiviteten, ϕ*, är att sättet som man definierar den externa källan är entydigt, och att Ψ* är proportionell mot energiutbytet. Ψ* beskrivet som en funktion av olika systemparametrar ger en grund för ADS-design med optimala egenskaper för att få en hög härdeffekt i förhållande till stråleffekten. Som ett exempel ser man att Ψ* minskar avsevärt med ökande spallationstargetradie (se Appendix 9). För ett gaskylt system så kan vi sammanfatta: Americium som introduceras i bränslet, i en subkritisk härd, minskar Ψ*. I en härd med americiumbaserat bränsle, så är Ψ* ca 10% lägre än i en MOXbaserad härd. Ψ* minskar med ytterligare 10% när helium byts ut mot LBE. Båda dessa effekter beror på det starka beroendet mellan fission och infångningstvärsnitt på den neutronenergin i 1 Mev-området i jämna N-nuklider, och på ett litet energiskift i detta beroende på tvärsnitten mellan nukliderna. KÄRNBRÄNSLECYKELSTUDIER Studier av bränslecykler vid KTH är starkt kopplade till det europeiska projektet RED- IMPACT, koordinerat av KTH, och har fokuserat på ett hypotetiskt svenskt scenario. För att göra dessa studier har nya, avancerade simuleringsverktyg utvecklats, och fortsätter att förbättras kontinuerligt. Jämviktsstudier har utförts, och visar att fyra ADSreaktorer, med 800 MWt var, är tillräckligt för att bränna en mängd plutonium och americium som motsvarar den uppbyggda mängden av dessa isotoper i den svenska reaktorparken med en installerad kapacitet på ca 10 GWe. Studierna visar att plutoniuminventariet kunde reduceras mer genom MOX-återcykling i lättvattenreaktorer före användningen av ADS, men med nackdelen av en något försämrad americiumutbränning. I ett detaljerat svenskt scenario så har ett antal möjligheter behandlats: Att skicka det använda bränslet som det är till ett bränsleförvar för permanent förvar och övervakning (Utfasningsscenario) Att starta om ett antal BWR- och PWR-enheter för att bränna/transmutera existerande plutonium och/eller aktinider i form av bland-oxid- bränsle (MOX). 11
Page 1 and 2: System and safety studies of accele
Page 3 and 4: Preface The research on safety of A
Page 5 and 6: coolant fraction allows for decay h
Page 7 and 8: To dispose the spent fuel as it is
Page 9: SAMMANFATTNING Resultaten från for
Page 13 and 14: Modellering av de termo-kemiska ege
Page 15 and 16: LIST OF APPENDICES 1. Carl-Magnus P
Page 17 and 18: ABBREVIATIONS AND ACRONYMS EUROPEAN
Page 19 and 20: FCC Face Centered Cubic - type of a
Page 21 and 22: 1 SYSTEM AND SAFETY STUDIES OF ADS
Page 23 and 24: pin. The full core void worth was c
Page 25 and 26: Figure 2.1 The 1180-loading of Yali
Page 27 and 28: Counts Counts 10 5 10 4 10 3 10 2 1
Page 29 and 30: Figure 2.4 Ion source interruption
Page 31 and 32: New 1 g 232 Th, 238 U (ultra pure)
Page 33 and 34: 3.1.2 System descriptions The PDS-X
Page 35 and 36: 4 NUCLEAR FUEL CYCLE ANALYSIS 4.1 E
Page 37 and 38: will be calculated using MCB, the M
Page 39 and 40: irradiation, the spent fuel assembl
Page 41 and 42: 4.1.3 Results The calculations has
Page 43 and 44: 4.2 ANALYSIS OF THE SWEDISH NUCLEAR
Page 45 and 46: Mass [tons] 300 250 200 150 100 50
Page 47 and 48: 5 POTENTIAL OF REACTOR BASED TRANSM
Page 49 and 50: due to a partial insertion, the inf
Page 51 and 52: irradiation to maintain the core as
Page 53 and 54: configuration allowed the reactor t
Page 55 and 56: 6.2 THERMOCHEMISTRY OF ADVANCED FUE
Page 57 and 58: Figure 7.1 Positions of Cr atoms in
Page 59 and 60: 8 DEVELOPMENT OF CODES AND METHODS
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Let us assume the neutron flux is p
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waste repository notes which year t
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9 INTERNATIONAL INTERACTIONS, SEMIN
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Janne Wallenius Oct 2005 Participat
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[11] Sylvie Pillon and Janne Wallen
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Nuclear Instruments and Methods in
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376 fraction, beff, have been calcu
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378 Fig. 3. Fit of exponentials to
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380 Table 6 Experimental estimation
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382 dominating closer to criticalit
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12th International Conference on Em
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2.2 Yalina Booster Yalina and Yalin
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Yalina and Yalina Booster Λ 1 ⎛
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Yalina and Yalina Booster Table III
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Yalina and Yalina Booster 7 REFEREN
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1720 A. Talamo, W. Gudowski / Annal
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Journal of NUCLEAR SCIENCE and TECH
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1042 A. TALAMO and W. GUDOWSKI Tabl
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1046 A. TALAMO and W. GUDOWSKI 237
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1048 A. TALAMO and W. GUDOWSKI 1) 2
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1052 A. TALAMO and W. GUDOWSKI IX.
