TY - GEN
T1 - Effect of the accelerated irradiation and hydrogen/helium gas on IASCC characteristics for highly irradiated austenitic stainless steels
AU - Fujimoto, K.
AU - Yonezawa, Toshio
AU - Wachi, E.
AU - Yamaguchi, Y.
AU - Nakano, M.
AU - Shogan, R. P.
AU - Massoud, J. P.
AU - Mager, T. R.
PY - 2005/12/1
Y1 - 2005/12/1
N2 - In order to clarify irradiation assisted stress corrosion cracking (IASCC) characteristics of highly irradiated austenitic stainless steels over dose of 40dpa, SCC susceptibility in simulated PWR primary water, mechanical/ metallurgical properties, and hydrogen/helium gas concentrations have been investigated for the austenitic stainless steels irradiated in actual PWRs or in fast breeder reactor (FBR). The IASCC susceptibility of the stainless steels irradiated in a FBR was extremely lower than that of the stainless steels irradiated in a PWR, according to the slow strain rate tensile (SSRT) tests in PWR environment. Mechanical properties and radiation induced segregation (RIS) of the stainless steels irradiated in a FBR revealed the same tendency as those of the stainless steels irradiated in a PWR. But hydrogen/helium gas concentrations in the stainless steels irradiated in a FBR was extremely smaller than that in the stainless steels irradiated in a PWR. Also, cavity formation was observed not only in the grain, but also near the grain boundary in the highly irradiated stainless steel in a PWR. Therefore, it is suggested that the hydrogen/helium gas plays an important role in IASCC of PWR core internals, in addition to conventionally proposed RIS and radiation hardening. Furthermore, it is considered that the IASCC characteristics at the high irradiation range are different from those at the low irradiation range.
AB - In order to clarify irradiation assisted stress corrosion cracking (IASCC) characteristics of highly irradiated austenitic stainless steels over dose of 40dpa, SCC susceptibility in simulated PWR primary water, mechanical/ metallurgical properties, and hydrogen/helium gas concentrations have been investigated for the austenitic stainless steels irradiated in actual PWRs or in fast breeder reactor (FBR). The IASCC susceptibility of the stainless steels irradiated in a FBR was extremely lower than that of the stainless steels irradiated in a PWR, according to the slow strain rate tensile (SSRT) tests in PWR environment. Mechanical properties and radiation induced segregation (RIS) of the stainless steels irradiated in a FBR revealed the same tendency as those of the stainless steels irradiated in a PWR. But hydrogen/helium gas concentrations in the stainless steels irradiated in a FBR was extremely smaller than that in the stainless steels irradiated in a PWR. Also, cavity formation was observed not only in the grain, but also near the grain boundary in the highly irradiated stainless steel in a PWR. Therefore, it is suggested that the hydrogen/helium gas plays an important role in IASCC of PWR core internals, in addition to conventionally proposed RIS and radiation hardening. Furthermore, it is considered that the IASCC characteristics at the high irradiation range are different from those at the low irradiation range.
KW - Baffle Former Bolt
KW - Fast Breeder Reactor
KW - Helium
KW - Hydrogen
KW - Intergranular Stress Corrosion Cracking
KW - Irradiation Assisted Stress Corrosion Cracking
KW - Pressurized Water Reactor
KW - Radiation Induced Segregation
UR - http://www.scopus.com/inward/record.url?scp=33745188223&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=33745188223&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:33745188223
SN - 9780873395953
T3 - Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
SP - 299
EP - 310
BT - Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
T2 - 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Y2 - 14 August 2005 through 18 August 2005
ER -