PW和W-Zr-Y_(2)O_(3)耐氘等离子体辐照性能研究  

Surface Blistering and Deuterium Retention Behavior of PW and W-Zr-Y_(2)O_(3) Exposed to D Plasma in EAST Tokamak

作　　者：张群 刘凤 曹茹 徐玉平 周海山 罗广南[2] ZHANG Qun;LIU Feng;CAO Ru;XU Yuping;ZHOU Haishan;LUO Guangnan(School of Science,Nanjing University of Science and Technology,Nanjing 210094,Jiangsu,China;Institute of Plasma Physics,Chinese Academy of Sciences,Hefei 230031,Anhui,China)

机构地区：[1]南京理工大学理学院,江苏南京210094 [2]中国科学院等离子体物理研究所,安徽合肥230031

出　　处：《中国钨业》2021年第5期42-47,共6页China Tungsten Industry

基　　金：国家自然科学基金青年项目(11705232)。

摘　　要：利用东方超环(EAST)装置中的材料与等离子体评价系统开展了氘(D)等离子体辐照试验,考察多种钨(W)材料在D等离子体辐照前后的形貌变化与D滞留行为。材料分别为纯钨PW-AT、纯钨PW-BK和掺杂钨W-Zr-Y_(2)O_(3),采用扫描电子显微镜(SEM)分析样品形貌变化,通过热脱附谱仪(TDS)对D滞留行为进行测量分析。SEM结果表明W-Zr-Y_(2)O_(3)具有更良好的抗D等离子体辐照起泡/开裂性能;TDS分析指出W-Zr-Y_(2)O_(3)辐照后的D滞留量最低。W-Zr-Y_(2)O_(3)具有等轴细晶组织以及较低的氧杂质含量可能是其性能优于PW-AT和PW-BK的主要原因。The main purpose of this study is to investigate the surface morphology change and deuterium(D)retention behavior in recently developed tungsten(W)materials after D plasma exposure in the EAST tokamak.The W studied were PW-AT,PW-BK and W-Zr-Y_(2)O_(3),developed in China.Morphology changes were analyzed by Scanning Electron Microscopy(SEM)and deuterium retention behavior were measured by Thermal Desorption Spectroscopy(TDS).Results indicated that W-Zr-Y_(2)O_(3) showed less surface blistering/cracking and had the lowest D retention.The equiaxed fine grain structure and better control of oxygen impurity of W-Zr-Y_(2)O_(3) may result in its superior properties than that of PW-AT and PW-BK.

关 键 词：钨材料 氘等离子体辐照 表面起泡/开裂 氘滞留 聚变堆材料 

分 类 号：TG146.411[一般工业技术—材料科学与工程] TL627[金属学及工艺—金属材料]