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Abstract Annals of Nuclear Energy 3
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Table 1 Technical data of the power
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Abstract Technical note Managing th
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86 A. Talamo / Annals of Nuclear En
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Westlén and Wallenius HEAT REMOVAL
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Accelerator-driven Systems: Safety
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Abstract The accelerator-driven sys
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Acknowledgements I owe thanks to ma
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“A grad student in procrastinatio
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specify the meaning of the term “
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that three fast breeder reactors (F
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emitting properties and its relativ
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TABLE 8 Effective dose coefficients
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Fig. 1 Radiotoxic inventory of the
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prior to disposal. The most commonl
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often used in repository safety ana
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separations process is also known a
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Spent Fuel U Pu PUREX FP + An Np Tc
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Fig. 6 Schematic picture of the pyr
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From the viewpoint of reducing the
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Chapter 3: Transmutation Strategies
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from reprocessing is sent into stor
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adiotoxicity in the spent fuel afte
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In order to overcome the safety iss
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79 Se (T1/2=6.5·10 4 years) and 12
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Source multiplication in a subcriti
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given by the source multiplication
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Fig. 16 Delayed neutron spectra vs.
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offers low void worths. For tight l
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smaller than classical MOX-fuel sur
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Responsiveness of the ADS The kinet
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Fig. 19 compares the response in a
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design parameters. The reference co
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indefinitely. The burst limit is ap
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maintain the reactor in the subcrit
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value (-$18.5), the power increases
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() β ( ) Λ () dck t k t = p t −
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(a) (b) (c) (d) Fig. 25 Source over
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Accelerator reliability In accelera
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Conclusions The thesis analysed and
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Appendix A: Reactor Kinetics Equati
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The definition of F(t) is: ρ () t
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Bibliography 1 R. G. Cochran and N.
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38 M. Bunn, S. Fetter, J. P. Holdre
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75 R. J. Puigh and M. L. Hamilton,
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74 Paper I
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chemical reactions. An “inherentl
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temperature with irradiation time e
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and compressible pool volumes with
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comparison, the FFTF reactor, which
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CerMet and nitride. The reason is t
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failure, which leaves small safety
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XII.B. Transient results The result
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programme,” Nucl. Sci. Eng., Acce
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277, American Nuclear Society, LaGr
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Neutronics of minor actinide burnin
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TABLE I: Fuel Doppler constant KD (
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nitric acid. Therefore, we may not
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(e.g. SS316) on the other hand have
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FIG. 4: Example of core map with 24
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TABLE X: BOL temperature coefficien
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[18] M.A. Smith, E.E. Morris, and R
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76 Paper III
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II. REACTOR KINETICS EQUATIONS In t
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The model pertains to an accelerato
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V.A. Variations in Source Strength
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TABLE VI Calculations of the core c
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pressure, starting at t=1 sec. The
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14. R. E. ALCOUFFE, F. W. BRINKLEY,
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Safety Analysis of Na and Pb-Bi Coo
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Neutronics analysis Table 1. Design
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stoichiometric oxide fuel. The fuel
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4000 3500 3000 2500 2000 Peak fuel
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Figure 7. Sodium (left) and lead/bi
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78 Paper V
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1690 M. Eriksson, J.E. Cahalan / An
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RELIABILITY ASSESSMENT OF THE LANSC
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calculations are based on operation
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Figure 3 is interesting in that sen
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The database is for practical reaso
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Failure analysis Analysis of failur
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Source efficiency and high-energy n
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Abstract Transmutation of plutonium
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The following papers are not includ
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ERALIB1 ERAnos LIBrary ERANOS Europ
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TRU TRansUranic elements TRUEX TRan
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Contents 1 Introduction 1 2 Transmu
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Chapter 1 Introduction The growing
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objectives of the present thesis ha
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n+ 238U → 239U + γ → 239Np + e
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natural uranium is typically needed
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ate step when an even-N nuclide is
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the atomic mass of a specific eleme
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χ (Ε) 0.4 0.3 0.2 0.1 0.0 0 1 2 3
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UOX- LWR 1. Once-through 2. Pu-burn
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2.2.4 Radiotoxicity reduction The t
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onstrated that recovery yields of 9
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advantage, thanks to the radiation
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As was mentioned earlier, a fast ne
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3.3 Coolant options Since the neutr
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3.4.1 Heavy liquid metal target Two
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In a single spallation reaction, ab
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for this purpose, since it allows f
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technical reasons. One is that larg
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concepts, developed by different EU
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Evaluated Nuclear Data Libraries (e
