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Probabilistic Approach for Creep-Fatigue Evaluation in Liquid Metal Cooled Fast Reactor

[+] Author Affiliations
Nobuchika Kawasaki, Tal Asayama

Japan Nuclear Cycle Development Institute, Ibaraki, Japan

Yasuharu Chuman

Mitsubishi Heavy Industries, Ltd., Nagasaki, Japan

Yoshihiko Tanaka

Japan Atomic Power Company, Tokyo, Japan

Paper No. PVP2002-1235, pp. 191-198; 8 pages
  • ASME 2002 Pressure Vessels and Piping Conference
  • Pressure Vessel and Piping Codes and Standards
  • Vancouver, BC, Canada, August 5–9, 2002
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4650-4
  • Copyright © 2002 by ASME


A procedure to calculate crack initiation probabilities by creep-fatigue damage is explained in this paper with a calculation example. Material properties of 316FR are determined as probabilistic distributions from test data. As the result yield stress, fatigue property, cyclic stress-strain relation and creep property are input into a creep-fatigue evaluation as the probabilistic distributions. The crack initiation probability is calculated with the condition for the Japanese commercialized sodium cooled fast breeder reactor. As the result, the allowable thermal cycles in the present design becomes 5 × 10−9 cumulative crack initiation probability.

Copyright © 2002 by ASME



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