Assessment and selection of materials for ITER in-vessel components
Assessment and selection of materials for ITER in-vessel components
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DOI：
10.1016/s0022-3115(00)00305-6
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发表时间：
2000-12-01
影响因子：
3.1
通讯作者：
Tivey, R
中科院分区：
文献类型：
--
作者：
Kalinin, G;Barabash, V;Tivey, R
在国际热核实验堆（ITER）工程设计活动（EDA）中，反应堆容器内构件材料的选择取得了重大进展。这一进展是材料科学家和行业在全球范围内合作的结果，他们专注于优化材料和组件制造以及研究最关键的材料特性。建议将奥氏体不锈钢316 L（N）-IG和316 L、镍基合金Inconel 718和Inconel 625、Ti-6Al-4V合金和两种铜合金CuCrZr-IG和CuAl 25-IG作为参考结构材料，并选择铁素体钢430和添加硼的奥氏体钢304 B7用于ITER容器内部件的某些特定部件。铍、钨和碳纤维复合材料被认为是面向等离子体的装甲材料。本文对所有这些材料的性能数据库进行了严格评估和简要回顾，并对材料选择的理由进行了说明（例如，中子辐照对材料机械性能的影响、制造周期的影响等）。(C)2000 Elsevier Science B. V.保留所有权利。
During the international thermonuclear experimental reactor (ITER) engineering design activities (EDA) significant progress has been made in the selection of materials for the in-vessel components of the reactor. This progress is a result of the worldwide collaboration of material scientists and industries which focused their effort on the optimisation of material and component manufacturing and on the investigation of the most critical material properties. Austenitic stainless steels 316L(N)-IG and 316L, nickel-based alloys Inconel 718 and Inconel 625, Ti-6Al-4V alloy and two copper alloys, CuCrZr-IG and CuAl25-IG, have been proposed as reference structural materials, and ferritic steel 430, and austenitic steel 304B7 with the addition of boron have been selected for some specific parts of the ITER in-vessel components. Beryllium, tungsten and carbon fibre composites are considered as plasma facing armour materials. The data base on the properties of all these materials is critically assessed and briefly reviewed in this paper together with the justification of the material selection (e.g., effect of neutron irradiation on the mechanical properties of materials, effect of manufacturing cycle, etc.). (C) 2000 Elsevier Science B.V. All rights reserved.