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CH04AD001 WAM--MM Transactions Oral Presentations and Posters V. 1st International Topical Meeting on Research Reactor Fuel Management February to 71997 Bruges, Belgium Organized by the European Nuclear Society European Nuclear Society Belpstrasse 23 P.O. Box 5032 CH-3001 Berne/Switzerland Phone Number: 41 31 32061 1 Fax Number: +41 31 3824466 RRFM'97 1st International Topical Meeting on Research Reactor Fuel Management Holiday Inn Crowne Plaza, Bruges, Belgium February 57, 1997 Organised by the European Nuclear Society in cooperation with the Belgian Nuclear Society anfjAe International Atomic Energy Agency Invited and ContributedP apers Oral and PosterP resentations RRFM'97 PROGRAM COMMITTEE Chairman: Jean-Louis Robert, CERCA, France Vladimir L. Afanasjev, Novosibirsk Chemical Concentrates Plant, Russia J.W. de Ves, Interfaculty Reactor Institute, The Netherlands Lucien Gilles, CEA CE Saclay, France Pol Gubel, SCK/CEN, Belgium Albert K. Panyushkin, Electrostal, Russia Matjaz Ravnik, Jozef Stefan Institute, Slovenia lain G. Ritchie, nternational Atomic Energy Agency, Austria Gerd Thamm, Research Centre Jillich, Germany David Thom, UKAEA, Great Britain Claude Vandenberg, Belgonucl6aire, Belgium Published by the European Nuclear Society (ENS) Belpstrasse 23, P.O. Box 5032, CH-3001 Berne (Switzerland) Phone: 41 31 320 61 11 Fax: 41 31 382 44 66 (NOEX Session 1: Research Reactors and Fissile Materials Supply Invited Papers Page The New German Research Reactor FRM-11 I A. Axmann, K. ning and M. Rottmann, TU Munich, Germany Reactor Jules Horowitz: A new material testing reactor project 4 F. Merchie, S. Frachet, P. Martel, B. Maugard and P. Raymond, CEA, France The current status and future trends in the use of Russian research reactors 5 N. Arkhangelsky, Ministry for Atomic Energy of the Russian Federation, Russia Supply of LEU and HEU for research reactors 8 H. MOller, NUKEM Nuklear GmbH, Germany Uranium supply and licensing progress at CERCA 1 2 G. Harbonnier, CERCA, France Recovery of uranium from manufacturing scraps and blending of recycled MTR uranium Is D. Skea and P. Cartwright, UKAEA, Great Britain Highly enriched uranium recycle and conversion facility at COGEMA Pierrelatte 21 S. Bouchardy and J.F. Pauty, COGEMA, France The Novosibirsk Chemical Concentrates plant as manufacturer of nuclear fuel and fissile materials for research reactors 26 V.L. Afanasiev, A.B. Aleksandrov, A.A. Yenin and G. G. Sidorenko Novosibirsk Chemical Concentrates Plant, Russia ContributedP apers The RERTR Program 29 A. Travelli, Argonne National Laboratory, USA Session 2 Fuel Fabrication Invited Papers Different types of research reactor plate fuel and their possible optimisation 35 J.-P. Durand, CERCA, France The manufacture of MTR fuel elements and Mo-99 production targets at Dounreay 39 J. Gibson, UKAEA, Great Britain ContfibutedP apers Development of very-high-density low-enriched uranium fuels 46 J.L. Snelgrove, G.L. Hofman, C.L. Trybus and T.C. Wiencek Argonne National Laboratory, USA TRIGA INTERNATIONAL -A new TRIGA fuel fabrication facility at CERCA 52 G. Harbonnier, CERCA, France Thermal compatibility in U-2wt.%Mo and U-10wt.Mo fuel prepared by centrifugal atornization for high density research reactor fuels 56 Ki-Hwan Kim, D.B. Lee, C.K. Kim and I.H. Kuk Korea Atomic Energy Research Institute, Republic of Korea Session 3 Reactor Operation and Fuel Safety Contributed Papers Requirements on fuel management for a safe and optimum operation of the German research reactor FRJ-2 60 R. Nabbi, H.J. Bormann, K. Koizlik and J. Wolters, Research Centre Jillich, Germany Fuel shuffling optimization for the Delft research reactor 65 R. van Geemert, A.J. Quist, J.E. Hoogenboon and H.P.M. Gibcus Delft University of Technology, The Netherlands Advanced fuel in the Budapest research reactor 70 1. Vidovszky and T. Hargitai, KFKI Atomic Energy Research Institute, Hungary BR2 mixed core management 74 B. Ponsard and A. Beekmans, CEN/SCK, Belgium Fuel management strategy for the new equilibrium, silicide core design of RSG Gas (MPR-30) 78 Liern Peng Hong, Bakri Arbie and T.M. Sembiring, National Atomic Energy Agency (Batan), Indonesia Theffnal hydraulic model validation for HOR mixed core fuel management 82 H.P.M. Gibcus, J.W. de Vries and P.F.A. de Leege, Delft University of