2020 Fall Meeting

Presentation information

Oral presentation

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

[2C08-13] Irradiation Effect 2

Thu. Sep 17, 2020 2:45 PM - 4:30 PM Room C (Zoom room 3)

Chair:Kenta Murakami(Nagaoka Univ. Tech.)

2:45 PM - 3:00 PM

[2C08] Nature of defect clusters produced in ferritic model alloy at elevated temperatures

*Liang Chen1, Kenta Murakami1, Dongyue Chen2, Huilong Yang2, Hiroaki Abe2, Zhengcao Li3, Naoto Sekimura2 (1. Nagaoka Univ. of Tech., 2. Univ. of Tokyo, 3. Tsinghua Univ.)

Keywords:reactor pressure vessel, dislocation loops, model alloy, combined irradiation, in situ transmission electron microscope

Dislocation loop is a principal feature of radiation damage, pertinent to embrittlement of nuclear reactor pressure vessel steel. Whether such loops consist of agglomerates of vacancies or of interstitials is one of the most fundamental questions. It is also one of the most difficult to answer, especially for defect clusters smaller than 10 nm. The objective of this work is to develop new method to determine the nature of small defect clusters, via combining bulk irradiation and in situ irradiation in transmission electron microscope. For this purpose, reactor pressure vessel model alloy Fe-Mn is selected. The behaviour of defect clusters under in situ irradiation is analysed.