Research Reactor Fuel Management 1 (RRFM 1997)

دسته بندی: انرژی
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تعداد صفحات: 216 
زبان: English 
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قیمت کتاب (تومان) : 54,000

European Nuclear Society, 1997. — 216 p.
1st International Topical Meeting on Research Reactor Fuel Management February 5 to 7 1997 Bruges, Belgium. Contents Session 1: Research Reactors and Fissile Materials Supply The New German Research Reactor FRM-11 A. Axmann, K. ning and M. Rottmann, TU Munich, Germany
Reactor Jules Horowitz: A new material testing reactor project 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 N. Arkhangelsky, Ministry for Atomic Energy of the Russian Federation, Russia
Supply of LEU and HEU for research reactors H. Moller, NUKEM Nuklear GmbH, Germany
Uranium supply and licensing progress at CERCA G. Harbonnier, CERCA, France
Recovery of uranium from manufacturing scraps and blending of recycled MTR uranium D. Skea and P. Cartwright, UKAEA, Great Britain
Highly enriched uranium recycle and conversion facility at COGEMA Pierrelatte S. Bouchardy and J.F. Pauty, COGEMA, France
The Novosibirsk Chemical Concentrates plant as manufacturer of nuclear fuel and fissile
materials for research reactors V.L. Afanasiev, A.B. Aleksandrov, A.A. Yenin and G. G. Sidorenko Novosibirsk Chemical Concentrates Plant, Russia
The RERTR Program A. Travelli, Argonne National Laboratory, USA Session 2 Fuel Fabrication Different types of research reactor plate fuel and their possible optimisation J.-P. Durand, CERCA, France
The manufacture of MTR fuel elements and Mo-99 production targets at Dounreay J. Gibson, UKAEA, Great Britain
Development of very-high-density low-enriched uranium fuels 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 G. Harbonnier, CERCA, France
Thermal compatibility in U-2wt.%Mo and U-10wt. Mo fuel prepared by centrifugal
atomization for high density research reactor fuels 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 Requirements on fuel management for a safe and optimum operation of the German research reactor FRJ-2 R. Nabbi, H.J. Bormann, K. Koizlik and J. Wolters, Research Centre Jillich, Germany
Fuel shuffling optimization for the Delft research reactor 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 I. Vidovszky and T. Hargitai, KFKI Atomic Energy Research Institute, Hungary
BR2 mixed core management B. Ponsard and A. Beekmans, CEN/SCK, Belgium
Fuel management strategy for the new equilibrium, silicide core design of RSG Gas (MPR-30) Liern Peng Hong, Bakri Arbie and T.M. Sembiring, National Atomic Energy Agency (Batan), Indonesia
Thermal hydraulic model validation for HOR mixed core fuel management 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 G. Krzysztoszek, Institute of Atomic Energy Research Reactor Centre, Poland
OSIRIS: An example of gradual conversion J. Guidez, Mr. Beylot and Mr. Joly, CEA, France Session 4 Back-end Options and Transportation MTR Spent Fuel Reprocessing - The Cogema Answer P. de I'Epine, COGEMA, France
Handling of spent fuel from research reactors in Japan K. Kanda, Research Reactor Institute, Kyoto University, Japan
Fuel transportation for research reactors S. Hdrin, H. Libon and H. Sannen, TRANSNUBEL, Belgium
World-wide French experience in research reactor fuel cycle transportation D. Raisonnier, TRANSNUCLEAIRE, France
US foreign research reactor spent nuclear fuel return policy - status quo G. Gruber, NUKEM, Germany
Reprocessing of MTR fuel at Dounreay N. Hough, UKAEA, Great Britain
Current activities on improving storage conditions of the research reactor "RN' spent fuel 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 K. Kroth, H. BrOcher and F. Kreutz, Research Centre Alich, Germany
Behavior of spent aluminum cladded metallic uranium fuel in concentrated salt brines J. Fachinger, H. Brocher and H. Rainer, Research Centre Alich, Germany Posters Isotope c(234U)/c(235U) relation in PIK reactor fuel elements K. Konoplev, P.A. Sushkov, D.V. Tchmshkyan, G.Ja. Vasiliev and A.S. Zakharov St. Petersburg Nuclear Physics Institute, Russia
Non-destructive control of cladding thickness of fuel elements for research reactors Y. Karlov, Y. Zhukov and S. Chashchin, Novosibirsk Chemical Concentrates Plant, Russia
Improved HOR fuel managent by flux measurement data feedback J.E. Hoogenboom, LV. Serov, P.F.A. Leege, H.P.M. Gibcus Delft University of Technology, The Netherlands
Core management, operational limits conditions and safety aspects of the Australian high flux reactor (HIFAR) S. L. Town, HIFAR, ANSTO, Australia
In-core fuel management practice in HANARO Hark Rho Kim, Choong Sung Lee and Ji Bok Lee
Korea Atomic Energy Research Institute, Republic of Korea
Operation of the FRG research reactors at Geesthacht A. Reymann and W. Krull, GKSS Research Centre, Germany
Calculations of fuel element bum-up for mixed TRIGA core M. Ravnik, T. Zagar and A. Persic, Institute 'Jozef Stefan", Slovenia
Some aspects of accidental criticality safety of TRIGA reactor spent fuel pool M. Logar, B. Blumac and M. Ravnik, University of Maribor, Slovenia
The IR-8 reactor operation E.P. Ryazantsev, P.M. Egorenkov and A.F. Yashin, RCC Kurchatov Institute, Russia
Fuel and fuel cycle of the SM-2 reactor V.B. Ivanov, A.V. Klinov, V.A. Kuprienko and V.A. Tsykanov Research Institute of Atomic Reactors, Russia
Design and experience of HEU and LEU fuel for WWR-M reactor 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
Lead-shielded spent fuel transport casks - The thermal switch concept R. Bera and C. Bochard, ROBATEL, France
Experiences from operation, shut down and dismantlement of the MTR research reactor SAPHIR E.H. Lehmann, R. Christen, J. Hammer and H. Heyck, Paul-Scherrer-institute, Switzerland
Concepts for the interim storage of spent fuel elements from research reactors in the Federal Republic of Germany D. Niephaus, P. Quassdorff, S. PAtzer and D. Bensch, Research Centre JOlich, Germany
The reprocessing of irradiated MTR fuel and the nuclear material accountancy - Dounreay, UKAEA T.R. Barrett and R. Harrison, UKAEA, Great Britain
An analysis of burnup reactivity credit for reactor RA spent fuel storage M.J. Milosevic and M.P. Pesic, Institute of Nuclear Sciences 'VINCA'
Defuelling of the UTR-300 research reactor (video) R.D. Scoft, H.M. Banford, BW East, M.A. Ord and A.P. Gaffka Scottish Universities Research and Reactor Centre, Great Britain