Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials
Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials
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DOI：
10.1016/j.jnucmat.2013.02.074
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发表时间：
2013-11-01
影响因子：
3.1
通讯作者：
Pippan, R.
中科院分区：
文献类型：
--
作者：
Wurster, S.;Baluc, N.;Pippan, R.
钨材料由于其优越的上级热物理性能而成为国际热核实验反应堆和DEMOnstration发电厂等离子体组件的候选材料。由于这些材料不是像钢这样的常见结构材料，因此改善其性能的知识和策略仍在开发中。这里讨论的这些策略包括新的合金化方法和通过氧化物弥散强化以及TiC稳定的钨基材料的微观结构稳定。采用钨层压材料和钨丝增强材料改善了断裂性能。材料的发展伴随着中子辐照活动。自钝化是面向等离子体的材料在冷却剂损失事故中必不可少的，可以通过一定量的铬和钛来实现。此外，建模和计算机模拟的合金元素和热负荷和氦轰击的影响将被提交。(C)2013爱思唯尔有限公司版权所有。
Tungsten materials are candidates for plasma-facing components for the International Thermonuclear Experimental Reactor and the DEMOnstration power plant because of their superior thermophysical properties. Because these materials are not common structural materials like steels, knowledge and strategies to improve the properties are still under development. These strategies discussed here, include new alloying approaches and microstructural stabilization by oxide dispersion strengthened as well as TiC stabilized tungsten based materials. The fracture behavior is improved by using tungsten laminated and tungsten wire reinforced materials. Material development is accompanied by neutron irradiation campaigns. Self-passivation, which is essential in case of loss-of-coolant accidents for plasma facing materials, can be achieved by certain amounts of chromium and titanium. Furthermore, modeling and computer simulation on the influence of alloying elements and heat loading and helium bombardment will be presented. (C) 2013 Elsevier B.V. All rights reserved.