首页|聚变堆用W在等离子体作用下的辐照损伤行为研究进展

聚变堆用W在等离子体作用下的辐照损伤行为研究进展

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核聚变反应堆中,W因为其高熔点、高导热性、低溅射率和低氚(T)滞留等优势,成为面向等离子体材料中最有应用前景的候选材料.在服役过程中,W会受到低能高束流等离子体的辐照作用,导致材料表面产生微纳尺度的损伤结构,如表面起泡和表面纳米组织等,引起导热性能和力学性能下降,从而严重影响其再服役性能.本文聚焦于国内外关于氢/氘(H/D)等离子体作用下W的辐照损伤行为的研究现状,总结了气泡的形核和长大机制,以及辐照缺陷对导热、力学和再服役性能的影响机制,为W组织结构优化、性能预测和服役寿命评价提供理论基础.
Review of Irradiation Damage Behavior of Tungsten Exposed to Plasma in Nuclear Fusion
Tungsten is the most promising candidate as plasma facing material in nuclear fusion re-actors because of its high melting point,high thermal conductivity,low sputtering rate,and low tritium re-tention.However,when exposed to low-energy high flux plasma,tungsten undergoes micro/nanoscale damage,such as surface blistering and surface nanostructure,on its surface.These damage structures can degrade thermal and mechanical properties,thereby adversely affecting the reservice performance of tungsten.In this paper,the current research status of the damage behavior of tungsten when exposed to H/D plasma was focused.The research progress of the mechanisms of surface blistering nucleation and growth,as well as the effects of irradiation defects on thermal conductivity,mechanics,and service performance was summarized.These data can provide a theoretical basis for optimizing the microstruc-ture of tungsten materials,thus improving its service performance and extending its service life.

nuclear fusiontungstenplasmairradiation damageservice performance

刘伟、陈婉琦、马梦晗、李恺伦

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清华大学 材料学院 北京 100084

中国核电工程有限公司 北京 100840

中国科学院工程热物理研究所 北京 100190

核聚变 W 等离子体 辐照损伤 服役性能

国家自然科学基金

12105314

2023

金属学报
中国金属学会

金属学报

CSTPCDCSCD北大核心
影响因子:0.925
ISSN:0412-1961
年,卷(期):2023.59(8)
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