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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