Plasma-facing materials for thermo-nuclear fusion devices
Plasma-facing materials for thermo-nuclear fusion devices
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DOI：
10.1007/s12666-009-0016-y
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发表时间：
2009-07
影响因子：
1.6
通讯作者：
L. Singheiser;T. Hirai;J. Linke;G. Pintsuk;M. Rödig
中科院分区：
文献类型：
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作者：
L. Singheiser;T. Hirai;J. Linke;G. Pintsuk;M. Rödig
在现有的和未来的聚变装置中，等离子体壁相互作用过程对面向等离子体的材料和部件有很大的影响。这些部件，特别是第一壁（FW）、限制器和偏滤器在等离子体操作期间经受强烈的准静态热负荷。虽然第一壁的热负荷将保持在1 MW·m−2以下，但必须特别注意限制器和偏滤器等高热通量部件。在这里，预期的功率密度将比FW的功率密度高出至少一个数量级，未来磁约束装置的预期峰值热通量高达20 MW·m− 2。除了准稳态热负荷外，沉积能量密度高达几十MJ·m− 2的短瞬态热脉冲是下一步托卡马克装置，特别是ITER的另一个重要问题。最严重的事件是等离子体破裂、垂直位移事件和边缘局域模（所谓的ELM）。这些要求对主动冷却面向等离子体部件的合格材料和可靠制造工艺的选择提出了很高的要求。基于强电子和离子束的高热通量测试设备已成功用于评估不同材料解决方案和设计概念的效率和疲劳寿命。正在进行正常操作场景和瞬态事件的建模和实验，以评估和量化由此产生的材料侵蚀或损坏，从而评估组件的使用寿命。其他研究活动的重点是由于高能中子的材料和关节的退化。为了研究辐照引起的性能变化，材料样品和主动冷却的等离子体面对组件已在裂变反应堆中辐照和热负荷试验测试。目前考虑的技术解决方案主要基于铍、碳材料或钨作为装甲材料，铜合金或不锈钢作为散热器。此外，还将强调在采购阶段需要广泛的质量控制方法和非破坏性分析。
The plasma facing materials and components in existing and future fusion devices are strongly affected by plasma wall interaction processes. These components, in particular the first wall (FW), the limiters and the divertor are subject to intense quasi-stationary thermal loads during plasma operation. While the resulting thermal loads to the first wall will remain below 1 MW·m−2, special attention has to be paid to high heat flux components like limiters and the divertor. Here the expected power densities will be at least one order of magnitude above the ones at the FW, with expected peak heat fluxes of up to 20 MW·m−2for future magnetic confinement devices. Beside quasi-stationary heat loads, short transient thermal pulses with deposited energy densities up to several tens of MJ·m−2are another serious concern for next step tokamak devices, in particular for ITER. The most serious events are plasma disruptions, vertical displacement events, and Edge Localized Modes (so-called ELMs). These requirements make high demands on the selection of qualified materials and reliable fabrication processes for actively cooled plasma facing components. High heat flux test facilities based on intense electron and ion beams have been utilized successfully to assess the efficiency and the fatigue life time of different material solutions and design concepts. Modeling and experiments with both normal operation scenarios and transient events, are being performed to evaluate and to quantify the resulting material erosion or damage and thus to assess the life time of the components. Additional research activities are focused on the degradation of materials and joints due to energetic neutrons. In order to investigate irradiation induced property changes, materials samples and actively cooled plasma facing components have been irradiated in fission reactors and tested in thermal load tests. The technical solutions which are considered today are mainly based on beryllium, carbon materials or tungsten as armor materials and copper alloys or stainless steel for the heat sink. Furthermore, the needs for extensive quality control methods and non-destructive analyses during the procurement phase will be highlighted.