2020 Annual Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[1M06-09] Irradiation Effect 1

Mon. Mar 16, 2020 2:45 PM - 3:50 PM Room M (Lecture Bildg. S 3F S-31)

Chair:Hiroaki Abe(Univ. of Tokyo)

2:45 PM - 3:00 PM

[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.)

Keywords: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.