Research Reactor Fuel Management 6 (RRFM 2002)

246 Pages·15.803 MB·English

CH0300000
Transactions
Oral Presentations and Posters
NN
6th International Topical Meeting on
Research Reactor Fuel Management
March 17 to 20, 2002, Ghent, Belgium
Organised by the European Nuclear Society
European Nuclear Society
Belpstrasse 23
P. 0 Box 5032
CH-3001 Berne/Switzerland
PhoneNumber: 41582866111
Fax Number: [phone]
E-mail: rrfm2OO2(cid:1)to.aey.ch
http://www.euronuclear.org/meetings
N/ Ct-1 -
LU,
RRFM 2002
6th International Topical Meeting on
Research Reactor Fuel Management
Cultural Center of Ghent University'Het Pand',
Ghent, Belgium
March 17-20, 2002
Organised by the European Nuclear Society
in cooperation with the International Atomic Energy Agency
Invited and ContributedP apers
Oral and PosterP resentations
RRFM 2002 PROGRAM COMMITTEE
Chairman: Pol Gubel, SCK/CEN Mol, Belgium
Vladimir L. Afanasjev, Novosibirsk CCP, Russia
Philip A. Beeley, HMS Sultan, United Kingdom
Andr6 Chabre, CEA Saclay, France
Gunter Damm, Research Centre JG]ich, Germany
Jobl Guidez, EC Joint Research Center Petten, The Netherlands
Hans MOller, RWE NUKEM, Germany
lain G. Ritchie, International Atomic Energy Agency, Austria
Klaus Al Usta, CERCA, France
IstvAn Vidovszky, KFK1 Atomic Energy Research Institute, Hungary
Jacob W. de Vries, Interfaculty Reactor Institute Delft, The Netherlands
Published by the European Nuclear Society (ENS)
Belpstrasse 23, P.O. Box 5032, CH-3001 Berne (Switzerland)
Phone: [phone] Fax: [phone]
INDEX
Session 1: Fissile materials supply Page
Past and present Supply of enriched Uranium for Research Reactors in the European 1
Union
H. MOIler, RWE NUKEM GrnbH, Germany
A new Standard Specification for Uranium Metal intended for Research Reactor Fuel 4
Fabrication
J. Laucht, RWE NUKEM GmbH, Germany
The revised IAEA Regulations and their Impact on the Transport of Research 8
Reactor Fuel
R. Christ, F. Hilbert and M. KObel, NCS GmbH, Germany
Session 2 Fuel development, qualification,
fabrication and licensing
RERTR Progress in MO-99 Production from LEU (Invited Paper) 11
G.F. Vandegrift, C. Conner, S. Aase, A. Bakel, D. Bowers, E. Freiberg,
A. Gelis, K.J. Quigley, and J.L. Snelgrove, Argonne National Laboratory, USA
An Update on the LEU Target Development and Conversion Program 1 8
for the Maple Reactors and new Processing Facility (invited Paper)
G.R. Malkoske, MIDS Nordion, Canada
Experimental Irradiation of UMo Fuel: Pie Results and Modeling of Fuel Behaviour 26
A. Languille, D. Plancq, F. Huet, B. Guigon, CEA Cadarache, France; P. Lemoine,
P. Sacristan, CEA Saclay, France; G. Hofman, J. Snelgrove, J. Rest, S. Hayes, M. Meyer,
Argonne National Laboratory, USA; H. Vacelet, CERCA Framatome, France;
E. Leborgne, Technicatome, France; G. Dassel, NRG Petten, The Netherlands
Status as of March 2002 of the Wo Development Program 33
JIVI. Harny, Framatome-ANP; A. Languille, B. Guigon, CEA, Cadarache; P. Lemoine, CEA Saclay;
C. Jarousse, CERCA, Framatome-ANP; M. Boyard, Technicatome; JL. Emin, COGEMA; France
Advances and Highlights of the CNEA Qualification Program as High Density Fuel 40
Manufacturer for Research Reactors
P. Adelfang, L. Alvarez, N. Boero, R. Calabrese, P. Echenique, M. Markiewicz, E. Pasqualini,
G. Ruggirello and H. Taboada, Comisi6n Nacional de Energfa At6mica (CNEA), Argentina
