不同辐照粒子下钨及钨合金辐照损伤行为的研究进展

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。

Progress in Irradiation Damage of Tungsten and Tungsten Alloys Under Different Irradiation Particles

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.