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机械工程学报

机械工程学报 ›› 2017, Vol. 53 ›› Issue (8): 25-34.doi: 10.3901/JME.2017.08.025

• • 上一篇    下一篇

面向等离子体钨基材料的辐照损伤行为研究现状

吴玉程1,2, 林锦山1, 罗来马1,2, 昝祥1,2, 朱晓勇1,2, 陈俊凌3   

  1. 1. 合肥工业大学材料科学与工程学院 合肥 230009；
    2. 合肥工业大学安徽省有色金属材料与加工工程实验室 合肥 230009；
    3. 中国科学院等离子体物理研究所 合肥 230031
  • 出版日期:2017-04-15 发布日期:2017-04-15
  • 作者简介:

    吴玉程(通信作者)，男，1962年出生，博士研究生导师。主要研究方向为有色金属材料与加工技术，能源材料。

    E-mail：ycwu@hfut.edu.cn

  • 基金资助:
    * 国际热核聚变实验堆(ITER)计划专项(2014GB121001)和国家自然科学基金面上(51474083，51574101)资助项目; 20160321收到初稿，20161101收到修改稿;

Irradiation Damage Behavior Research Status of Tungsten-matrix Materials Facing Plasma

WU Yucheng1,2, LIN Jinshan1, LUO Laima1,2, ZAN Xiang1,2, ZHU Xiaoyong1,2, CHEN Junling3   

  1. 1. College of Material Science and Engineering， Hefei University of Technology， Hefei 230009;
    2. Laboratories of Nonferrous Metal Material and Processing Engineering of Anhui Province， Hefei University of Technology， Hefei 230009;
    3. Institute of Plasma Physics， Chinese Academic Sciences， Hefei 230031
  • Online:2017-04-15 Published:2017-04-15

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摘要：

解决人类能源问题的重要途径之一就是开发受热控核聚变能。在受热控核聚变反应堆装置中，钨作为优选最有前途的面向等离子体第一壁材料，具备这许多优良特性，如高熔点、高热导率、良好的高温强度等。然而钨基材料在离子中子辐照下会导致微观结构的改变，例如气泡、孔洞、纳米结构的形成。辐照还会导致材料硬化并使材料变脆。钨的辐照损伤问题是钨作为面向等离子体第一壁材料要重点解决的问题之一。通过改变材料的结构和成分设计可以改变钨的抗辐照性能。国内外许多研究人员对纯钨、碳化物掺杂钨、氧化物掺杂钨以及其他钨基材料的辐照损伤行为进行相关研究。对这些相关的研究进展和趋势进行综述。

关键词: 辐照损伤, 钨基材料, 面向等离子体材料

Abstract:

One of the important way to solve the problem of human energy is to exploit controlled thermonuclear fusion energy. In controlled thermonuclear nuclear fusion reactor device, tungsten as the selection of the most promising for the first wall materials facing plasma have many good qualities, such as high melting point, high thermal conductivity, good high temperature strength, etc.However, the irradiation of ion and neutron for tungsten-matrix materials will lead to the change of microstructure, such as the formation of bubbles, holes, nanostructure. Irradiation can also make the materials hardening and become brittle. The irradiation damage problem of tungsten materials as the first wall materials facing plasma is one of the key problem to solve. By changing the structure and the composition design of tungsten materials can change its radiation resistance. Many researchers of home and aboard have studied the irradiation damage behavior for the pure tungsten, carbide doped tungsten, oxide doped tungsten and other tungsten-matrix materials. The progress and trends of these related studies are reviewed.

Key words: irradiation damage, tungsten-matrix materials, plasma facing materials

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