Research and development on vanadium alloys for fusion breeder blanket application

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-12-01 DOI:10.1016/j.fusengdes.2024.114739
Louis Butt , Alexandra Dickinson-Lomas , Martin Freer , Joven Lim , Yu-Lung Chiu
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Abstract

The status of research and development on vanadium alloys and on their application as a structural material in the breeder blanket of a fusion power plant are reviewed. Emphasis has been placed on irradiation experiments and the effects of neutron and ion irradiation on the microstructure of the current reference alloy, V4Cr4Ti. The effects of a liquid lithium environment and the exchange of carbon, nitrogen, and oxygen impurities between the alloy and application-relevant environments are also reviewed. The dependence of microstructural features on irradiation experiment parameters are examined, with a summary on magnetohydrodynamic effects and mechanical properties of the alloy. The relationship between the ductility and the alloy chemistry and the irradiation test temperature are analysed. Review of the state of the art indicates that further developments of facilities simulating a realistic fusion radiation and liquid lithium environment are fundamental to advancing fusion reactor breeder design.

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融合增殖用钒合金的研究与开发
综述了钒合金作为结构材料在核聚变反应堆增殖包层中的研究与开发现状。重点介绍了辐照实验以及中子和离子辐照对当前参考合金V4Cr4Ti显微组织的影响。对液态锂环境的影响以及合金之间碳、氮、氧杂质的交换和应用相关环境的影响也进行了综述。研究了辐照实验参数对合金显微组织特征的影响,总结了合金的磁流体力学效应和力学性能。分析了塑性与合金化学成分及辐照试验温度的关系。对目前技术状况的回顾表明,模拟真实聚变辐射和液态锂环境的设施的进一步发展是推进聚变反应堆增殖器设计的基础。
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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