Development and testing of vanadium alloys for fusion applications
Development and testing of vanadium alloys for fusion applications
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DOI：
10.1016/s0022-3115(96)00676-9
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发表时间：
1996-12-01
影响因子：
3.1
通讯作者：
Smith, DL
中科院分区：
文献类型：
--
作者：
Chung, HM;Loomis, BA;Smith, DL
钒基合金由于具有以下几个重要优点而成为应用于聚变堆第一壁和包层结构的有希望的候选材料，即，固有低辐射诱导活性、良好的机械性能、与锂的良好相容性、高导热性和良好的抗辐射诱导溶胀和损伤性。为了筛选候选合金并开发优化的钒基合金，在快裂变反应堆锂环境中对各种V-Ti、V-Cr-Ti和V-Ti-Si合金进行了辐照前后的物理和机械性能的广泛研究。从这些研究中，含有500-1000 wppm Si和< 1000 wppm O + N + C的V-4Cr-4 Ti合金已被确定为最有前途的合金，并且正在对该合金的性能进行针对聚变相关条件的更全面的测试。本文介绍了研制最佳合金和测试辐照性能的综合工作的主要结果。参比合金V-4Cr-4 Ti表现出最有吸引力的机械和物理性能的组合，这些性能是第一壁和覆盖层结构的先决条件，即，良好的热蠕变行为、良好的拉伸强度和延展性、高冲击能量、优异的抗溶胀性以及在辐照前后非常低的延性-脆性转变温度。该合金在420-600摄氏度下对Li中的辐照致脆具有高度的抵抗性，并且动态充电的氦对溶胀和机械性能的影响是微不足道的。然而，若干重要问题仍未得到解决，例如，焊接、低温辐照性能、高剂量和高氦浓度下的氦效应、辐照蠕变以及在空气或氦环境中的辐照性能。其中一些问题的初步调查结果也给出。
Vanadium-base alloys are promising candidate materials for application in fusion reactor first-wall and blanket structure because of several important advantages, i.e., inherently low irradiation-induced activity, good mechanical properties, good compatibility with lithium, high thermal conductivity, and good resistance to irradiation-induced swelling and damage. To screen candidate alloys and develop an optimized vanadium-base alloy, extensive investigations of physical and mechanical properties of various V-Ti, V-Cr-Ti, and V-Ti-Si alloys have been conducted before and after irradiation in lithium environment in fast fission reactors. From these investigations, a V-4Cr-4Ti alloy containing 500-1000 wppm Si and < 1000 wppm O + N + C has been identified as the most promising alloy, end more comprehensive testing on the performance of this alloy is being conducted for fusion-relevant conditions. Major results of the comprehensive work to develop the optimal alloy and test the irradiation performance are presented in this paper. The reference alloy V-4Cr-4Ti exhibited the most attractive combination of the mechanical and physical properties that are prerequisite for first-wall and blanket structures, i.e., good thermal creep behavior, good tensile strength and ductility, high impact energy, excellent resistance to swelling, and very low ductile-brittle transition temperature before and after irradiation. The alloy was highly resistant to irradiation-induced embrittlement in Li at 420-600 degrees C, and the effects of dynamically charged helium on swelling and mechanical properties were insignificant. However, several important issues remain unresolved, e.g., welding, low-temperature irradiation properties, helium effect at high dose and high helium concentration, irradiation creep, and irradiation performance in air or helium environment. Initial results of investigation of some of these issues are also given.