Review of recent works in development and evaluation of high-Z plasma facing materials
Review of recent works in development and evaluation of high-Z plasma facing materials
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DOI：
10.1016/s0022-3115(98)00817-4
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发表时间：
1999-03
影响因子：
3.1
通讯作者：
N. Yoshida
中科院分区：
文献类型：
--
作者：
N. Yoshida
本文回顾了以钨及其合金为重点的新型高Z材料的开发和评估的最新活动和成果。通过在钨和基材之间插入复杂的多层扩散阻挡层 (W/Re)，石墨和 CFC 上的 VPS-W 涂层表现出卓越的高热负荷特性。为了成功应用，有必要了解铼和钨的再结晶和相互扩散的温度，这可能会降低粘合性能。必须考虑等离子体杂质的溅射和高能电荷交换中性物质的损坏。氢同位素的保留很大程度上取决于材料等级和生产工艺。氦轰击形成的密集气泡和位错可以作为氢的有效陷阱。预计氦的长程扩散会引起脆化。中子辐照是钨材料在聚变反应堆应用中的主要问题之一。迄今为止开发的钨材料在中子辐照下性能较差，其脆性可能限制其作为聚变材料的应用。需要进一步努力提高延展性，同时保持其他所需的性能，例如高导热性。
This paper reviews the recent activities and results in development and evaluation of new high-Z materials focusing on tungsten and its alloys. VPS-W coating on graphite and CFC showed superior high heat load properties by inserting sophisticated multilayer diffusion barriers (W/Re) between tungsten and substrate. For successful application it is necessary to know the temperatures for recrystallization and interdiffusion of rhenium and tungsten, which may degrade bonding properties. Sputtering by plasma impurities and damage by energetic charge-exchange neutrals must be considered. Retention of hydrogen isotopes strongly depends on material grade and production process. Dense bubbles and dislocations formed by helium bombardment may act as effective traps for hydrogen. It is anticipated that long range diffusion of helium induces embrittlement. Neutron irradiation is one of the major concerns for tungsten materials in fusion reactor application. The tungsten materials developed so far perform poorly under neutron irradiation and their brittle nature could limit their application as a fusion material. Further efforts are needed to improve ductility while keeping other desirable properties such as high thermal conductivity.