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Working Material IAEA-TM-25332 TWG-FR/109 LIMITED DISTRIBUTION WORKING MATERIAL Technical Meeting on "Operational and Decommissioning Experience with Fast Reactors" Cadarache, France, 11-15 March 2002 Reproduced by the IAEA Vienna, Austria, 2002 NOTE The material in this document has been supplied by the authors and has not been edited by the IAEA. The views expressed remain the responsibility of the named authors and do not necessarily reflect those of the government (s) of the designating Member State (s). hi particular, neither the IAEA nor any other organization or body sponsoring this MEETING can be held responsible for any material reproduced in this document. CONTENTS Meeting Report 1 A. Stanculescu List of participants 15 SESSION 1: Fast reactor operational experience Fast breeder test reactor 15 years of operational experience 22 K. V. Suresh Kumar, R.P. Kapoor, P. V. Ramalingam, B. Rajendran, G. Srinivasan, K. V. Kasiviswanathan Operational experience and upgrading program of the experimental fast reactor JOYO 66 T. Aoyama, T. Odo, S. Suzuki, S. Yogo Operating history, present status and future plans for Monju 188 Y. Ibuki Operational experience of BN-350 194 I. Dumchev Lifetime extension of the Phenix nuclear power plant 214 L. Martin, D. Pepe, R. Dupraz Lifetime extension of the Phenix nuclear power plant (viewgraphs) 222 L. Martin Advanced and innovative approaches to inspect the Phenix fast breeder reactor 258 M. Giraud, P. Major, J. Gros, L. Martin, P. Benoist, O. Burat Visual inspection of reactor internal structures (viewgraphs) 264 R. Dupraz, P. Major, L. Martin Reactor conical shell inspection (viewgraphs) 291 R. Dupraz, M. Giraud, J. Gros, L. Martin Sodium cleaning in Phenix steam generator modules 314 O. Gastaldi, V. Grabon, Ch. Cavagna Review of fast reactor operational experience gained in Russia. Approaches to coordinated research project 339 V.M. Poplavsky, Yu.M. Ashurko, Yu.E. Bagdassarov, A. V. Karpov, M.P. Nikulin, A.M. Tsiboulia, N.N. Oshkanov, A.I. Kiryshin, B.A. Vasilyev, K.L. Suknev, A.S. Korol'kov, V.V. Denisov SESSION 2: Fast reactor decommissioning experience Decommissioning experience from the experimental breeder reactor-II 363 S.P. Henslee, K.E. Rosenberg Decommissioning experience from the EBR-II (viewgraphs) 368 S.P. Henslee Overview of Tacis project K1.01/98A "Assistance to the elaboration of a decommissioning plan" for Aktau BN 350 NPP (Kazakhstan) 385 R. Brachi Tacis project K1.01/98A. Achievements & recommendations (viewgraphs) 395 R. Brachi General review of the decommissioning of liquid metal fast reactors (LMFRs) in France 409 G. Rodriguez, R. Frith, M. Berte Overall strategy of Creys Malville power station dismantling 462 P. Alphonse Disposal of Creys Malville sodium 470 P. Alphonse Superphenix. Strategy and orientations for dismantling reactor block. State of 479 reflections in February 2002 D. Chiarot Superphenix (SPX). Reactor vessel dismantling strategy and orientations (viewgraphs) 490 D. Chiarot Dismantling strategy for secondary loops and associated sodium circuits 502 E. Joulia Concept for dismantling the reactor vessel and the biological shield of the compact sodium-cooled nuclear reactor facility (KNK) 524 /. Hillebrand, J. Benkert (presented by W. Pfeifer) Concept for dismantling the reactor vessel and the biological shield of the compact sodium-cooled nuclear reactor facility (KNK) (viewgraphs) 532 W. Pfeifer, I. Hillebrand CEA Experimental feedback on sodium loop decommissioning 557 O. Vinoche, G. Rodriguez Sodium removal & decontamination process and decommissioning considerations for the PFBR components 576 M. Rajan, C.S. Surendran, V.Ganesan, B.S. Sodhi, S.C. Chetal, R.D. Kale, R. Indira, A.K. Bhaduri SESSION 3: Fast reactor physics and engineering experiments and analyses Intergranular reheat cracking in austenitic stainless steel welds. Experimental program and numerical values 586 M.T. Cabrillat, L. Allais, M. Reytier, E. Pluyette Present status of the RCC-MR code 599 B. Riou, C. Escaravage, M. Sperandio, B. Salles, Y. Meziere, M.T. Cabrillat, B. Drubay Analysis of Superphenix and Phenix neutron physics experiments with the ERANOS code and data system 619 J. Tommasi, S. Czernecki, G. Rimpault, F. Varaine Physics and engineering experiments in fast breeder test reactor 645 K. V. Suresh Kumar, C.P. Reddy, R. Indira, R.S. Kesava Murthy, N. Kasinathan, R.P. Kapoor, P. V. Ramalingam, B. Rajendran, G. Srinivasan SESSION 4: Preservation of fast reactor knowledge and experience R&D LMFRs knowledge preservation French project 694 F. Baque LMFRs knowledge preservation (viewgraphs) 700 F. Baque R&D LMFRs knowledge preservation French project. Application to the sodium coolant and cover gas 710 G. Rodriguez LMFRs R&D knowledge preservation: sodium coolant (viewgraphs) 