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SATURNE experiments that the Bertin
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4. Number of neutrons appearing as
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The eigenfunctions of hermitian ope
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( , , ) + ∫∫∫ Φ ( , , ) =
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ks FˆΦ FˆΦ = = AˆΦFˆΦ + S ,
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S Fˆ Φ AˆΦ − FˆΦ AˆΦ 1−
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the second-step calculation. This i
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⎛1−kˆ eff ⎞ FΦ ψ * = ⎜
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Moreover, replacing ϕ * ⋅ Z by
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6.3.3 Varying the target radius Bot
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6.3.4 Required proton beam current
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multiplication process from the ext
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Three sub-critical configurations,
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have energy close to 14.1 MeV. Howe
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and can from this point of view be
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1.E+00 Neutron flux (normalised) 10
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7.2.3 Distribution of the spallatio
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equal or slightly larger than 1, wh
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eactivity indicator can be obtained
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Chapter 8 The Yalina experiments In
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8.2 Dynamic experiments performed a
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fundamental decay rate, determined
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ρ n1 − n0 = β n eff 1 . (64) Th
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for this is the fluctuations of the
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above the bottom of the active part
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perimental results. Experience from
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Core power [kW] 300 200 100 0 0 0.9
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29). As expected, it appears that t
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ficients together with the specific
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personnel is 12 µSv/h. However, pr
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High-energy contribution As was sho
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Fig. 46. Vertical cross-sectional v
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there is a fraction of leakage neut
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ψ∗/Ep 40 30 20 10 0 Energy gain
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ψ∗ 40 30 20 10 ZrN matrix YN mat
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Table 20. Proton source efficiency,
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Fig. 56. Horizontal cross-sectional
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Chapter 11 Abstracts of papers 11.1
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11.5 Paper V Different reactivity d
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source response have been investiga
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Table A2. Production facts for oper
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Eq. (B.5) expresses the energy prod
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Table C1 (cont.) Neutrons Photons P
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13 R. Soule, “Neutronic Studies i
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45 H. A. Abderrahim, P. Kuoschus, M
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78 F. Atchison, Proc. of a Speciali
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108 I. Koprivnikar, E. Schachinger,
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The basic idea of ADS is to supply
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equilibrium (Prael, 1998) Models ar
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two dips in the neutron fluxes caus
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4.3 Calculations of ϕ* for the MUS
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Instead of plotting the ratio ϕ* /
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have already been multiplied in the
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APPENDIX A Table 3 Material Composi
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Definition and Application of Proto
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is the best way to define the neutr
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TABLE I Relative Fraction of Actini
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compared to 0.8% for r=50 cm). When
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Proton Source Efficiency ψ * 40 30
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16. L. S. WATERS, “MCNPX TM User
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314 spallation reactions. The produ
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316 current of3.0 mA (1.9 10 13 pro
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318 between 0.1 and 10 MeV, while m
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320 would be very thin, only the un
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322 Relative effective dose 1.E+01
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324 12 mSv h 1 , which is about 15
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326 originates from neutrons with e
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328 [17] Internal SAD document at t
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affecting ψ* - the macroscopic fis
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nected to an increase in ψ*. Preli
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fission and capture cross-sections
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Relative fission probability, σf/(
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F φ >=< Fφ > + < Fφ > + < Fφ >
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tions. Three parameters - the avera
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Nuclear Instruments and Methods in
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fraction, beff, have been calculate
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satisfactory statistical agreement,
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and combining the values of a obtai
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dominating closer to criticality, t
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Abstract Elsevier Science 1 Journal
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adjusted to give a keff close to 0.
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Elsevier Science 5 f Σ Σ c Core F
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Table 6 shows how the differences i
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Transmutation of nuclear waste in g
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ii Abstract The actinides in spent
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iv VI D. Westlén, J. Cetnar and W.
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vi MONJU Japanese experimental fast
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viii CONTENTS 6.5 Summary of the se
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2 CHAPTER 1. BURDENING FUTURE GENER
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10 CHAPTER 2. NUCLEAR REACTIONS Fig
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12 CHAPTER 2. NUCLEAR REACTIONS Fig
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14 CHAPTER 3. FAST REACTORS Reactor
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16 CHAPTER 3. FAST REACTORS reactor
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18 CHAPTER 3. FAST REACTORS Generat
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20 CHAPTER 3. FAST REACTORS Two ent
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22 CHAPTER 3. FAST REACTORS a liqui
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24 CHAPTER 4. PARTITIONING AND TRAN
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34 CHAPTER 5. FAST SUB-CRITICAL COR
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48 CHAPTER 6. DESIGNING A GAS-COOLE
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Bibliography [1] T. Ginsburg. Die f
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[29] G. Melese-d’Hospital. Perfor
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[58] L.A. Lys et al. Gas turbine po
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Acknowledgements Even though my wor
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PROOF COPY [LY8910B] 088545PRB OLSS
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£ ¤¥¦ §¨¨© ¡¢ ¨§¨ ¢¦
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List of Papers I. J. Wallenius, P.
