Stress corrosion cracking behavior of type 304 stainless steel irradiated under different neutron dose rates at JMTR

Yoshiyuki Kaji, Keietsu Kondo, Yoshiteru Aoyagi, Yoshiaki Kato, Taketoshi Taguchi, Fumiki Takada, Junichi Nakano, Hirokazu Ugachi, Takashi Tsukada, Kenichi Takakura, Hiroshi Sakamoto

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

3 Citations (Scopus)

Abstract

In order to investigate the effect of neutron dose rate on tensile property and irradiation stress corrosion cracking (IASCC) behavior, crack growth rate (CGR) and, tensile tests and microstructure observation have been conducted with type 304 stainless steel specimens. The specimens were irradiated in high temperature water simulating boiling water reactor (BWR) environments up to about 1dpa with two different dose rates at the Japan Materials Testing Reactor (JMTR). While radiation hardening increased with the dose rate, CGR was not affected by the dose rate. Increase of the yield strength of the low dose rate specimens was caused by the increase of number density of Frank loops. Little difference of radiation-induced segregation at grain boundaries was observed in specimens irradiated by different dose rates. Furthermore, no dose rate effect on local plastic deformation behavior was found near crack tip in the crystal plasticity simulation.

Original languageEnglish
Title of host publication15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Pages1140-1153
Number of pages14
Publication statusPublished - 2011 Dec 1
Externally publishedYes
Event15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 - Colorado Springs, CO, United States
Duration: 2011 Aug 72011 Aug 11

Publication series

Name15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Volume2

Other

Other15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
CountryUnited States
CityColorado Springs, CO
Period11/8/711/8/11

Keywords

  • JMTR
  • Neutron dose rate
  • Stress corrosion cracking
  • Type 304 stainless steel

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Pollution

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