Plasma facing and high heat flux materials - needs for ITER and beyond
Plasma facing and high heat flux materials - needs for ITER and beyond
复制标题
DOI：
10.1016/s0022-3115(02)01175-3
复制
发表时间：
2002-12-01
影响因子：
3.1
通讯作者：
Sato, K
中科院分区：
文献类型：
--
作者：
Bolt, H;Barabash, V;Sato, K
面向等离子体的材料（PFMs）必须承受来自等离子体的粒子和热负荷以及反应堆运行期间的中子负荷。就热核实验堆而言，通过运行经验和目前托卡马克的专门测试以及实验室实验和建模积累了知识。介绍了在ITER中选择PFMs（Be，W，碳纤维增强碳）的基本原理，以及PFMs的关键问题，特别是瞬态热负荷下的腐蚀和碳再沉积的T-清单。在热核实验堆之后的聚变反应堆一代中，从等离子体中去除的表面功率增加、几年运行寿命要求、高中子注量和提高的运行温度等非常严格的条件对可能材料的选择施加了更严格的限制。将这些边界条件与正在开发的材料及其进一步潜力进行比较，关于散热器和PFMs，只剩下一条狭窄的道路。在这种情况下，正在讨论对W作为第一壁材料进行的研究，例如在ASDEX升级中进行的研究，以及W基材料系统的实验室结果。这些结果的影响是什么应该形成一个一致的计划，面向等离子体和热沉材料的聚变反应堆的起点。(C)2002 Elsevier Science B. V.保留所有权利。
Plasma-facing materials (PFMs) have to withstand particle and heat loads from the plasma and neutron loads during reactor operation. For ITER knowledge has been accumulated by operation experience and dedicated tests in present tokamaks as well as by laboratory experiments and modelling. The rationale for the selection of PFMs in ITER (Be, W, carbon fibre reinforced carbon) is described with regard to the critical issues concerning PFMs, esp. erosion during transient heat loads and the T-inventory in connection with the redeposition of carbon. In the fusion reactor generation after ITER the very stringent conditions of increased surface power to be removed from the plasma, a lifetime requirement of several operational years, high neutron fluences and increased operation temperature are exerting even more severe constraints on the selection of possible materials. Comparing these boundary conditions with materials under development and their further potential, only a narrow path is left regarding heat sink and PFMs. In this context the investigations on W as first wall material carried out e.g. in ASDEX Upgrade are being discussed as well as laboratory results on W-based material systems. The implications of these results are the starting point of what should form a consistent programme towards plasma-facing and heat sink materials for a fusion reactor. (C) 2002 Elsevier Science B.V. All rights reserved.