Memory effects and steady state growth kinetics for stress corrosion cracking of a cold worked 316L stainless steel in high temperature pure water

Zhanpeng Lu, Tetsuo Shoji, Yoichi Takeda, Yuzuru Ito, Akira Kai, Seiya Yamazaki

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

5 Citations (Scopus)

Abstract

The stress corrosion cracking (SCC) growth kinetics for a cold worked 316L stainless steel was continuously monitored in high purity water at different temperatures and dissolved oxygen (DO) levels under a K (or Kmax) of 30MPa.m0.5. The total SCC test time was more than 8000h to make sure the steady state crack growth rate under each test condition could be reached. Crack growth rate (CGR) increases with increasing temperature in the range 110-288°C A typical intergraular-cracking mode is identified. Depending on the previous test condition, especially the temperature, three kinds of crack growth kinetics, i.e., increasing with testing time then becoming steady, being constant during the whole period, or decreasing with test time then becoming steady, are identified and discussed. Time-dependent and testing history-dependent crack growth modes were confirmed in two series of tests in 2ppm DO and 7.5ppm DO pure water. The apparent activation energies are calculated and compared with other data in different environments under different applied loading levels for understanding the cracking mechanism.

Original languageEnglish
Title of host publicationProceedings - CIS Workshops 2007, 2007 International Conference on Computational Intelligence and Security Workshops, CISW 2007
Pages1783-1798
Number of pages16
Publication statusPublished - 2007 Dec 1
Event13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007 - Whistler, BC, Canada
Duration: 2007 Apr 192007 Apr 23

Publication series

NameCanadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
Volume3

Other

Other13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
CountryCanada
CityWhistler, BC
Period07/4/1907/4/23

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality
  • Materials Science(all)

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