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Flaw Evaluation and Allowable Flaw Sizes of Nuclear Piping in JSME Code

[+] Author Affiliations
Kunio Hasegawa

Hitachi, Ltd., Hitachi-shi, Ibaraki-ken, Japan

Hideo Kobayashi

Tokyo Institute of Technology, Tokyo, Japan

Koichi Kashima

Central Research Institute of Electric Power Industry, Komae-shi, Tokyo, Japan

Paper No. PVP2003-2025, pp. 39-44; 6 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


A flaw evaluation code for nuclear power plants has been developed at the Japan Society of Mechanical Engineers (JSME) in 2000 and revised adding inspection rules in 2002. Then the code consists of inspection for nuclear components and evaluation procedures of flaws in Class 1 components detected during in-service inspection. This paper introduces the summary of the JSME Code and describes two kinds of allowable flaw sizes, Acceptance Standards and Acceptance Criteria, for Class 1 pipes in the flaw evaluation procedures. In addition, these allowable flaws are compared with those in the ASME (American Society of Mechanical Engineers) Code Section XI.

Copyright © 2003 by ASME
Topics: Pipes , JSME Standards



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