Review of Recent Progress in Plasma-Facing Material Joints and Composites in the FRONTIER U.S.-Japan Collaboration

Review of Recent Progress in Plasma-Facing Material Joints and Composites in the FRONTIER U.S.-Japan Collaboration
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美日前沿合作中面向等离子体材料接头和复合材料的最新进展回顾

DOI:
10.1080/15361055.2023.2176687
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发表时间:
2023
影响因子:
0.9
通讯作者:
Garrison L
Garrison L
中科院分区:
工程技术4区
文献类型:
--
作者:
Garrison L

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未来聚变反应堆的面向等离子体的部件(PFC)将具有复杂的结构,需要多种材料,因为没有一种材料可以同时满足部件的所有要求。PFCs中异种材料接头必须承受中子辐照下的极端热应力梯度。面向中子辐照和材料界面处氚行为的聚变研究(前沿)日本的合作旨在探索和解释中子辐照下PFC内部固体界面的行为。合作的第一步是确定应进一步研究的主要PFC,并为下一步(包括中子辐照)做好准备。全世界正在采取不同的材料开发战略,以生产耐用的全氟化学品。在这里,概述了铜合金,钨铜复合材料,钨钢复合材料,增材制造钨,颗粒增强钨以及钨和SiC纤维复合材料领域中一些最有前途的材料。描述了每种材料的制造和优点,并对剩余问题进行了一些讨论。
The plasma-facing components (PFCs) of future fusion reactors will have intricate structures and require multiple materials because no one material can simultaneously satisfy all the requirements of the component. The dissimilar material joints in PFCs must withstand extreme thermal and stress gradients under neutron irradiation. The Fusion Research Oriented to Neutron Irradiation and Tritium Behavior at Material Interfaces (FRONTIER) U.S.-Japan collaboration seeks to explore and explain the behavior of internal solid interfaces in PFCs under neutron irradiation. The first step of the collaboration was to identify the leading PFCs that should be studied further and prepare them for the next step, which will include neutron irradiation. Different strategies for material development are being pursued worldwide to produce robust PFCs. Here, an overview is presented of some of the most promising materials in the areas of copper alloys, tungsten-copper composites, tungsten-steel composites, additively manufactured tungsten, particle-reinforced tungsten, and tungsten and SiC fiber composites. Each material’s fabrication and benefits are described, and some discussion of remaining questions is given.
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