2016年春の年会

講演情報

一般セッション

IV. 核燃料サイクルと材料 » 402-1. 炉材料とその照射挙動

[2H17-22] 圧力容器 管材

2016年3月27日(日) 16:25 〜 18:05 H会場 (講義棟B棟 B204)

座長:沖田 泰良(東大)

16:40 〜 16:55

[2H18] Evaluation of the relationship between microstructure and hardness in neutron irradiated reactor pressure vessel model alloys following thermal ageing

*Liang Chen1,2, Kenji Nishida2, Kenta Murakami1, Kenji Dohi2, Li Liu1, Naoto Sekimura1 (1.Univ. Tokyo, 2.CRIEPI)

キーワード:Reactor pressure vessel, Embrittlement, Solute clusters, Atom probe tomography

The relationship between microstructures and mechanical properties is important issue for the embrittlement correlation method for Japanese reactor pressure vessel steels. In this work,the characteristics of solute clusters are studied by atom probe tomography in neutron irradiated model alloys following thermal ageing to peak hardness. Also, the relationship between solute clusters and Vickers hardness change is investigated.