Quantifying the effects of straining-hardening and water chemistry on crack growth rates of 316L Ss welds in high temperature water

Zhanpeng Lu, Kazuhiko Sakaguchi, Koji Negishi, Yoichi Takeda, Yuzuru Ito, Tetsuo Shoji

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

9 Citations (Scopus)

Abstract

A series of stress corrosion crack (SCC) growth rate tests with in-situ crack length monitoring for 316L stainless steel weld heat-affected zones with different Vickers hardness and 316 weld metals with different delta-ferrite contents in 288°C pure water with different concentrations of dissolved oxygen were performed. Typical intergranular stress corrosion cracking (IGSCC) and branching of the crack front were observed for two 316L HAZ specimens. Crack growth rate increases with Vickers Hardness in the 316L HAZ specimens. CGRs for 316L HAZ specimens in 2ppm and 7ppm DO are moderately higher than that in 0.2ppm DO water. After a single overloading, CGR tends to be lower for a period of time. Crack growth near the fusion line is monitored and the crack front of a 316L HAZ specimen is near the fusion line, while ACPD still shows an increase before stopping the test. SCC growth rates of two 316L weld metals with two ferrite contents, 9% in the crack growth region for high ferrite weld metal, and 6-7 % ferrite in the crack growth region were measured at 288°C in oxygenated pure water. Generally, CGRs in the high ferrite weld metal are higher than those in the low ferrite weld metal under the same test environment. The CGRs for the two weld metals in 2ppm DO water are higher than those in 200ppb DO water. For the weld metal with a low ferrite content, the CGR shows a tendency to become saturate at DO>2ppm. However, for the weld metal with a high ferrite content, the CGR in 2ppm DO water is higher than those in 7ppm and 11ppm DO water. Such an observation is confirmed by separate test.

Original languageEnglish
Title of host publication14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
Pages636-645
Number of pages10
Publication statusPublished - 2009 Dec 1
Event14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009 - Virginia Beach, VA, United States
Duration: 2009 Aug 232009 Aug 27

Publication series

Name14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
Volume1

Other

Other14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
CountryUnited States
CityVirginia Beach, VA
Period09/8/2309/8/27

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Environmental Engineering

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