The RSE-M Code provides rules and requirements for inservice inspection of French Pressurized Water Reactor power plant components. Appendices 5.3 and 5.4 of the Code give non mandatory guidance for analytical evaluation of flaws, i.e. fracture mechanics analyses based on simplified methods. Flaw assessment aims to calculate the initiation and the subsequent propagation of the crack under cyclic loading (fatigue analysis) and then to assess the crack stability, by comparing the applied J integral to the toughness of the material. This paper shows an overview of the R&D work undergone to make possible an analytical approach: • analytical formulas for the elastic stress field in elbows under in-plane, out-of-plane and torsion moments, • stress intensity factors solutions based on the influence coefficient method for surface and embedded cracks in pipes, • simplified methods to estimate the J integral for various configurations of piping, flaws and loading. These methods are shortly presented, including their field of application and their validation.

No abstract

No abstract

Two 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 through a collaboration between CEA, EDF and AREVA-NP, and through R&D actions involving CEA and IRSN. These activities have led to unification of the common methods of the two codes. The calculation of fracture mechanics parameters, and in particular the stress intensity factor K 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 papers is composed of five parts: the first presents an overview of the methods proposed in the RCC-MR and RSE-M codes. Parts II-IV provide compendia for specific components. The geometries are plates (part II), pipes (part III) and elbows (part IV). Part V presents validation of the methods, with details on their accuracy. This paper presents the stress intensity factor and J calculation for cracked elbows. General data applicable for all defect geometries are first presented, and then, compendia for K I and s ref calculations are provided for the available defect geometries. r

No abstract