• CN:11-2187/TH
  • ISSN:0577-6686

机械工程学报 ›› 2018, Vol. 54 ›› Issue (8): 117-128.doi: 10.3901/JME.2018.08.117

• 材料科学与工程 • 上一篇    下一篇

合金化改性钨基材料的组织和性能研究与发展

罗来马1,2, 黄科1, 昝祥1,2, 朱晓勇2,3, 李萍1,2, 吴玉程1,2,3   

  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. 合肥工业大学有色金属与加工技术国家地方联合工程研究中心 合肥 230009
  • 收稿日期:2017-06-15 修回日期:2017-10-05 出版日期:2018-04-20 发布日期:2018-04-20
  • 通讯作者: 吴玉程(通信作者),男,1962年出生,博士,教授,博士研究生导师。主要从事有色金属与纳米元器件相关研究。E-mail:ycwu@hfut.edu.cn
  • 作者简介:罗来马,男,1980年出生,副教授,硕士研究生导师。主要从事核聚变材料研究。E-mail:luolaima@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(51474083,51574101,51674095,51675154)资助项目。

Research and Development of Alloy Modified Tungsten-based Materials

LUO Laima1,2, HUANG Ke1, ZAN Xiang1,2, ZHU Xiaoyong2,3, LI Ping1,2, WU Yucheng1,2,3   

  1. 1. School of Materials 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. National-Local Joint Engineering Research Centre of Nonferrous Metals and Processing Technology, Hefei University of Technology, Hefei 230009
  • Received:2017-06-15 Revised:2017-10-05 Online:2018-04-20 Published:2018-04-20

摘要: 开发受控核聚变能源是一种解决未来能源问题的有效途径。多年来国内外研究发现,钨具有高熔点、高热导率、低物理溅射率、低氚滞留、低肿胀等优点,被认为是最有潜力作为第一壁的候选材料。应用于核聚变反应堆极端环境中的材料,要求具有良好的抗氧化性能、力学性能、抗辐照性能等综合性能。但钨的抗氧化性能较差、再结晶温度较低、脆韧转变温度较高和辐照敏感性,实际应用中还有许多待解决之处。因此需要通过合金化,掺杂第二相弥散强化和制备超细晶钨的手段改善钨基材料性能。合金化是最常用的改善钨基体材料性能的手段之一。结合了近些年来研究成果,综述了掺杂合金元素对钨基材料性能方面的改善效果、作用机理以及分析了未来的发展趋势。

关键词: 合金元素, 核聚变堆, 钨基材料

Abstract: Development of controlled nuclear fusion energy is an effective solution to solve the problem of future energy. In recent years many experimental studies home and abroad find that pure tungsten has many advantages, such as high melting point, high heat conductivity, low physical sputtering rate, low tritium retention and low swelling, etc. Applied in extreme environments of nuclear fusion reactors, the material requires good overall properties such as oxidation resistance, mechanical properties, anti-irradiation properties, etc. However there are also some problems to be solved. For example, lower oxidation resistance, low recrystallization temperature, high ductile-brittle transition temperature and irradiation sensitivity. Therefore W-based materials' properties were improved via doping alloying elements or stable dispersed phases and fabricating ultra-fine grain tungsten, etc. Alloying is one of the most common methods to improve the performance of tungsten-based materials. This paper summarizes the research results in recent years. This review focuses on the change of properties and the correlative mechanism of alloyed tungsten-based materials and analyzes the development trend in future.

Key words: alloying elements, nuclear fusion reactor, tungsten-matrix materials

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