715 G. Rodriguez JNC viewpoint on fast reactor knowledge preservation 728 T. Irie International Atomic Energy Agency Technical Meeting (TM) on "Operational and Decommissioning Experience with Fast Reactors' hosted by CEA, Centre d'Etudes de Cadarache, France 11-15 March 2002 Meeting Report INTRODUCTION For three decades, several countries had large and vigorous fast breeder reactor development programs. In most cases, fast reactor development programs were at their peaks by 1980. Fast test reactors [Rapsodie (France), KNK-II (Germany), FBTR (India), JOYO (Japan), DFR (UK), BR-10, BOR-60 (Russia), EBR-II, Fermi, FFTF (U.S.A.)] were operating in several countries, with commercial size prototype reactors [Phenix, Superphenix (France), SNR-300 (Germany), MONJU (Japan), PFR (UK), BN-350 (Kazakhstan), BN-600 (Russia)] just under construction or coming on line. From that time onward, fast reactor development in general began to decline. By 1994 in the USA, the Clinch River Breeder Reactor (CRBR) had been cancelled, and the two fast reactor test facilities, FFTF and EBR-II had been shutdown - with EBR-II permanently, and FFTF in a standby condition. Thus, effort essentially disappeared for fast breeder reactor development. Similarly, programs in other nations were terminated or substantially reduced. In France, Superphenix was shut down at the end of 1998; SNR-300 in Germany was completed but not taken into operation, and KNK-II was permanently shut down in 1991 after 17 years of operation, and is scheduled to be dismantled by 2004; in the UK, PFR was shut down in 1994; BN-350 in Kazakhstan was shut down in 1998. It is difficult to argue that fast breeder reactors will be built in the near term when no commercial market exists and there is a plentiful supply of cheap uranium. Nevertheless, it is reasonable to assume that, were nuclear energy to remain an option as part of the long-term world energy supply mix, meeting the sustainability requirements vis-a-vis natural resources and long-lived radioactive waste management will require deploying systems involving several reactor types and fuel cycles operating in symbiosis. Apart from cost effectiveness, simplification, and safety considerations, a basic requirement to these reactor types and fuel cycles will be flexibility to accommodate changing objectives and boundary conditions. This flexibility can only be assured with the deployment of the fast neutron spectrum reactor technology, and reprocessing. At the same time that the interest in the fast reactor waned, also the retirement of many of the developers of this technology reached its peak, between 1990 and 2000, and hiring diminished in parallel. Moreover, R&D programs are being discontinued, and facilities falling in disuse. Under these circumstances, the loss of the fast reactor knowledge base should be taken seriously. One particularly important aspect of this knowledge base is given by the accumulated operational experience. The participants in the 33rd Annual Meeting of the International Working Group on Fast Reactors, "Technical Committee Meeting on Liquid Metal Fast Reactor Developments" (Vienna, 16-18 May 2000), recommended holding a technical meeting (TM) on "Feedback from Operational and Decommissioning Experience with Fast Reactors". At the 34th Annual Meeting of the Technical Working Group on Fast Reactors, "Technical Committee Meeting on Review of National Programmes on Fast Reactors and ADS" (Almaty/Kurchatov City, Kazakhstan, 14-18 May 2001), it was further recommended to launch a Coordinated Research Program (CRP) on "Generalisation and Analyses of Operational Experience with Fast Reactor Equipment and Systems" (Preserve Fast Reactor Operation and Decommissioning Experience). It was agreed to structure the TM in such a way that, apart from providing an information exchange opportunity, it would also prepare the grounds for the CRP. 2 SCOPE AND OBJECTIVES The scope of the TM was to provide a global forum for information exchange on fast reactor operational and decommissioning experience. The objectives of the TM were to: exchange detailed technical information on fast reactor operation and/or decommissioning experience with DFR, PFR (UK); KNK-II (Germany); Rapsodie, Phenix, Superphenix (France); BR-10, BOR-60, BN-600 (Russia); BN-350 (Kazakhstan); SEFOR, EBR-II, Fermi, FFTF (U.S.A.); FTBR (India); JOYO, MONJU (Japan); present the status of the work concerning the knowledge preservation efforts related to the experience accumulated in the various member states from the operation and decommissioning of fast reactors; start the preparation of the planned Co-ordinated Research Project (CRP) on "Generalization and Analyses of Operational Experience with Fast Reactor Equipment and Systems" (narrow down scope and
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