Fast Reactors and Accelerator Driven Systems Knowledge Base

Working Materials of the Technical Working Group on Fast Reactors

Technical Meeting on "Operational and Decommissioning Experience with Fast Reactors", Cadarache, France, 11–15 March 2002
report nr.: TWGFR/109
IAEA-TM-25332
 
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:
  1. 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);
  2. 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;
  3. 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 objectives of the CRP, propose a detailed work plan).

Contents

SESSION 1 : Fast reactor operational experience

  • Fast breeder test reactor 15 years of operational experience
    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
    T. Aoyama, T. Odo, S. Suzuki, S. Yogo
  • Operating history, present status and future plans for Monju
    Y. Ibuki
  • Operational experience of BN-350
    I. Dumchev
  • Lifetime extension of the Phenix nuclear power plant
    L. Martin, D. Pepe, R. Dupraz
  • Lifetime extension of the Phenix nuclear power plant (viewgraphs)
    L. Martin
  • Advanced and innovative approaches to inspect the Phenix fast breeder reactor
    M. Giraud, P. Major, J. Gros, L. Martin, P. Benoist, O. Burat
  • Visual inspection of reactor internal structures (viewgraphs)
    R. Dupraz, P. Major, L. Martin
  • Reactor conical shell inspection (viewgraphs)
    R. Dupraz, M. Giraud, J. Gros, L. Martin
  • Sodium cleaning in Phenix steam generator modules
    O. Gastaldi, V. Grabon, Ch. Cavagna
  • Review of fast reactor operational experience gained in Russia. Approaches to coordinated research project
    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
    S. P. Henslee, K. E. Rosenberg
  • Decommissioning experience from the EBR-II (viewgraphs)
    S. P. Henslee
  • Overview of Tacis project K1.01/98A “Assistance to the elaboration of a decommissioning plan” for Aktau BN 350 NPP (Kazakhstan)
    R. Brachi
  • Tacis project K1.01/98A. Achievements & recommendations (viewgraphs)
    R. Brachi
  • General review of the decommissioning of liquid metal fast reactors (LMFRs) in France
    G. Rodriguez, R. Frith, M. Berte
  • Overall strategy of Creys Malville power station dismantling
    P. Alphonse
  • Disposal of Creys Malville sodium
    P. Alphonse
  • Superphenix. Strategy and orientations for dismantling reactor block. State of reflections in February 2002
    D. Chiarot
  • Superphenix (SPX). Reactor vessel dismantling strategy and orientations (viewgraphs)
    D. Chiarot
  • Dismantling strategy for secondary loops and associated sodium circuits
    E. Joulia
  • Concept for dismantling the reactor vessel and the biological shield of the compact sodium-cooled nuclear reactor facility (KNK)
    I. 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)
    W. Pfeifer, I. Hillebrand
  • CEA Experimental feedback on sodium loop decommissioning
    O. Vinoche, G. Rodriguez
  • Sodium removal & decontamination process and decommissioning considerations for the PFBR components
    M. Rajan, C.S. Surendran, FGanesan, 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
    M.T. Cabrillat, L. Allais, M. Reytier, E. Pluyette
  • Present status of the RCC-MR code
    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
    J. Tommasi, S. Czernecki, G. Rimpault, F. Varaine
  • Physics and engineering experiments in fast breeder test reactor
    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
    F. Baque
  • LMFRs knowledge preservation (viewgraphs)
    F. Baque
  • R&D LMFRs knowledge preservation French project. Application to the sodium coolant and cover gas
    G. Rodriguez
  • LMFRs R&D knowledge preservation: sodium coolant (viewgraphs)
    G. Rodriguez
  • JNC viewpoint on fast reactor knowledge preservation
    T. Irie
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