- 著者
- 井野 博満 上澤 千尋 伊東 良徳
- 出版者
- 日本金属学会
- 雑誌
- 日本金屬學會誌 = Journal of the Japan Institute of Metals (ISSN:00214876)
- 巻号頁・発行日
- vol.72, no.4, pp.261-267, 2008-04-01
1 0 0 0 OA 国内沸騰水型原子炉圧力容器鋼材における照射脆化</br>—監視試験データの解析—
- 著者
- 井野 博満 上澤 千尋 伊東 良徳
- 出版者
- 公益社団法人 日本金属学会
- 雑誌
- 日本金属学会誌 (ISSN:00214876)
- 巻号頁・発行日
- vol.72, no.4, pp.261-267, 2008 (Released:2008-04-01)
- 参考文献数
- 12
- 被引用文献数
- 1 1
Surveillance data for pressure vessel steels of the 51 LWR plants in Japan were analyzed to make clear the effect of neutron irradiation on the brittle transition temperature of the steels. The clear difference observed in the rise of the ductile to brittle transition temperature between the normal and accelerated irradiation samples is considered to be due to the effect of neutron flux. The present analysis is discussed in comparison with the result of computer simulation based on the rate equations of the radiation damage process and the recent experiments of APFIM and positron annihilation.