OKMC Simulation of the Evolution of Irradiation Defects in RPV Steel

• 作者: Ding Zhaonan Li Jianyang Zhang Chonghong
• 来源期刊: 中国科学院近代物理研究所和兰州重离子研究装置年报:英文版
• 学科: 工学
• 关键词: MICROSTRUCTURE DUCTILE SOLUTE
• 年，卷（期）: 2018,（1）
• 页码范围: 129-130
• 页数: 2页
• 分类号: TG1

摘要

Reactor Pressure Vessel(RPV)is a key structural component of nuclear reactor.It has to endure high-dose neutron irradiation during service.Neutron irradiation produces defect clusters and solute segregation,causing hardening and embrittlement of the RPV steel.A pretty number of testing and characterization techniques of microstructure and mechanical properties utilizing miniaturized specimens have been developed[1−4].Current experimental studies show that the increase of nano-hardness and micro-hardness of materials is positively correlated with that of macroscopic yield stress and ductile-brittle transition temperature[5;6].Meanwhile,some physical models related to defects,solute cluster characteristics and hardness change of materials have been established[7;8],supposing that the hardness increment in irradiation material mainly comes from the large heterogeneous clusters.