High heat flux testing of plasma facing materials and components -: Status and perspectives for ITER related activities
High heat flux testing of plasma facing materials and components -: Status and perspectives for ITER related activities
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DOI：
10.1016/j.jnucmat.2007.04.028
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发表时间：
2007-08-01
影响因子：
3.1
通讯作者：
Suzuki, S.
中科院分区：
文献类型：
--
作者：
Linke, J.;Escourbiac, F.;Suzuki, S.
广泛的高热流密度测试设备正在世界范围内用于研究等离子体表面材料和组件对聚变相关热负荷的热响应。这些测试既包括循环热负荷和功率密度在几MW m（-2）范围内的正常运行场景，也包括模拟边缘局部模式、等离子体中断和垂直位移等短事件的瞬态热负荷测试。在ITER的采购阶段，迫切需要可靠的质量控制方法和无损分析；这些技术大多是基于热通量法。为了量化辐照引起的性能变化和评估中子辐照组件的整体性能，在裂变反应堆中辐照了小型化等离子体面组件并对其辐照后进行了测试。此外，为了研究热载荷和中子载荷的协同效应，还进行了桩内试验。(C) 2007 Elsevier B.V.版权所有
A broad spectrum of high heat flux test facilities are being used worldwide to investigate the thermal response of plasma facing materials and components to fusion relevant thermal loads. These tests cover both normal operation scenarios with cyclic thermal loads and power densities in the range of several MW m(-2) and transient heat load tests to simulate short events such as edge localized modes, plasma disruptions and vertical displacement events. There is an urgent need for reliable quality control methods and non-destructive analyses during the procurement phase of ITER; most of these techniques are based on heat flux methods. To quantify irradiation induced property changes and to evaluate the overall performance of neutron irradiated components, miniaturized plasma facing components have been irradiated in fission reactors and post-irradiation tested. Furthermore, in-pile tests have been carried out in order to study the synergetic effects of heat loads and neutron loads. (C) 2007 Elsevier B.V. All rights reserved.