磁控核聚变装置中钨基合金面向等离子体材料的研究现状与进展  

Present Situation and Research Progress of Tungsten-based Alloy Plasma-facing Materials in Magnetron Nuclear Fusion Devices

作　　者：杨毅超 李延超[1,2] 李雅馨 林小辉 高选乔[1] 李来平 YANG Yichao;LI Yanchao;LI Yaxin;Lin Xiaohui;GAO Xuanqiao;LI Laiping(Northwest Institute For Non-Ferrous Metal Research,Xi'an 710016,Shaanxi,China;School of Materials Science and Engineering,Xi’an University of Technology,Xi'an 710048,Shaanxi,China)

机构地区：[1]西北有色金属研究院,陕西西安710016 [2]西安理工大学材料科学与工程学院,陕西西安710048

出　　处：《中国钨业》2020年第6期72-80,共9页China Tungsten Industry

基　　金：科技部国家重点研究和发展项目(2017YFB0306003);陕西省重点产业创新链(2020 ZDLGY12-08);陕西省创新能力支撑计划(2019KJXX-071);陕西省科技重大项目(2020 ZDZX 04-02-02)

摘　　要：综述了国内外ODS、CDS、合金强化、W纤维复合强化等钨基面向等离子体材料以及辐照性能的研究进展。Y_(2)O_(3)和La_(2)O_(3)的添加限制了钨合金晶粒的成长,适度地添加有助于钨合金的抗拉强度,添加了质量分数为0.8%的W合金相比同样工艺的纯W在1273 K至1973 K温度区间有更高的抗拉伸性能,但延伸率较低。La_(2)O_(3)的添加对于W合金抗中子辐照无明显帮助,含有质量分数为0.5%的W合金锻造面裂纹阈值范围比横截面高。添加TiC所形成的超细晶钨合金拥有较纯钨弯曲断裂强度高75%,且中子辐照后缺陷密度较低。添加ZrC的钨合金在D辐照中氢的滞留量较纯钨明显下降,同时耐He+离子辐照能力较强;HIP技术制备的W-V合金有不错的强度,但塑脆转变温度和塑性较纯钨未有明显变化,对氢泡长大具有显著抑制作用,但氢滞留较高;W-Re对比纯W塑性提高,DBTT降低,但强度、导热率等均有下降,在高剂量中子辐照中抗辐照能力下降;ZrO_(x)作为Wf/W复合材料界面涂层展现了不错的热稳定性;Zr/Cr比值为1∶2的W-Cr-Zr合金拥有出色的抗氧化性能。This paper reviews the research progress of plasma-facing tungsten materials,such as ODS,CDS,alloy strengthening and W fiber composite strengthening,and their irradiation properties at home and abroad.The addition of Y_(2)O_(3) and La_(2)O_(3) limits the grain growth of tungsten alloy,and moderate addition contributes to the tensile strength of tungsten alloy.compared with pure W with the same process,W alloy with 0.8%mass fraction has higher tensile properties in the temperature range from 1273 K to 1973 K,but its elongation is lower.The addition of La_(2)O_(3) has no obvious effect on the neutron irradiation resistance of W alloy,and the threshold range of forging surface crack of W alloy containing 0.5%by mass is higher than that of cross section.The ultra-fine grained tungsten alloy formed by adding TiC has 75%higher bending fracture strength than pure tungsten,and the defect density is lower after neutron irradiation.Compared with pure tungsten,the hydrogen retention of tungsten alloy with ZrC in d irradiation is obviously lower,and the ability of resisting He+ion irradiation is stronger;W-V alloy prepared by HIP technology has good strength,but the plastic-brittle transition temperature and plasticity have no obvious changes compared with pure tungsten,which has a significant inhibitory effect on hydrogen bubble growth,but hydrogen retention is higher;Compared with pure W,W-Re has higher plasticity,lower DBTT,lower strength and thermal conductivity,and lower radiation resistance in high dose neutron irradiation.ZrO_(x),as the interface layer of Wf/W composites,shows good thermal stability.W-Cr-Zr alloy with Zr/Cr ratio of 1∶2 has excellent oxidation resistance.

关 键 词：钨基合金 面向等离子体 托卡马克装置 辐照 

分 类 号：TF841.1[冶金工程—有色金属冶金] TL627[核科学技术—核技术及应用]