Annual Report 2009/2010 - JUWEL - Forschungszentrum Jülich

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3.8.1 Product Quality Control of Radioactive Waste – High Level Waste from Reprocessing High-level radioactive waste requires specific care and attention for its very long-term and high radiotoxic potential. No decision on a conceivable “direct disposal” path for merely untreated high-level waste has yet been made in Germany. However, spent fuel dissolution for reprocessing has been employed until 2005, and still today residual vitrification methods are being used for the appropriate conditioning of high level waste from spent fuel of German nuclear power plants. The expected result of nuclear waste product quality control is that all radioactive waste residues can be disposed of safely over a very long period of time. This is achieved by threefold tasks of the PKS-WAA team: 1.) Waste conditioning process qualification: to assess and evaluate the production processes applied to produce waste residues compliant with the officially approved waste properties and repository acceptance criteria. 2.) Production process inspection and manufacturer’s auditing: to make sure that all production is performed orderly within the production process guidelines and that only conform waste packages compliant with the well-defined product properties and repository acceptance criteria are being produced and prepared for their final disposal in Germany. 3.) Documentation checking: to assess all the documentation to accompany the waste residue packages and to check if all nuclear inventory declarations are correct, comprehensive and complete. The PKS-WAA team, which are currently three scientists, two engineers, a Ph.D student and a project assistant, reports directly and solely to the authority in charge, the Federal Office for Radiation Protection (BfS). All reprocessing and vitrification of high-level waste residues and proportionate conditioning of the by-products are conformed in fully quality assured production processes at the reprocessing sites in La Hague in France, Sellafield in the UK and a domestic site at the WAK in Karlsruhe. Fig. 11: Left: Documentation to verify the repository relevant properties. Right: Containers filled with vitrified and compacted waste. Contact: Dr. Holger Tietze-Jaensch h.tietze@fz-juelich.de 21
3.8.2 Product Quality Control of Low and Intermediate Level Radioactive Waste (LAW/MAW) Radioactive waste products and waste packages have to be in compliance with the technical acceptance requirements for mine KONRAD. Repository-relevant features, radionuclide inventories and related activities as well as container parameters have to be documented and are checked by the independent experts of PKS-I. LAW / MAW arises from nuclear power production, nuclear industry, research, medicine and technology as well as from the dismantling of nuclear installations. Accordingly, conducting a thorough and competent control and evaluation demands integrated competence in various scientific and engineering special fields. Often various technical details, complex issues and inter-relations as well as vast quantities of data have to be understood, analyzed, checked and evaluated by PKS-I. The results are summarized in written expert opinions and evaluation reports. In executing its tasks as a Federal expert group the PKS-I in many ways is corresponding with waste producers, waste conditioning or interim storage facilities and nuclear companies, as well as nuclear licensing and supervisory authorities or government ministries of the individual German Federal States. Concerning the incineration of German LAW the control activities of PKS-I are not only limited to domestic plants but also include audits or inspections in foreign facilities, at present in France and Belgium and forthcoming in USA. Moreover, many radioactive isotopes or sealed sources used in Germany have been produced in the former Soviet Union. To be able to evaluate the completeness or reliability of corresponding waste declarations PKS-I maintains close links also to Russian organizations, in particular to Rosatom, JSC Isotop, and SIA ’RADON’ (Moscow). As a multidisciplinary group PKS-I in <strong>2010</strong> consisted of six scientists and engineers assisted by one office administrator. The lean management organization of PKS-I is divided into two areas of activity focusing either on “conditioning process qualification and documentation” or on “nuclear technology, nuclear reactors and computation”. They are planned to be gradually completed by additional experts. Fig. 12: Left: KONRAD repository. Middle: Container for KONRAD. Right: Quality control plan. Contact: Dr. Hans-Jürgen Steinmetz h.j.steinmetz@fz-juelich.de 22
Page 1 and 2: Mitglied Mitglied der der Helmholtz
Page 4 and 5: Forschungszentrum Jülich GmbH Inst
Page 6 and 7: TABLE OF CONTENTS 1 Preface .......
Page 8: 6.2.2 Doctoral Thesis .............
