Effects of interstitial cluster mobility on dislocation loops evolution under irradiation of austenitic steel  

作　　者：Xin‑Hua Yan Lu Sun Du Zhou Teng Xie Chang Peng Ye‑Xin Yang Li Chen Zhen‑Feng Tong 

机构地区：[1]North China Electric Power University,Beijing 102206,China [2]China Nuclear Power Operations Co.,Ltd,Shenzhen 518000,China

出　　处：《Nuclear Science and Techniques》2024年第8期69-78,共10页核技术（英文）

基　　金：supported by the National Natural Science Foundation of China(No.U1967212);the Fundamental Research Funds for the Central Universities(No.2021MS032);the Nuclear Materials Innovation Foundation(No.WDZC-2023-AW-0305)。

摘　　要：The evolution of dislocation loops in austenitic steels irradiated with Fe^(+)is investigated using cluster dynamics(CD)simulations by developing a CD model.The CD predictions are compared with experimental results in the literature.The number density and average diameter of the dislocation loops obtained from the CD simulations are in good agreement with the experimental data obtained from transmission electron microscopy(TEM)observations of Fe~+-irradiated Solution Annealed 304,Cold Worked 316,and HR3 austenitic steels in the literature.The CD simulation results demonstrate that the diffusion of in-cascade interstitial clusters plays a major role in the dislocation loop density and dislocation loop growth;in particular,for the HR3 austenitic steel,the CD model has verified the effect of temperature on the density and size of the dislocation loops.

关 键 词：Cluster dynamics Dislocation loops In-cascade interstitial clusters Austenitic steels 

分 类 号：TL34[核科学技术—核技术及应用]