The safety margin evaluation for French Reactor Pressure Vessels has been carried out according to a semi-probabilistic approach derived from the codified methodology (RCC-M code -appendix ZG), based on a selection of reference defects and a list of leading transients. The level of required criteria depends on the probability of the combination (defect x selected transient). The main results taken from the generic analysis of the 900 MWe RPV margin evaluation are presented, based on numerous R&D studies dealing with plasticity correction and validation of computation codes. The emphasis is put on the conservatism of the approach in terms of generic data (fluence evaluation, heat transfer coefficient, material properties, RTNDT values). The various studies in progress performed in order to improve the present safety margins (3D thermohydraulic analysis, elastic-plastic computations as well as probabilistic fracture mechanics approach) are mentioned.


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    Titel :

    Reassessment of French Reactor Pressure Vessel integrity


    Beteiligte:
    Ternon-Morin, F. (Autor:in) / Meziere, Y. (Autor:in) / Moinereau, D. (Autor:in) / Bezdikian, G. (Autor:in) / Heuze, A. (Autor:in) / Vagner, J. (Autor:in)


    Erscheinungsdatum :

    1998


    Format / Umfang :

    9 Seiten, 6 Quellen


    Medientyp :

    Aufsatz (Konferenz)


    Format :

    Print


    Sprache :

    Englisch




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