Status of the Qualification Program for atomized U-Mo Dispersion Rod Type Fuel in Korea 45
C.K. Kim, K.H. Kim, J.M. Park, D.S. Sohn, Fuel Design Technology Development Dept.,
K.H. Lee, H.T. Chae, HANARO Center, Korea Atomic Energy Research Institute, Korea
Progress in Development of Low-Enriched U-Mo Dispersion Fuels 50
G.L. Hofman and J.L. Snelgrove, Argonne National Laboratory, Argonne, USA
S.L. Hayes and M.K. Meyer, Argonne National Laboratory, Idaho Falls, USA
MTR Fuel Plate Qualification Capabilities at SCK-CEN .59
E. Koonen, P. Jacquet, SCK-CEN, Belgium
Session 3 Reactor operation, fuel safety and core conversion
Progress of the RERTR Program in 2001 (invited Paper) 63
A. Travelli, Argonne National Laboratory, USA
Progress of the Russian RERTR Program: Development of new-type Fuel Elements 69
for Russian-built Research Reactors (invited Paper)
A.V. Vatulin, Y.A. Stetskiy, V.A. Mishunin, V.B. Suprun, I.V. Dobrikova, VNIINM, Russia
Use of Highly Enriched Uranium at the FRM-11 (invited Paper) 73
K. 136ning, Technische Universitdt MOnchen, Germany
Characteristic Differences of LEU and HEU Cores at the German FRJ-2 Research Reactor 78
R. Nabbi, J. Wolters and G. Damm, Research Center JOlich, Germany
A preliminary Study on the Suitability of High Density LEU Fuel Elements to maintain 83
BR2 Reactor Operational Characteristics
A. Beeckmans and E. Koonen, SCK-CEN, Belgium
Behaviour of UMo with Cladding Failure UMUS test in the HFR 88
J. Guidez, S. Casalta, JRC Petten, The Netherlands;
F.J. Wijtsma, G. Dassel, P.M.J. Thijssen, NRG Petten, The Netherlands;
C. Jarousse, CERCA Framatome, France; A. Languille, CEA Cadarache, France
Best Safety Practices for the Operation of Research Reactors 93
H. B6ck, M. Villa, Atominstitute of the Austrian Universities, Austria
Session 4 Spent fuel management, corrosion and degradation
Influence of the Fuel operational Parameters on the Aluminium Cladding Quality 99
of Discharged Fuel
S. Chwaszczewski, W. Czajkowski, E. Borek-Kruszewska, Institute of Atomic Energy, Poland
MIR Reactor Fuel Assemblies Operating Experience 104
A.F. Grachev, A.L. lzhutov, A.E. Novosyolov, M.N. Svyatkin, Z.1. Chechetkina, V.V. Aleksandrov,
State Scientific Centre of Russia Research Institute of Atomic Reactors, Russia
New Storage Mode for spent Fuel at the Budapest Research Reactor 109
T. Hargitai, 1.V idovszky, KFKI Atomic Energy Research Institute, Hungary
Storage, Inspection and SIP Testing of spent nuclear fuel from the HIFAR 114
Materials Test Reactor
H. Selwyn, R. Finlay, P. Bull and A. Irwin, ANSTO, Australia
Session 5: Back-end options and transportation
Progress of the United States Foreign Research Reactor spent Nuclear Fuel Acceptance 119
Program (invited Paper)
D.G. Huizenga, M. Clapper, U.S. Department of Energy and A.W. Thrower, Science Applications
International Corporation, USA
Management of the Acceptance Process of RTR Aluminide Type Spent Fuel 123
P. Auzi6re, J. Thomasson, COGEMA, France
Development of Melt Dilute Technology for Disposition of Aluminium based 132
spent Nuclear Fuel
W.F. Swift, Westinghouse Savannah River Company, USA
Spent Fuel Management Plans for the FiR 1 Reactor 136
S.E.J. Salmenhaara, Technical Research Centre of Finland, Finland
The Russian Federation Legislation. The new Laws. Prospects for International Cooperation. 13SI
A.Ye. Lebedev, Tenex, Russia
Posters
