|
|||||
|
|
Detection of intergranular cracking susceptibility due to hydrogen in irradiated austenitic stainless steel with a superconducting quantum interference device (SQUID) sensor |
|
| Authors: | J Morisawa M OtakaM Kodama T KatoS Suzuki |
| Affiliation: | a Research Department, Nippon Nuclear Fuel Development Co., Ltd., 2163 Narita-cho, Oarai machi, Ibaraki-ken 311-1313, Japan b Nuclear Plant Construction and Engineering Department, Nuclear Systems Division, Hitachi Ltd., 3-1-1 Saiwai-cho, Hitachi-shi, Ibaraki-ken 317-0073, Japan c Research Department, Nippon Nuclear Fuel Development Co., Ltd., 2163 Narita-cho, Oarai machi, Ibaraki-ken 311-1313, Japan d Nuclear Plant Service Engineering Department, Nuclear Systems Division, Hitachi Ltd., 3-1-1 Saiwai-cho, Hitachi-shi, Ibaraki-ken 317-0073, Japan e Materials Engineering Group, Power Engineering R & D Center, Tokyo Electric Power Company, 4-1 Egasaki-cho, Tsurumi-ku, Yokohama, Kanagawa-ken 230-8510, Japan |
| Abstract: | To investigate the detection method of intergranular (IG) cracking susceptibility by hydrogen in irradiated austenitic stainless steel (SS), magnetic and mechanical properties were examined after two repeats of hydrogen charging and discharging (hydrogen treatment) in Type 304 SS which had been irradiated during use in different reactor cores. The residual magnetic flux density (Br) was measured with a superconducting quantum interference device sensor and Br increased with increased neutron fluence and repeated hydrogen treatments. Elongation decreased with an increase of Br and IG cracking appeared above Br of 2×10−5 T for this measuring method after repeated hydrogen treatments. These phenomena would be caused by hydrogen-induced martensite phase being formed on grain boundaries. It was thought the appearance of IG cracking susceptibility due to hydrogen in irradiated SS could be predicted by measuring the Br of the steel. |
| Keywords: | E0500 H0400 M0300 N0100 S0500 |
| 本文献已被 ScienceDirect 等数据库收录！ | |