Stress corrosion crack growth behavior of cold worked austenitic stainless steel in high temperature water

M. Tsubota, Y. Katayama, Yoshiaki Saito

Research output: Chapter in Book/Report/Conference proceedingConference contribution

14 Citations (Scopus)

Abstract

Crack propagation testing of type 316L stainless steel, with different hardness levels, in high temperature water has been performed, and the relationship between SCC growth rate (da/dt) and hardness (Hv) discussed. Intergranular crack propagation was observed in both solution treated material and cold worked materials. Highly cold worked material showed a higher crack propagation rate. Using the strain distribution near the crack tip and the SCC susceptible plastic zone size, where the hardness was higher than the critical Vickers hardness for SCC susceptibility (Hvc), the crack propagation rate for low carbon stainless steel, under the fixed environment, could be described as da/dt=A·K2/(Hvc-Hv0)2, where K is the stress intensity factor, Hvc is the critical hardness for SCC (defined as a Vickers hardness of 300), and HV0 is the Vickers hardness of the base material.

Original languageEnglish
Title of host publicationProceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Pages109-115
Number of pages7
Publication statusPublished - 2005 Dec 1
Externally publishedYes
Event12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors - Salt Lake City, UT, United States
Duration: 2005 Aug 142005 Aug 18

Other

Other12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
CountryUnited States
CitySalt Lake City, UT
Period05/8/1405/8/18

Keywords

  • BWR
  • Crack Growth Rate
  • Hardness
  • Stainless Steel
  • Stress Corrosion Cracking

ASJC Scopus subject areas

  • Engineering(all)

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  • Cite this

    Tsubota, M., Katayama, Y., & Saito, Y. (2005). Stress corrosion crack growth behavior of cold worked austenitic stainless steel in high temperature water. In Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (pp. 109-115)