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金属学报  2019, Vol. 55 Issue (8): 939-950    DOI: 10.11900/0412.1961.2018.00405
  本期目录 | 过刊浏览 |
核聚变堆用W及其合金辐照损伤行为研究进展
吴玉程1,2,3()
1. 合肥工业大学材料科学与工程学院 合肥 230009
2. 合肥工业大学有色金属与加工技术国家地方联合工程研究中心 合肥 230009
3. 太原理工大学新材料界面科学与工程教育部重点实验室 太原 030024
Research Progress in Irradiation Damage Behavior of Tungsten and Its Alloys for Nuclear Fusion Reactor
Yucheng WU1,2,3()
1. School of Materials Science and Engineering, Hefei University of Technology, Hefei 230009, China
2. National-Local Joint Engineering Research Centre of Nonferrous Metals and Processing Technology, Hefei University of Technology, Hefei 230009, China
3. Key Laboratory of Interface Science and Engineering of New Materials, Ministry of Education, Taiyuan University of Technology, Taiyuan 030024, China
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摘要: 

受控热核聚变能作为一种清洁且原材料丰富的终极理想能源,被认为是未来能够有效解决能源问题的主要途径。而在实际聚变反应过程中,面向等离子体材料(plasma facing materials,PFMs)需要面临极其苛刻和恶劣的环境。W及其合金是目前最具有应用前途的PFMs的候选材料,但由于其低温脆性、再结晶脆性和辐照脆化等性能方面的不足,还不能达到PFMs的使用要求。本文对W及其合金在不同辐照粒子下的损伤行为的机制进行了详细阐述,并对相关领域近年来的研究进展进行了综合评述和展望,旨在为后期钨基材料辐照方面的研究提供参考。

关键词 核聚变W面向等离子体材料辐照损伤    
Abstract

Controlled thermonuclear fusion energy, regarded as the ultimate and ideal energy source, is considered as the principle way to effectively solve the future energy problem because of its cleaning and abundant raw materials. In the actual fusion reaction process, plasma facing materials (PFMs) will have to face the extremely harsh and severe environment. W and its alloys are the most promising PFMs candidate materials for the present reference design. However, due to its low-temperature brittleness, recrystallization brittleness, radiation-reduced brittleness and other disadvantages, they are still far from all the requirements of PFMs. In this paper, the principles of damage behavior under different irradiation particles were described in detail, and the research progress in related fields in recent years was also reviewed, in order to provide references for the research on the irradiation of W-based materials in the future.

Key wordsnuclear fusion    W    plasma facing material    irradiation damage
收稿日期: 2018-08-31     
ZTFLH:  TL34  
基金资助:国家重大基础研究磁约束核聚变项目(No.2014GB121001B);国家自然科学基金项目((Nos.51474083, 51574101, 51674095 and 51675154));高等学校学科创新引智计划项目(No.B18018)
通讯作者: 吴玉程     E-mail: ycwu@hfut.edu.cn
Corresponding author: Yucheng WU     E-mail: ycwu@hfut.edu.cn
作者简介: 吴玉程,男,1962年生,教授

引用本文:

吴玉程. 核聚变堆用W及其合金辐照损伤行为研究进展[J]. 金属学报, 2019, 55(8): 939-950.
Yucheng WU. Research Progress in Irradiation Damage Behavior of Tungsten and Its Alloys for Nuclear Fusion Reactor. Acta Metall Sin, 2019, 55(8): 939-950.

链接本文:

https://www.ams.org.cn/CN/10.11900/0412.1961.2018.00405      或      https://www.ams.org.cn/CN/Y2019/V55/I8/939

图1  W中(110)晶面处2~9个He原子聚集形成间隙氦原子层状结构的示意图[19]
图2  珊瑚状纳米丝和较高温度下树状纳米丝形成过程[28]
图3  W-TiC合金及商业W在5 keV、900 ℃氦辐照前后的TEM像[36]
图4  W、W-3%Re和W-5%Re试样fuzz结构截面图及3组试样的fuzz厚度分布图以及对应的SEM像[37]
图5  单空位中捕获不同数量H原子时的原子结构图及其最佳等值面示意图[45]
图6  W试样在同一辐照剂量(2.25×1021 m-2)、不同温度(500、600和800 ℃)下辐照后,H泡密度与平均直径曲线图及气泡直径分布区间图[47]
图7  快中子辐照下W中显微组织演变原理图[64,65]
图8  在不同辐照温度及剂量下各类缺陷对材料辐照硬化的影响[67]
图9  未损伤、300 K下0.2 dpa辐照剂量和1240 K下0.2 dpa辐照剂量试样的TDS图谱[79]
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