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Chapter 1 Introduction About 16% of
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Figure 1.1: The length and time sca
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2.2. Primary Damage: Vacancies and
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2.2. Primary Damage: Vacancies and
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2.3. Primary Damage Evolution 9 the
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2.3. Primary Damage Evolution 11 20
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2.3. Primary Damage Evolution 13 Im
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3.1. Ab Initio 15 The problem is ad
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3.2. Interatomic Potentials 17 wher
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3.2. Interatomic Potentials 19 3.2.
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3.3. Molecular Dynamics 21 be of th
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3.4. The Monte Carlo Method 23 sele
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4.1. Potential Construction 25 func
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4.2. Verification of Potentials 27
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4.2. Verification of Potentials 29
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4.3. Cascades Using Molecular Dynam
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Chapter 5 Summary and Outlook Befor
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Bibliography [1] http://www.iaea.or
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Bibliography 37 [24] P. Olsson, J.
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Modeling of chromium precipitation
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MODELING OF CHROMIUM PRECIPITATION
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etween EAM and FS type of potential
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leaving other properties untouched.
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1. Introduction Displacement cascad
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(BCA) study [44], to correlate with
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correspondence with the maximum num
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however, that only above 20 keV can
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As explained in what follows, Figs.
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4.2 Clustered fraction While the st
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metals, for example, it has been sh
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Acknowledgements This work required
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[52] W.J. Phytian, A.J.E. Foreman,
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Table 2 - Summary of recoil energie
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Figure captions Figure 1 - Fe-Fe pa
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Number of FP at peak time cascade d
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Number of sub-cascades 4 3 2 1 0 Fi
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SIA clustered fraction Vacancy clus
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SIA clustered fraction Vacancy clus
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* Corresponding author, phone #: +3
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time and the different mechanisms o
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[35]. The use of a large distance c
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SIA clusters have been counted both
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and depleted in SIAs. Isolated vaca
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Figure 3 shows the number of recomb
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potentials predict between 30% and
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To summarize, we expect to see the
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properties. But while in the latter
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[24] H.-E. Schaefer, K. Maier, M. W
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fraction 0.5 0.4 0.3 0.2 0.1 Contri
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Number of defects 20 15 10 5 SIA cl
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Abstract This study is a first step
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Abbreviations ADS Accelerator-drive
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9 ADS and MOX Transmutation Strateg
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Important technological assumptions
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2 Generating nuclear power Fission
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coolants are low neutron capture cr
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steam-generators and other equipmen
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3.3 Conversion At the conversion fa
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3.5.2 Uranium oxide (UOX) The urani
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Table 1. Main elements present in s
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Fig. 4. Fission product yield as fu
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corresponding radioactive decay hal
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4 Swedish Spent Fuel Storage and Di
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Fig. 6. Swedish nuclear waste manag
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handling spent fuel at CLAB. It als
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Secondly it performs an operation o
Page 809 and 810:
6 Nuclear Fuel Cycles studied in th
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7 Advanced Nuclear Fuel Cycles sele
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8 Characterization of the ADS Conce
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9 ADS and MOX Transmutation Strateg
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10.2 Scenario II - LWR + ADS Stabil
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ecycling in Scenario III resulted i
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12 Results - Phase-Out Scenarios 12
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the time of shut-down only 7 tons o
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LWR-park which is doomed to be phas
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22. Working Party on the Physics of
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nuclear power reactor under normal
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fission in LWRs and other reactors
Page 833 and 834:
238 U microscopic cross sections [b
Page 835 and 836:
Appendix B - Transmutation of Nucle
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In a fast neutron spectrum the neut
Page 839 and 840:
understood it is important to exami
Page 841 and 842:
Elsevier Science 1 From Once-throug
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Phase-out Reference Scenario The ph
Page 845 and 846:
varied from 1800 to 3300 [MWt] depe
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plutonium in the system 4 though, w
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Elsevier Science 1 The Subcritical
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3. Subcritical assembly The sub-cri
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6. Conclusion The SAD project is in
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2 2. Key parameters of SAD and supp
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4 Fig. 5 Distributions of the 210 P
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O FFICE PARLEMENTAIRE D ’ ÉVALUA
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Nouvelles Les recherches technologi
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OPECST,Public Hearing, January 20,
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Some pre-declarations for this talk
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Pu can be pretty efficiently (but s
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Page 886:
I am leaving conclusions to the Hon
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