面向等离子体材料钨中氘/氦滞留行为的研究进展  

Research Progress on the Retention Behavior of Deuterium/Helium in Tungsten as a Plasma Facing Material

作　　者：王维[1,2] 叶小球[2] 陈长安[2] 李强[2] 金伟[2] 杨勇彬[2] 高涛[1] 

机构地区：[1]四川大学原子与分子物理研究所,成都610065 [2]表面物理与化学重点实验室,江油621908

出　　处：《材料导报》2017年第9期112-117,134,共7页Materials Reports

基　　金：国家磁约束聚变计划专项(2015GB109002);中国工程物理研究院科学技术发展基金(2014B0301048)

摘　　要：作为面向等离子体材料,钨(W)在服役的过程中不仅受到等离子体造成的高能热负荷的作用,还受到高束流粒子如氘(D)、氚(T)、氦(He)等的轰击和D-T聚变反应产生的高能中子的影响。W中D、T、He的滞留和起泡,仍是聚变堆装置中有待解决的关键问题之一。综述了D、T和He的滞留行为及其气泡形成与辐照条件之间的关系,简要评述了W的服役性能和强化机理。通过降低W中D/He滞留量、抑制气泡的形成可有效改善W的服役性能。深入研究D/He滞留行为与辐照缺陷之间的相互作用关系,进而构建D/He的宏观热脱附行为与其微观状态之间的对应关系,为寻找合适途径来改善W的服役性能提供理论支撑。Tungsten （W） as a plasma facing material （PFM） in the service process is not only affected by the plasma with high heat load, but also bombarded by the high-fluence particles such as deuterium （D）, tritium （T）, helium （He） and high-energy neutrons which produced by D-T fusion reaction. The retention and blister formation of D, T and He in tungsten are still one of the key issues needed to be solved in the fusion reactor. The correlation between the retention or blister formation and the irradiation conditions are reviewed to briefly elucidate the service performance and strengthening mechanism of W. The performance of W can be effectively improved by reducing the amount of D/He retention or inhibiting blister formation. Further study of the relationship between the retention behavior and irradiation defects are still needed to construct the correspondence between the macroscopic thermal desorption behavior and the microscopic state of D/He. These kinds of studies will provide theoretical supports for seeking suitable ways to enhance the service performance of W.

关 键 词：钨氘 氦 滞留 起泡 

分 类 号：TL627[核科学技术—核技术及应用] TB31[一般工业技术—材料科学与工程]