Overview

Review of Irradiation Damage Behavior of Tungsten Exposed to Plasma in Nuclear Fusion

  • LIU Wei ,
  • CHEN Wanqi ,
  • MA Menghan ,
  • LI Kailun
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  • 1School of Materials Science and Engineering, Tsinghua University, Beijing 100084, China
    2CNNC China Nuclear Power Engineering Co., Ltd., Beijing 100840, China
    3Institute of Engineering Thermophysics, Chinese Academy of Sciences, Beijing 100190, China
LIU Wei, professor, Tel:13910677301, E-mail: liuw@mail.tsinghua.edu.cn

Received date: 2023-02-27

  Revised date: 2023-05-02

  Online published: 2023-05-30

Supported by

National Natural Science Foundation of China(12105314)

Abstract

Tungsten is the most promising candidate as plasma facing material in nuclear fusion reactors because of its high melting point, high thermal conductivity, low sputtering rate, and low tritium retention. 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 microstructure of tungsten materials, thus improving its service performance and extending its service life.

Cite this article

LIU Wei , CHEN Wanqi , MA Menghan , LI Kailun . Review of Irradiation Damage Behavior of Tungsten Exposed to Plasma in Nuclear Fusion[J]. Acta Metall Sin, 2023 , 59(8) : 986 -1000 . DOI: 10.11900/0412.1961.2023.00078

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