Advances in research on helium ion irradiation in tungsten-based plasma-facing materials

被引:1
作者
Liang, Mengxia [1 ]
Xie, Fang [1 ]
Song, Jiupeng [1 ]
机构
[1] Xihua Univ, Sch Mat Sci & Engn, Chengdu 610039, Peoples R China
基金
中国国家自然科学基金;
关键词
Nuclear fusion; W-based PFM; He ion irradiation; Morphology; THERMAL-SHOCK RESISTANCE; LOW-ENERGY; MECHANICAL-PROPERTIES; BUBBLE FORMATION; SURFACE; MICROSTRUCTURE; EVOLUTION; BEHAVIOR; ALLOYS; STABILITY;
D O I
10.1016/j.mtcomm.2025.112002
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Nuclear fusion energy has been reckoned as a key solution to addressing global energy and environmental challenges. However, pure tungsten (PW), as the most promising plasma-facing materials (PFMs) is unsuitable for application in the future fusion reactors with more demanding environment due to its low recrystallization temperature (RCT), high ductile-to-brittle transition temperature (DBTT), and high irradiation-induced embrittlement susceptibility. This paper reviews the damage mechanisms of PW and the trending W-based candidate PFMs under helium ion (He+) irradiation, focusing on He bubble formation and irradiation-induced micro- structural evolution. It also provides a comprehensive assessment of recent advances and challenges in improving the irradiation resistance of W-based materials. This review aims to guide future research on W-based materials under He+ irradiation conditions.
引用
收藏
页数:9
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