Page 11 and 12: state of NRW. The collaborative pro
Page 13 and 14: 2 Institute’s Profile Due to the
Page 15 and 16: 2.2. Organization chart Reactor Saf
Page 17 and 18: 3 Key Research Topics 3.1. Long Ter
Page 19 and 20: actinide co-conversion into polyact
Page 21 and 22: Fig. 7: Non-destructive analytical
Page 23 and 24: Fig. 9: Thermal treatment of an AVR
Page 25: 3.8. Product Quality Control of Rad
Page 29 and 30: The advantage of working at low vac
Page 31 and 32: NdPO 4 powder sample, directly rece
Page 33 and 34: 4.5. Non-destructive assay testing
Page 35 and 36: 5 Scientific and Technical Reports
Page 37 and 38: Results and Discussion The irradiat
Page 39 and 40: work will focus on the identificati
Page 41 and 42: Different solvents (iso-propanol an
Page 43 and 44: e & j) Aggregates of aluminium oxid
Page 45 and 46: Experimental details The corrosion
Page 47 and 48: Intensity [CPS] 500 400 300 200 100
Page 49 and 50: Fig. 24: Left: High resolution TEM
Page 51 and 52: a) MD model [10] b) Derived Lesukit
Page 53 and 54: 5.4. Minor actinide(III) recovery f
Page 55 and 56: Extensive extraction studies were p
Page 57 and 58: of the extraction properties of the
Page 59 and 60: Cm(III) together with the lanthanid
Page 61 and 62: using a mixture of CyMe4BTBP and TO
Page 63 and 64: A more challenging route studied wi
Page 65 and 66: These preliminary results show that
Page 67 and 68: The 1-cycle SANEX process is intend
Page 69 and 70: Continuous counter-current tests us
Page 71 and 72: Conclusion In this work, it was sho
Page 73 and 74: shaken by a vortex mixer for 15 min
Page 75 and 76: 100 100 Distribution ratio 10 1 0.1
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Tab. 15: The distribution ratios of
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5.7. Synthesis and thermal treatmen
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Acid-Deficient Uranyl-Nitrate via d
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Optical investigation showed a noti
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TG /% 100 98 96 94 92 90 88 86 84 8
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Radiolysis in the aqueous solutions
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is about 4% while the one of the rh
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Fig. 59: Compressibility curve for
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Conclusion and outlook Monazite-typ
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Fig. 63: Description of the unit ce
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agents for the synthesis of neodymi
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100 TG 785°C Exo DSC 0,2 0,0 90 -0
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After synthesis the product was cen
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process of monazite and additional
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Tab. 18: Lattice parameters determi
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Conclusions For Sm 1-x Ce x PO 4 mo
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5.11. Raman Spectra of Synthetic Ra
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The numerical values of all measure
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knowledge, these special relationsh
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Fig. 80: Raman spectra of LaPO 4 ir
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5.12. MC simulation of thermal neut
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content was replaced by hydrogen. C
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constant for hydrogen concentration
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with a 0 1 -183.88 ± 8.55 and a 2
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5.13. An Improved Method for the no
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2 2 2 d0 R ds d0 dw la( )
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The relative uncertainty for the ac
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In the drum, 4 ‘hot spots’ for
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activity of Cs-137 is much more und
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gamma-ray detector approximated by
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shown in Fig. 96. In both cases the
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econstruction than the old calculat
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Neutron capture cross sections and
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Outlook The evaluated data will be
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from carbon-based HTR fuel elements
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Fig. 102: 3D volume reconstructions
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dislocate the 14 C atom from its pr
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It can be seen that nearly all trit
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Acknowledgement The authors like to
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development by investigations of ga
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Fig. 109: The left picture shows th
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[2] A European Roadmap for Developi
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from airborne SWIR Full Spectrum Im
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Fig. 113: Visualization of the vege
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number of training samples up to 19
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Acknowledgements The work presented
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three approaches has severe drawbac
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neighbours from the list of merge c
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it gives a difference in segmentati
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[6] I. Niemeyer, F. Bachmann, A. Jo
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Monitoring 3 cooperated intensively
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facilities and other treaty related
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parameters of the SAR system, such
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The MGD products used in the study
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Fig. 134 contains the result for th
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[2] H. Maître (ed.), Processing of
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Preparatory Committee to allocate t
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unconditional security assurances f
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safeguards was also requested. Deci
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[16] United Nations Security Counci
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5.24. Development and Application o
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Hardware layer The hardware layer i
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So in most applications the scale u
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The ENDF-B/V and ENDF-B/VI librarie
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5.26. Product control of waste prod
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Polysiloxane which has been investi
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acceptance requirements [3]. In the
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Fig. 145: List of description and d
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6.1. Courses taught at universities
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Umwelt / Energy & Environment 2010;
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6.5. Institute Seminar The IEK-6 or
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6.5.3 Invited talks 2009 30.04.2009
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21.09.2010 Dr. N. Evans: The Chemis
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8 Selected R&D projects 8.1. EU pro
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K. Aymanns: Nominated as deputy re
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Bukaemskiy A.A., Barrier D., Modolo
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11.2. Publications 2009 11.2.1 Jour
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Rezniczek, A.; Richter, B.; Jussofi
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Daniels, H.: Co-conversion of actin
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11.3. Publications 2010 11.3.1 Jour
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Sypula, M.; Wilden, A.; Schreinemac
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(Partitioning) - Stabilitätsunters
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Modolo, G.; Bosbach, D.; Geist, A.;
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12 How to reach us Postal Address F
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By train: Take the train from Aache
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Schriften des Forschungszentrums J
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