A reduced cluster dynamics modeling of radiation damage in tungsten

被引:0
|
作者
Li, Zhiyuan [1 ]
Ding, Gaowen [1 ]
Liu, Pengchuang [3 ]
Cong, Tenglong [4 ]
Li, Yang [1 ,2 ]
机构
[1] Shanghai Univ, Shanghai Inst Appl Math & Mech, Sch Mech & Engn Sci, Shanghai Key Lab Mech Energy Engn, Shanghai 200072, Peoples R China
[2] Shanghai Inst Aircraft Mech & Control, 100 Zhangwu Rd, Shanghai 200092, Peoples R China
[3] Sci & Technol Surface Phys & Chem Lab, Mianyang 621908, Sichuan, Peoples R China
[4] Shanghai Jiao Tong Univ, Sch Nucl Sci & Engn, Shanghai 200240, Peoples R China
基金
中国国家自然科学基金;
关键词
Irradiated tungsten; Cluster dynamics; Helium bubble; Loop punching; HELIUM BUBBLE-GROWTH; SELF-ION IRRADIATION; MICROSTRUCTURAL EVOLUTION; NEUTRON-IRRADIATION; CASCADE DAMAGE; MOLECULAR-DYNAMICS; DISLOCATION LOOPS; PURE TUNGSTEN; IN-SITU; DISPLACEMENT DAMAGE;
D O I
10.1016/j.nme.2024.101814
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A reduced cluster dynamics model is developed to investigate the microstructure evolution of irradiated single crystal tungsten. The model accounts for the generation and reaction of point defects, small-size defect clusters, helium clusters, as well as the nucleation and growth of large immobile defects, including the interstitial dislocation loops, voids and helium bubbles. Moreover, by incorporating an atomically informed loop punching mechanism for bubble growth, the model is able to accurately capture the evolution kinetics of radiation-induced defects with and without the helium implantation. The predicted densities and sizes of loops and voids/bubbles, the helium-to-vacancy ratio and the internal pressure of helium bubbles are all in good agreement with experimental data at different irradiation doses across a wide range of temperatures from 300 K up to 1200 K. This work aims to provide a robust tool for analyzing the microstructure of irradiated tungsten under both fission and fusion conditions.
引用
收藏
页数:15
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