TY - GEN
T1 - Stress corrosion cracking behavior of type 304 stainless steel irradiated under different neutron dose rates at JMTR
AU - Kaji, Yoshiyuki
AU - Kondo, Keietsu
AU - Aoyagi, Yoshiteru
AU - Kato, Yoshiaki
AU - Taguchi, Taketoshi
AU - Takada, Fumiki
AU - Nakano, Junichi
AU - Ugachi, Hirokazu
AU - Tsukada, Takashi
AU - Takakura, Kenichi
AU - Sakamoto, Hiroshi
PY - 2011
Y1 - 2011
N2 - 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.
AB - 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.
KW - JMTR
KW - Neutron dose rate
KW - Stress corrosion cracking
KW - Type 304 stainless steel
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M3 - Conference contribution
AN - SCOPUS:84867587641
SN - 9781622761944
T3 - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
SP - 1140
EP - 1153
BT - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
T2 - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Y2 - 7 August 2011 through 11 August 2011
ER -