Material Mixing of Tungsten with Carbon and Helium

被引：3
作者：
Ueda, Y. [1 ]
Lee, H. T. [1 ]
机构：
[1] Osaka Univ, Grad Sch Engn, Osaka 5650871, Japan
来源：
PLASMA INTERACTION IN CONTROLLED FUSION DEVICES | 2010年 / 1237卷
关键词：
material mixing; tungsten; carbon; helium; PLASMA-FACING COMPONENTS; ASDEX UPGRADE DIVERTOR; ITER-LIKE WALL; DEUTERIUM RETENTION; HYDROGEN RETENTION; SIMULTANEOUS BOMBARDMENT; MIXED-MATERIAL; TEST LIMITERS; CHEMICAL BEHAVIOR; DYNAMIC-BEHAVIOR;
D O I：
10.1063/1.3447996
中图分类号：
O59 [应用物理学];
学科分类号：
摘要：
In ITER, graphite and tungsten are used for divertor materials and are mixed through erosion, transport, and redeposition. Helium, a fusion reactant, is an intrinsic element in fusion plasmas that impinges on the metallic wall materials to form He bubbles. W-C mixed layers and He bubble layers greatly affect tritium retention. In this paper, impacts of W-C material mixing on erosion and hydrogen isotope retention are reviewed. Then, recent results on carbon deposition on tungsten in TEXTOR tokamak and helium effects on blistering and retention are discussed.
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页码：92 / 105
页数：14
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