Research Reactor Fuel Management 1 (RRFM 1997)

216 Pages·4.702 MB·English

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: [phone]
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: [phone] Fax: [phone]
(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