European Nuclear Society, 2003. — 258 p.
7th International Topical Meeting on Research Reactor Fuel Management March 9 to 12, 2003, Aix-en-Provence, FranceInternational topics and educationUS Department of Energy research reactor initiatives in support of global nuclear non-proliferation, nuclear security and nuclear safety D. G. Huizenga, M. Clapper, D. Newton
Future needs for materials test reactors in Europe (FEUNMARR Findings) C. Vitanza, D. Iracane, D. Parrat
Russian Research Reactor Fuel returns to the Russian Federation T. Dedik, I. Bolshinsky, S. Oehlbert, A. S. Krass
Research reactor education and training B. Gless, P. Chanteux
The situation of the nuclear engineering education in Europe H. Böck, M. Villa, M. HajekFuel development, qualification, fabrication and licensingQualification and licensing of U-Mo fuels J. L. Snelgrove, P. Lemoine, P. Adelfang, N. Arkhangelsky
Validation of the conditions and safety of the in-pile tests of high-density low enrichment fuel for research reactors V. A. Starkov, V. V. Pimenov, N. G. Gataullin, V. E. Fedoseev, Yu. B. Chertkov,
A. V. Vatulin, I. V. Dobrikova, G. V. Kulakov
Efforts to overcome the failure occurred in rod type U-Mo fuel irradiation test for HANARO in KAERI
C. K. Kim, K. H. Kim, J. M. Park, D. S. Sohn
Progress in post-irradiation examination and analysis of low-enriched U-Mo research reactor fuels G. L. Hofman, J. L. Snelgrove, S. L. Hayes, M. K. Meyer, C.R. Clark
Status as of March 2003 of the UMo development program J. M. Hamy, F. Huet, B. Guigon, P. Lemoine, C. Jarousse, M. Boyard, J. L. Emin
CERCA UMo Development - Status as of March 2003 C. Jarousse, J. P. Durand, Y. Lavastre, M. Grasse
Status of CNEA qualification programs for the fabrication of high density MTR plate type fuel elements P. Adelfang, L. Alvarez, P. Echenique, E. Paqualini, G. Ruggirello
Manufacturing of Uranium High Density Fuel elements using Uranium 73 % U 235 enriched, in an aluminide alloy for the BR2 reactor Th. Pin, Y. Lavastre, J. L. Falgoux, P. Gubel, F. Joppen
Manufacturing and licensing of a lead test assembly for the R2 reactor J. P. Durand, F. Obadia, Ch. Jarousse, Y. Lavastre, M Grasse, J. L. Falgoux, U. Lindelöw
The UMUS failure: Facts and analysis F. Huet, B. Guigon, P. Lemoine, C. Jarousse, F. Wijtsma, G. Dassel, G. Hofman, J. SnelgroveReactor operation, fuel safety and core conversionAcceleration of the RERTR program: Scope, status and plans J. R. Phillips, A. Travelli
Performance of the WWR-M research reactor in the Ukraine with a mixed-fuel core Y. P. Mahlers
Experimental capabilities of the MIR reactor for testing and qualification of research reactors fuel A. F. Grachev, A. L. Ijoutov, A. L. Malkov, A. E. Novoselov, M. N. Svyatkin, V. A. Starkov, V. A. Ovchinnikov,
Upgrading the HOR: An upgrading study for the HOR H. P. M. Gibcus, P. F. A. de Leege, F. Labohm, J. W. de Vries,J. Valko, W. Feltes, J. Heinecke
On-line monitoring of local irradiation conditions in BR2 L. Vermeeren, V. Kuzminov, B. Coupé, E. Koonen, B. Ponsard
Behaviour of uranium-zirconium hydride fuel under reactivity initiated accident conditions H. Sasajima, T. Sugiyama, T. Nakamura, T. Fuketa, H. Uetsuka
Fuel in-core management and safety at SAFARI-1 A. J. D'Arcy
Consequence of using LEU fuel on the effectiveness of the absorber system of the German FRJ-2 research reactor R. Nabbi, G. Damm, A. Ellinger
A new research reactor for Australia T. Irwin
