ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces
ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces
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DOI：
10.2320/matertrans.46.412
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发表时间：
2005-03
影响因子：
1.2
通讯作者：
T. Hirai;K. Ezato;P. Majerus
中科院分区：
文献类型：
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作者：
T. Hirai;K. Ezato;P. Majerus
目前的ITER设计采用铍、碳纤维增强复合材料和钨作为等离子体面对材料。由于这些材料在运行过程中暴露于高热流密度下，因此对ITER部件的研发进行高热流密度测试是必不可少的。与正常运行期间的循环负荷相对应的静态热负荷估计在偏滤器靶中高达20 MW/m2，在ITER的第一壁处约为0.5 MW/m2。对于静态高热流测试，已经进行了电子束设备、粒子束设备、红外加热器和堆内测试。另一种类型，更临界的热负荷，其具有高功率密度和短持续时间，对应于瞬态事件，即等离子体破裂、垂直位移事件（VDE）和边缘局部模式（ELM），将相当大的热通量传递到面向等离子体的材料上。为此，在电子束（短脉冲），等离子体枪和高功率激光设备进行了测试。本文综述了这些装置的特点和最近的实验结果，以及当前ITER等离子体面对部件的选择。
The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials. Since these materials are exposed to high heat fluxes during the operation, it is essential to perform high heat flux tests for R&D of ITER components. Static heat loads corresponding to cycling loads during normal operation, are estimated to be up to 20 MW/m 2 in the divertor targets and around 0.5 MW/m 2 at the first wall in ITER. For the static high heat flux testing, tests in electron beam facilities, particle beam facilities, IR heater and in-pile tests have been performed. Another type, more critical heat loads, which have high power densities and short durations, corresponding to transient events, i.e. plasma disruption, vertical displacement events (VDEs) and edge localized modes (ELMs) deliver considerable heat flux onto the plasma facing materials. For this purpose, tests in electron beam (short pulses), plasma gun and high power laser facilities have been carried out. The present work summarizes the features of these facilities and recent experimental results as well as the current selection of ITER plasma facing components.