Cluster dynamics study on nano damage of RPV steels under proton irradiation at 290°C

被引:0
|
作者
Wan, Qiangmao [1 ,2 ,3 ]
Shu, Guogang [4 ]
Tang, Jiaxuan [1 ]
Pang, Jianjun [2 ]
Chen, Lisha [3 ]
Wang, Duan [1 ]
Lin, Hui [1 ]
Ding, Hui [5 ]
机构
[1] CNNC, Nucl Ind Coll, Beijing, Peoples R China
[2] Zhejiang Univ Water Resources & Elect Power, Sch Mech & Automot Engn, Hangzhou, Zhejiang, Peoples R China
[3] Zhejiang Inst Mech & Elect Engn, Sch Modern Informat Technol, Hangzhou, Zhejiang, Peoples R China
[4] China United Gas Turbine Technol Co Ltd, Beijing, Peoples R China
[5] Southeast Univ, Sch Mat Sci & Engn, Nanjing, Peoples R China
来源
关键词
reactor pressure vessels; cluster dynamics; proton irradiation; dislocation loops; solute clusters; MICROSTRUCTURE EVOLUTION; A508-3; STEEL; REACTOR;
D O I
10.3389/fenrg.2024.1439489
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
Irradiation-induced defects such as dislocation loops, cavities or solute clusters and chemical composition segregation of reactor pressure vessel (RPV) steel are the root causes of irradiation embrittlement. Combining two nucleation mechanisms, namely, the uniform nucleation and non-uniform nucleation of solute clusters (such as Cu-rich phase), a cluster kinetic simulation was established based on the reaction rate theory, and the co-evolution of matrix damage and Cu-rich phase in low-copper RPV steel was simulated under irradiation. And the average size and number density of defective clusters and solute clusters were established with irradiation dose. Compared with the average size and number density of dislocation loops observed by transmission electron microscopy (TEM) of proton irradiated RPV steel at 290 degrees C, the verification results show that the cluster dynamics model considering both the nucleation mechanism of interstitial dislocation loops and vacancy clusters can well simulate the irradiation damage behavior of materials.
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收藏
页数:7
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