1 In-Reactor Behaviour of centrifugally atomized U3S! Dispersion Fuel 145
irradiated up to high burn-up for HANARO
K.H. Kim, D.G. Park, C.S. Lee, S.J. Oh, C.K. Kim,
Korea Atomic Energy Research Institute, Korea -
2 Boro Silicate Glass: The proven Conditioning of RTR Ultimate Waste 150
0. Bartagnon and V. Petitjean, COGEMA, France
3 Consortium NCS/GNS: Disposal of spent Nuclear Fuel from the DKFZ 155
(Heidelberg, Germany)
R. Vallentin, GNS; B. JOnger, DKFZ; T. Schmidt, NCS, Germany
4 U.S. Spent Nuclear Fuel Acceptance Policy 2006 and beyond 160
J. Edlow and K.R. Brown, Edlow International Company, USA
5 MR-6 Type Fuel Elements cooling in natural Convection Conditions after 165
the Reactor shut down
K. Pytel, W. Bykowski, A. Moldysz, Institute of Atomic Energy, Poland
6 Encapsulation Technology of MR6 spent Fuel and Quality Analysis of the EK-10 170
and WWR-SM spent Fuel stored more than 30 years in wet Conditions
E. Borek-Kruszewska, W. Bykowski, S. Chwaszczewski, W. Czajkowski, M. Madry,
Institute of Atomic Energy, Poland
7 Study on HANARO Core Conversion using U-Mo Fuel 175
K.H. Lee, C.S. Lee, C.G. Seo, SJ Park and H. Kim, Research Reactor Analysis Dept., and
C.K. Kim, Fuel Design Techn. Devel. Dept., Korea Atomic Energy Research Institute, Korea
8 Study on possibly Usage of 36 or 20 % enriched U02 TWR-S Fuel Type at 179
RB Heavy Water Critical Assembly
M. Pesic, N. Dasic and V. jubenov, The VINCA Institute of Nuclear Sciences, Yugoslavia
9 Powder Production of U-Mo Alloy, HIVID Process (Hydriding-Milling-Dehydriding) 183
E.E. Pasqualini, J. Helzel Garcfa, M. L6pez, E. Cabanillas and P. Adelfang,
Comisi6n Nacional de Energfa At6mica, Argentina
1 0 Improvements in irradiated Fuel Handling at Dhruva for enhanced Safety 188
H. Gujar and S. Agarwal, Dhruva, Bhabha Atomic Research Centre, India
1 1 Examination of U-9 % Mo Alloy Powder Microstructure in its initial Condition 193
and after Fuel Pin Fabrication
R.Kh. Gibadullin, A.D. Karpin, Yu.M. Pevchikh, V.V. Popov, V.N. Sugonyaev, V.M. Troyanov,
Institute for Physics and Power Engineering, Russia
12 Study of in-Reactor Creep in the Alloys employed as Structural Materials 197
for Research Reactor Core Components and Fuel Pins
M.G. Bulkanov, A.S. Kruglov, Yu.M. Pevchikh, V.V. Popov, V.M. Troyanov,
Institute for Physics and Power Engineering, Russia
13 Management and Inspection of Integrity of spent Fuel from IRT Mephi Research Reactor
V.G. Aden, S.Yu. Bulkin, A.V. Sokolov, Research and Development Institute of Power 201
Engineering, and A.V. Bushuev, A.F. Redkin, A.A. Portnov, Moscow State Engineering
Physics Institute -Technical University, Russia
14 Monte Carlo Simulation of Irradiation of IVITR Fuel Plates in the BR2 Reactor 206
using a full-scale 3-D Model with inclined Channels
V.V. Kuzminov, E. Koonen and B. Ponsard, SCK-CEN, Belgium
15 Neutronic Design of the RSG-Gas'Silicide Core 211
T.M. Sembiring, 1. Kuntoro, and H. Hastowo, BATAN, Indonesia
16 Spent Fuel Management and Site exploitation at IFIN-HH, Bucharest-Magurele 216
C.A. Dragolici, A. Zorliu, C. Petran and 1. Mincu, National Institute of Research and
Development for Physics and Nuclear Engineering'Horia Hulubei' IFIN-HH, Romania
17 Fuel Management Optimization for the WWR-M Research Reactor in Kiev 221
Y.P. Mahlers, Institute for Nuclear Research, Ukraine

Session
Fissile materials supply