Recent studies of tungsten-based plasma-facing materials in the linear plasma device STEP
Recent studies of tungsten-based plasma-facing materials in the linear plasma device STEP
复制标题
DOI：
10.1007/s42864-019-00004-x
复制
发表时间：
2019-04
期刊：
影响因子：
--
通讯作者：
Hao Yin;Jun Wang;Wangguo Guo;Long Cheng;Yue Yuan;G. Lu
中科院分区：
文献类型：
--
作者：
Hao Yin;Jun Wang;Wangguo Guo;Long Cheng;Yue Yuan;G. Lu
本文综述了近年来在托卡马克边缘等离子体模拟器（STEP）等线性等离子体装置中钨基等离子体材料的研究进展，重点研究了新开发的钨基材料和纯钨的等离子体诱导缺陷。将纯W、W- v、W- y2o3和W- zrc样品暴露在~ 1021 ~ 1022m−2s−1的高通量等离子体中，表面温度低于500 K，通量高达1026m−2。纯W等离子体诱导缺陷的基本演化研究表明，氢位错相互作用起着关键作用。在所有w基材料中都观察到抑制表面起泡，但不同材料的氘脱附行为和保留是不同的。研究表明，像STEP这样的线性等离子体装置对于理解等离子体-材料相互作用和确定未来聚变反应堆的新材料是必不可少的。
This contribution summarized the recent studies of tungsten-based plasma-facing materials in the linear plasma device like the simulator for tokamak edge plasma (STEP), focusing on the examination of newly developed tungsten (W)-based materials and plasma-induced defects in pure W. Pure W, W-V, W-Y2O3and W-ZrC samples were exposed to a high-flux plasma of ~ 1021–1022m−2s−1with a fluence up to 1026m−2at a surface temperature below 500 K. The investigation of fundamental evolution of plasma-induced defects in pure W indicated a critical role of hydrogen-dislocation interactions. Suppressed surface blistering was observed in all W-based materials, but deuterium desorption behavior and retention were distinct with respect to different materials. The studies showed that the linear plasma device like the STEP was indispensable in the understanding of plasma-material interactions and the qualification of new materials for future fusion reactors.