検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

イオン照射による原子炉圧力容器鋼溶接熱影響部の硬化と微細組織

Microstructure and hardening of ion-irradiated heat-affected zone of reactor pressure vessel steel

河 侑成  ; 高見澤 悠 ; 勝山 仁哉  ; 西山 裕孝 ; 吉田 健太*; 外山 健*; 永井 康介*

Ha, Yoosung; Takamizawa, Hisashi; Katsuyama, Jinya; Nishiyama, Yutaka; Yoshida, Kenta*; Toyama, Takeshi*; Nagai, Yasuyoshi*

原子炉圧力容器内表面のステンレスオーバーレイクラッド直下に生じる溶接熱影響部(HAZ)は加圧熱衝撃事象による想定き裂前縁にはHAZも含まれている。本研究はHAZの照射脆化感受性を調べるため、Fe$$^{2+}$$イオン照射によるHAZの照射硬化及び組織観察を行い、照射硬化と金属組織の関係について検討した。SCFGHAZの照射硬化量が最も高く、TEM観察結果から析出物が分布されているのを確認した。

Heat-affected zone of stainless over-ray clad is included in a supposed cracking area during the pressurized thermals shock regime. It is necessary to confirm the irradiation embrittlement susceptibility of HAZ compared with that of matrix. In this study, Fe$$^{2+}$$ ion irradiated into HAZ and matrix. We discussed the correlation between irradiation hardening and microstructure in HAZ. The irradiation hardening of SCFGHAZ is highest. As results of TEM observation, the precipitates dispersed with ~200 nm of sizes in SCFGHAZ specimen. Also, dislocation loops with high density by irradiation exist.

Access

:

- Accesses

InCites™

:

Altmetrics

:

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.