Computational analysis of the stressed-strained state and performance of research reactor fuel pins with detachment of fuel from cladding V. V. Popov, M. Ya. Khmelevsky
Localised fast neutron flux enhancement for damage experiments in a research reactor F. Malouch, V. Mastrangelo, A. Alberman, X. Wohleber, H. Carcreff
Fuel performance evaluation for ADS MYRRHA V. Sobolev, S. Lemehov, H. Ait Abderrahim
MCNP/HELIOS system for the HANARO research reactor using the table lookup method C. G. Seo, S. J. Park, C. S. Lee, H. Kim
High accuracy sensor for online measurement of the internal fuel rod pressure during irradiation experiments J-F. Villard, G. Lemaitre, J-M. Chaussy, F. Lefevre
Development of a cost-effective, reliable but disposable camera for fuel element inspection underwater at a low power research reactor S. Franklin, S. Velez-Moss, D. Bond, N. Morris
Enhancement of local fast flux in axis of standard BR2 fuel element S. Kaltcheva, E. Koonen
Inventory Reporting using OSCAR-3 F. Reitsma, C. C. Stoker, A. L.Graham
Performance of the LEU fuel and use of higher 235U loading in the Pakistan Research Reactor-1 (PARR-1) fuel M. ArshadSpent fuel management, back-end options, transportationDraft Edlow Group proposal for extension of DOE FRR SNF acceptance program J. Edlow
Dry storage of BR3 spent fuel in the Castor BR3® Cask L. Ooms, V. Massaut, L. Noynaert, M. Braeckeveldt, G. Geenen
U.S. spent fuel transportation security in the post 9/11 world T. Shelton, R. Boyd, C. Anne
A look ahead - an evaluation of the adequacy of the transportation infrastructure to handle potential returns for the balance of the FRR program T. Shelton, R. Boyd, J. Patterson, C. Anne
Return to the Russian Federation of irradiated fuel assemblies from the Institute of Nuclear Physics, Republic of Uzbekistan A. Ye. Lebedev
The test rig for inspection of spent fuel assemblies of research reactors of the State Scientific Center of the Russian Federation Research Institute of Atomic Reactors A. F. Grachev, A. S. Ladzin, V. V. Konyashov, V. V. Maklakov, R. N. Fitagdinov, Yu. V. Chechetkin, L. Satkoviak
A new generation in the family of packages for transportation J-L. Mondanel
Transport and storage casks for irradiated fuel assemblies from research reactors K. H. J. Dreesen, T. Schmidt
The leaking RTR aluminide spent fuel management - La Hague reprocessing plant flexibility P. Auziere, P. Gubel
Transportation for reprocessing of the spent nuclear fuel (SNF) of TVR ITEP research reactor and proposals for SNF management plans for the RA reactor V. G. Aden, S. Yu. Bulkin, A. V. Sokolov, Ye. B. Volkov, V. N. Konev, O. V. Shvedov, N. S. Tikhonov, A. I. Tokarenko, S. D. Khromeev, K. V. Golubkin, D. N. Kolupaev
RTR spent fuels reprocessing: Nitric dissolution of aluminium alloys A. Juvenelle, M. H. Garrido-Berton, B. Tuffery
FiR 1 reactor and the spent fuel management S. E. J. Salmenhaara
Experiences from HEU fresh fuel transportation from Yugoslavia to Russia M. Pešić, O. Šotić
Determination of radiological characteristics of reactor RA spent fuel elements M. J Milošević.
Criticality safety study of fresh HEU fuel elements in TK-S15 and TK-S16 transportation packages
V. Lj. Ljubenov, M. M. Steljić, M. P. Pešić
Research reactor records in the INIS database - a bibliometric study N. M. Marinkovic
Study on influence of corrosion at aluminium-clad spent fuel of research reactor M. Pešić, T. Maksin, R. Dobrijević, Z. Idjaković
Reprocessing U-Mo spent fuels: research program N. Herlet, J. P. Dancausse, A. Juvenelle, A. Vaudano