Technology, The Netherlands Reactivity variations associated with the core expansion of the MARIA research reactor after modernisation 86 G. Krzysztoszek, Institute of Atomic Energy Research Reactor Centre, Poland OSIRIS: An example of gradual conversion 90 J. Guidez, Mr. Beylot and Mr. Joly, CEA, France Session 4 Back-end Options and Transportation Invited Papers MTR Spent Fuel Reprocessing -The Cogema Answer 94 P. de I'Epine, COGEMA, France Handling of spent fuel from research reactors in Japan 96 K. Kanda, Research Reactor Institute, Kyoto University, Japan Fuel transportation for research reactors 99 S. Hdrin, H. Libon and H. Sannen, TRANSNUBEL, Belgium ContributedP apers World-wide French experience in research reactor fuel cycle transportation 100 D. Raisonnier, TRANSNUCLEAIRE, France US foreign research reactor spent nuclear fuel return policy - status quo 104 G. Gruber, NUKEM, Germany Reprocessing of MTR fuel at Dounreay 108 N. Hough, UKAEA, Great Britain Current activities on improving storage conditions of the research reactor "RN' spentfuel 115 M. Matausek, Z. Vukadin, R. Pavlovic and N. Madnkovic Institute of Nuclear Siences "VINCA', Yugoslavia Dry vault for spent fuel depository - basic outsets, operating results and safety of the "CASCAD" plant 119 P. Bardelle, CEA, France Dry storage experiment with spent materials testing reactor fuel elements 123 K. Kroth, H. BrOcher and F. Kreutz, Research Centre Alich, Germany Behavior of spent aluminum cladded metallic uranium fuel in concentrated salt brines 127 J. Fachinger, H. BrOcher and H. Rainer, Research Centre Alich, Germany Pbsters Page 1. Isotope c(234U)/c(235U) relation in PIK reactor fuel elements 131 K. Konoplev, P.A. Sushkov, D.V. Tchmshkyan, G.Ja. Vasiliev and A.S. Zakharov St. Petersburg Nuclear Physics Institute, Russia 2. Non-destructive control of cladding thickness of fuel elements for research reactors 134 Y. Karlov, Y. Zhukov and S. Chashchin, Novosibirsk Chemical Concentrates Plant, Russia 3. Improved HOR fuel managent by flux measurement data feedback 137 J.E. Hoogenboom, LV. Serov, P.F.A. Leege, H.P.M. Gibcus Delft University of Technology, The Netherlands 4. Core management, operational limits conditions and safety aspects of the Australian high flux reactor (HIFAR) 141 S. L.T own, HIFAR, ANSTO, Australia S. In-core fuel management practice in HANARO 145 Hark Rho Kim, Choong Sung Lee and Ji Bok Lee Korea Atomic Energy Research Institute, Republic of Korea 6. Operation of the FRG research reactors at Geesthacht 149 A. Reymann and W. Krull, GKSS Research Centre, Germany 7. Calculations of fuel element bum-up for mixed TRIGA core 153 M. Ravnik, T. Zagar and A. Persic, Institute 'Jozef Stefan", Slovenia 8. Some aspects of accidental criticality safety of TRIGA reactor spent fuel pool 157 M. Logar, B. Blumac and M. Ravnik, University of Maribor, Slovenia 9. The IR-8 reactor operation 161 E.P. Ryazantsev, P.M. Egorenkov and A.F. Yashin, RCC Kurchatov Institute, Russia 10. Fuel and fuel cycle of the SM-2 reactor 165 V.B. Ivanov, A.V. Klinov, V.A. Kuprienko and V.A. Tsykanov Research Institute of Atomic Reactors, Russia 11. Design and experience of HEU and LEU fuel for WWR-M reactor 168 AX Erykalov, A.A. Enin, A.S. Zakharov, V.S. Zvezdkin, G.A. Kirsanov, K.A. Konoplev, V.S. Uvov, Yu.V. Petrov and Yu.P. Saikov, St. Petersburg Nuclear Physics Institute, Russia 12. Lead-shielded spent fuel transport casks - The thermal switch concept 172 R. Bera and C. Bochard, ROBATEL, France 13. Experiences from operation, shut down and dismantlement of the MTR research reactor SAPHIR 174 E.H. Lehmann, R. Christen, J. Hammer and H. Heyck, Paul-Scherrer-institute, Switzerland 14. Concepts for the interim storage of spent fuel elements from research reactors in the Federal Republic of Germany 178 D. Niephaus, P. Quassdorff, S. PAtzer and D. Bensch, Research Centre JOlich, Germany 15. The reprocessing of irradiated MTR fuel and the nuclear material accountancy - Dounreay, UKAEA 182 T.R. Barrett and R. Harrison, UKAEA, Great Britain 16. An analysis of burnup reactivity credit for reactor RA spent fuel storage 188 M.J. Milosevic and M.P. Pesic, Institute of Nuclear Sciences'VINCA' 17. Defuelling of the UTR-300 research reactor (video) 192 R.D. Scoft, H.M. Banford, BW East, M.A. Ord and A.P. Gaffka Scottish Universities Research and Reactor Centre, Great Britain