2020年春の年会

講演情報

一般セッション

V. 核燃料サイクルと材料 » 502-1 原子炉材料,環境劣化,照射効果,評価・分析技術

[1M06-09] 照射効果1

2020年3月16日(月) 14:45 〜 15:50 M会場 (共通講義棟 S棟3F S-31)

座長:阿部 弘亨(東大)

14:45 〜 15:00

[1M06] Effects of Ni-Si clusters on loop growth and stability investigated by additional in-situ irradiation

*Dongyue Chen1, Kenta Murakami2, Liang Chen1, Hiroaki Abe1, Naoto Sekimura1 (1. Univ. of Tokyo, 2. Nagaoka Univ. of Tech.)

キーワード:stainless steel, combined irradiation, in-situ, loops

Stainless steel is widely applied in the light water reactors as structural materials. During its service, dislocation loops and Ni-Si clusters will be formed as a result of irradiation. These two types of radiation defects are expected to interact with each other, which is important in understanding the ageing of stainless steel in reactors. By our previous results, tiny Ni-Si clusters will be formed when our stainless steel model alloy is irradiated to 0.8dpa at 290 degree C. In this study, the irradiated model alloy with Ni-Si clusters will be further irradiated at higher temperate to enhance loop growth. The loop growth and stability in the additional irradiation will be observed by in-situ TEM, and the effects of pre-existing Ni-Si clusters will be discussed.