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Study on the Influence of Strain Rate on Crack Initiation and Growth in Simulated Reactor Coolant Environment of Type 316 Stainless Steel

[+] Author Affiliations
Takahisa Nose, Takao Nakamura, Takanori Kitada

Osaka University, Osaka, Japan

Paper No. PVP2018-84490, pp. V01AT01A022; 6 pages
  • ASME 2018 Pressure Vessels and Piping Conference
  • Volume 1A: Codes and Standards
  • Prague, Czech Republic, July 15–20, 2018
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-5158-6
  • Copyright © 2018 by ASME


In order to conduct effective and rational maintenance activity of components in nuclear power plants, it is proposed to manage fatigue degradation based on crack size corresponding to an extent of cumulative fatigue damage. The purpose of this study focuses on the influence of strain rate in simulated reactor coolant environment for fatigue crack initiation and growth. 3-dimensional replica observations were conducted for environmental fatigue test specimens in different strain rates. Crack initiation and growth were observed in the experiments. It is clarified that low strain rate influences crack propagation and coalescence and increases crack growth rate that finally decrease fatigue life.

Copyright © 2018 by ASME



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