Assessment of tungsten for use in the ITER plasma facing components
Assessment of tungsten for use in the ITER plasma facing components
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DOI：
10.1016/s0022-3115(98)00285-2
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发表时间：
1998-10-01
影响因子：
3.1
通讯作者：
Slattery, KT
中科院分区：
文献类型：
--
作者：
Davis, JW;Barabash, VR;Slattery, KT
钨是国际热核实验反应堆（ITER）等离子体表面组件的候选铠装材料之一。对于本参考设计，选择钨作为偏滤器上部垂直靶、圆顶、暗盒衬里和下部挡板的铠装，因为与其他材料相比，钨具有独特的耐离子和电荷交换颗粒侵蚀的能力。本文描述了 ITER 中使用钨的相关问题。对被视为候选材料的不同钨牌号（纯钨、弥散强化钨和铸造合金）进行了评估。对不同热机械条件下各种钨牌号的机械性能进行了比较分析，包括辐照效应的影响。还描述了不同的钨装甲设计解决方案。 (C) 1998 Elsevier Science B.V. 保留所有权利。
Tungsten is one of the candidate armor materials for the plasma facing components of the International Thermonuclear Experimental Reactor (ITER). For the present reference design, tungsten has been selected as armor for the divertor upper vertical target, dome, cassette liner, and for lower baffle because of its unique resistance to ion and charge-exchange particle erosion in comparison with other materials. The issues related to the use of tungsten in ITER are described in this paper. The different tungsten grades (pure, dispersion strengthened and cast alloys) which are being considered as candidate materials are evaluated. A comparative analysis has been made of the mechanical properties of the various tungsten grades in different thermomechanical conditions, including the impact of irradiation effects. The different tungsten armor design solutions are also described. (C) 1998 Elsevier Science B.V. All rights reserved.