聚变堆用W在等离子体作用下的辐照损伤行为研究进展
Review of Irradiation Damage Behavior of Tungsten Exposed to Plasma in Nuclear Fusion
聚变堆用W在等离子体作用下的辐照损伤行为研究进展 |
| 刘伟, 陈婉琦, 马梦晗, 李恺伦 |
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Review of Irradiation Damage Behavior of Tungsten Exposed to Plasma in Nuclear Fusion |
| LIU Wei, CHEN Wanqi, MA Menghan, LI Kailun |
| 图2 D等离子体(943 K)分别在1.55 × 1026、4.21 × 1026和7.05 × 1026 m-2辐照条件下W样品表面形貌及表面气泡尺寸和密度分布统计[ |
| Fig.2 Surface morphologies of W samples exposed to D plasma (943 K) at irradiation doses of 1.55 × 1026 m-2 (a), 4.21 × 1026 m-2 (b), and 7.05 × 1026 m-2 (c); and surface bubble size and density distribution statistics (d)[ |
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