French RSE-M and RCC-MR code appendices for flaw analysis: Presentation of the fracture parameters calculation - Part V: Elements of validation

摘要

French nuclear codes include flaw assessment procedures: the RSE-M Code "Rules for In-service Inspection of Nuclear Power Plant Components" and the RCC-MR code "Design and Construction Rules for Mechanical Components of FBR Nuclear Islands and High Temperature Applications". Development of analytical methods has been made for the last 10 years in the framework of a collaboration between CEA, EDF and AREVA-NP, and by R&D actions involving CEA and IRSN. These activities have led to a unification of the common methods of the two codes. The calculation of fracture mechanics parameters, in particular the stress intensity factor K{sub}I and the J integral, has been widely developed for industrial configurations. All the developments have been integrated in the 2005 edition of RSE-M and in 2007 edition of RCC-MR. This series of articles consists of 5 parts: the first part presents an overview of the methods proposed in the RCC-MR and RSE-M codes. Parts II-IV provide the compendia for specific components. The geometries are plates (part II), pipes (part III) and elbows (part IV). This part presents validation of the methods, with details on the process followed for their development and of the evaluation accuracy of the proposed analytical methods.