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General Presentation of French Codified Flaw Evaluation Procedure: RSE-M

[+] Author Affiliations
Claude Faidy

Electricité de France, Villeurbanne Cedex, France

Paper No. PVP2003-2024, pp. 27-38; 12 pages
  • ASME 2003 Pressure Vessels and Piping Conference
  • Flaw Evaluation, Service Experience, and Reliability
  • Cleveland, Ohio, USA, July 20–24, 2003
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4154-5
  • Copyright © 2003 by ASME


The RSE-M Code “Rules for In-service Inspection of Nuclear Power Plant Components” defines the requirements for in-service inspection of French Pressurized Water Reactor’s. The scope covered by the RSE-M is all the surveillance and in-service inspection program for safety class components with a special attention to class 1 components. A large concern for this code is the flaw evaluation procedure for an in-service inspection defect. Generally the defect has to be repaired, but in order to postpone the repair or to accept some small defect a complete procedure is proposed for safety class components: fatigue crack initiation, fatigue crack growth, brittle and ductile rupture. All the details and the validation limits are included in non-mandatory appendices. The methods are usable for nuclear and non-nuclear pressure equipment. Partial safety factors and material properties are more PWR oriented. The paper presents the different parts of the procedure, their validations and major on-going developments.

Copyright © 2003 by ASME



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