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《材料导报》期刊社  2018, Vol. 32 Issue (1): 41-46    https://doi.org/10.11896/j.issn.1005-023X.2018.01.004
     材料与可持续发展(一)—— 面向洁净能源的先进材料 |
不同辐照粒子下钨及钨合金辐照损伤行为的研究进展
罗来马1,2(),徐梦瑶1,昝祥1,2,朱晓勇2,3,李萍1,2,程继贵1,2,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 安徽省有色金属材料与加工工程实验室,合肥 230009
3 有色金属与加工技术国家地方联合工程研究中心,合肥 230009
Progress in Irradiation Damage of Tungsten and Tungsten AlloysUnder Different Irradiation Particles
Laima LUO1,2(),Mengyao XU1,Xiang ZAN1,2,Xiaoyong ZHU2,3,Ping LI1,2,Jigui CHENG1,2,Yucheng WU1,2,3
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 230009
3 National-Local Joint Engineering Research Centre of Nonferrous Metals and Processing Technology, Hefei 230009
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摘要 

研究核聚变、准稳态等离子体下面向等离子体材料的辐照行为,发展适合于先进实验超导托卡马克(EAST)、国际热核聚变实验堆(ITER)和中国聚变工程实验堆(CFETR)长脉冲高参数运行乃至未来聚变反应堆稳态运行的高性能面向等离子体材料是当前核聚变研究一项艰巨而又紧迫的任务。钨因具有高熔点、高导热率、低溅射腐蚀速率、高自溅射阀值以及低蒸气压和低氚滞留等优异性能,被认为是聚变装置最具有前景的面向等离子体材料。综合评述了钨及钨合金在不同辐照粒子下损伤行为的最新研究进展。粒子辐照造成的微观缺陷在钨及钨合金内部累积,辐照造成缺陷的形成和数量与钨基材料颗粒微观结构、第二相成分等密切相关,辐照缺陷情况各异。同时,辐照粒子种类、能量、剂量和温度等辐照条件都会对钨材料辐照后的形貌特征和缺陷产生重要影响。

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罗来马
徐梦瑶
昝祥
朱晓勇
李萍
程继贵
吴玉程
关键词:    核聚变堆  辐照损伤  面向等离子体材料    
Abstract: 

It is difficult and urgent task to develop a high-performance plasma facing materials for current nuclear fusion research by the irradiation behavior of PFMs, which is suitable for advanced experiment superconducting tokamak (EAST), international thermonuclear fusion reactor (ITER) and China fusion engineering experiment reactor (CFETR). Tungsten is considered to be the primary candidate for plasma facing materials in future fusion reactors owing to its superiority to other materials including high melting point, high thermal conductivity, low sputter corrosion rate, high sputtering threshold, low vapor pressure and low tritium inventory. In this paper, we review the research progress of damage of tungsten and tungsten alloy irradiated by various particles. The defects caused by irradiation are accumulate in tungsten and tungsten alloy. The formation and quantity of defects are closely related to the microstructure of the tungsten and the second phase components, the situation of defects are diverse. At the same time, the irradiation conditions, for instance, the kinds of particles, energy, flux and temperature, will also have an important impact on the morphology and defect of the irradiated sample.

Key words:  tungsten    nuclear fusion reactor    radiation damage    plasma facing materials
               出版日期:  2018-01-10      发布日期:  2018-01-10
ZTFLH:  TG146.4  
基金资助: 国际热核聚变实验堆(ITER计划专项2014GB121001B);国家自然基金面上项目(51474083)
作者简介:  罗来马:男,1980年生,副教授,硕士研究生导师,主要从事核聚变材料研究 E-mail: luolaima@126.com
引用本文:    
罗来马, 徐梦瑶, 昝祥, 朱晓勇, 李萍, 程继贵, 吴玉程. 不同辐照粒子下钨及钨合金辐照损伤行为的研究进展[J]. 《材料导报》期刊社, 2018, 32(1): 41-46.
Laima LUO, Mengyao XU, Xiang ZAN, Xiaoyong ZHU, Ping LI, Jigui CHENG, Yucheng WU. Progress in Irradiation Damage of Tungsten and Tungsten AlloysUnder Different Irradiation Particles. Materials Reports, 2018, 32(1): 41-46.
链接本文:  
http://www.mater-rep.com/CN/10.11896/j.issn.1005-023X.2018.01.004  或          http://www.mater-rep.com/CN/Y2018/V32/I1/41
Majorplasma
parameters
Thenumberofparticlesand
energyperunitarea
Maximumfluxofplasma 1.0×1024/(m2·s)
Heatload 5—10MW/m2
Averageneutronwallload 0.56(0.8)MW/m2
Temperatureofplasmasurface 200—1000℃
表1  面向等离子体材料所承受的辐照条件[6]
图1  He离子辐照超细晶钨的TEM图:(a)棒状纳米结构,(b)棒状纳米结构的高分辨图,(c)棒状结构间的氦泡,(d)样品表面下10 nm区域
图2  不同能量He+辐照后钨的横截面SEM图:(a) 2.3×1021/(m2·s),(b)5.4×1021/(m2·s),(c)7.7×1021/(m2·s),(d)1.0×1022/(m2·s),(e)1.3×1022/(m2·s),(f)1.6×1022/(m2·s)
图3  H+-C+混合离子束辐照样品的表面形貌图:(a)未预辐照,(b)300 keV H-辐照,(c)700 keV H-辐照
图4  不同钨材料辐照前TEM图:(a)纯钨,(b)钨铼合金,(c)钨钾合金,(d)超细晶W-0.5TiC/H
图5  不同钨材料辐照后TEM图:(a)纯钨,(b)钨铼合金,(c)钨钾合金,(d)超细晶W-0.5TiC/H
图6  辐照后钨的高分辨透射图:(a)含α相和β相的晶粒,(b)30 dpa辐照后α粗晶,(c、d)粗晶间隙区域空位图,(e)100 dpa辐照后图像
图7  0.89 dpa辐照样品的损伤区域的明场像
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