Annual Report 2009/2010 - JUWEL - Forschungszentrum Jülich

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TABLE OF CONTENTS 1 Preface ............................................................................................................................ 5 2 Institute’s Profile .............................................................................................................. 8 2.1. Staff ......................................................................................................................... 9 2.2. Organization chart ..................................................................................................10 2.3. Budget ....................................................................................................................11 3 Key Research Topics......................................................................................................12 3.1. Long Term Safety of Nuclear Waste Disposal .........................................................12 3.2. Innovative Nuclear Waste Management Strategies.................................................13 3.3. Structure Research .................................................................................................14 3.4. Characterisation of Nuclear Waste .........................................................................15 3.5. Transmutation .........................................................................................................16 3.6. Nuclear Waste Treatment .......................................................................................17 3.7. Nuclear Safeguards ................................................................................................18 3.8. Product Quality Control of Radioactive Waste & Packages .....................................20 3.8.1 Product Quality Control of Radioactive Waste – High Level Waste from Reprocessing ................................................................................................................21 3.8.2 Product Quality Control of Low and Intermediate Level Radioactive Waste (LAW/MAW) ..................................................................................................................22 4 Facilities .........................................................................................................................23 4.1. Electron Microscopy ...............................................................................................23 4.2. Raman spectroscopy ..............................................................................................25 4.3. X-ray diffraction analysis .........................................................................................26 4.4. Hot Cell Facility, GHZ .............................................................................................27 4.5. Non-destructive assay testing .................................................................................28 4.6. Radiochemical analytics .........................................................................................29 4.7. Miscellaneous .........................................................................................................29 5 Scientific and Technical Reports 2009/2010 ...................................................................30 5.1. Radionuclide release from research reactor fuel .....................................................30 5.2. Separation and enrichment of secondary phases of research reactor fuel elements and identification by SEM-EDX ...............................................................................35 5.3. XRD-analysis of secondary phases formed under final repository conditions due to corrosion of UAl x -Al research reactor fuel elements ................................................39 5.4. Minor actinide(III) recovery from high active waste solutions using innovative partitioning processes .............................................................................................48 1
5.5. 1-cycle SANEX process development studies and lab-scale demonstrations for the direct recovery of trivalent actinides from PUREX raffinate .....................................57 5.6. Innovative SANEX process for actinide(III) separation from PUREX raffinate using TODGA-based solvents ..........................................................................................67 5.7. Synthesis and thermal treatment of uranium-based microspheres through internal gelation ...................................................................................................................74 5.8. Conditioning of Minor Actinides in Monazite-type Ceramics ....................................83 5.9. Synthesis and characterization of ZrO 2 based ceramics for innovative nuclear waste strategies ................................................................................................................89 5.10. Synthesis and Characterization of Sm 1-x Ce x PO 4 Ceramics used for Nuclear Waste Management ...........................................................................................................95 5.11. Raman Spectra of Synthetic Rare Earth Orthophosphates ................................... 104 5.12. MC simulation of thermal neutron flux of large samples irradiated by 14 MeV neutrons ............................................................................................................... 112 5.13. An Improved Method for the non-destructive Characterization of Radioactive Waste by Gamma Scanning ............................................................................................ 120 5.14. Reconstruction of the Activity of Point Sources for the Accurate Characterization of Nuclear Waste Drums by Segmented Gamma Scanning ...................................... 129 5.15. Prompt Gamma Characterization of Actinides ...................................................... 135 5.16. Treatment and disposal of irradiated graphite and other carbonaceous waste ...... 139 5.17. Advanced Gas-cooled Accelerator-driven Transmutation Experiment – AGATE ... 149 5.18. Monitoring Uranium Mining and Processing Sites: Some Findings from an Airborne Hyperspectral Survey of Uranium Mining Legacies under Rehabilitation .............. 155 5.19. Multiresolution segmentation adapted for object-based change detection ............ 163 5.20. Nuclear Safeguards and Non-proliferation Issues in GMES .................................. 171 5.21. Use of TerraSAR-X Imagery for Geological Repositories Monitoring .................... 175 5.22. The NPT Review Conference 2010: Perspectives for International Safeguards .... 183 5.23. 2009-2010 annual report of PKS-WAA ................................................................. 191 5.24. Development and Application of a Beowulf Cluster for Nuclear Simulation ........... 192 5.25. 2009-2010 annual report of PKS-I ........................................................................ 199 5.26. Product control of waste products with new coating materials .............................. 200 5.27. Challenges in Compliance with the Waste Acceptance Requirements for the KONRAD Mine ..................................................................................................... 203 6 Education and training activities ................................................................................... 207 6.1. Courses taught at universities by IEK-6 staff......................................................... 208 6.2. Graduates ............................................................................................................. 209 6.2.1 Diploma/Master Thesis .................................................................................. 209 2
Page 1 and 2: Mitglied Mitglied der der Helmholtz
Page 4 and 5: Forschungszentrum Jülich GmbH Inst
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 and 26: 3.8. Product Quality Control of Rad
Page 27 and 28: 3.8.2 Product Quality Control of Lo
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
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of the extraction properties of the
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Cm(III) together with the lanthanid
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using a mixture of CyMe4BTBP and TO
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A more challenging route studied wi
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These preliminary results show that
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The 1-cycle SANEX process is intend
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Continuous counter-current tests us
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Conclusion In this work, it was sho
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shaken by a vortex mixer for 15 min
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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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Annual Report 2009/2010 - JUWEL - Forschungszentrum Jülich

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