材料科学
抗辐射性
聚变能
结构材料
包层(金属加工)
陶瓷
核工程
碳化硅
辐射损伤
氧化物
融合
工程物理
辐射
复合材料
冶金
核物理学
语言学
哲学
物理
等离子体
工程类
作者
S.J. Zinkle,L.L. Snead
标识
DOI:10.1146/annurev-matsci-070813-113627
摘要
Proposed fusion and advanced (Generation IV) fission energy systems require high-performance materials capable of satisfactory operation up to neutron damage levels approaching 200 atomic displacements per atom with large amounts of transmutant hydrogen and helium isotopes. After a brief overview of fusion reactor concepts and radiation effects phenomena in structural and functional (nonstructural) materials, three fundamental options for designing radiation resistance are outlined: Utilize matrix phases with inherent radiation tolerance, select materials in which vacancies are immobile at the design operating temperatures, or engineer materials with high sink densities for point defect recombination. Environmental and safety considerations impose several additional restrictions on potential materials systems, but reduced-activation ferritic/martensitic steels (including thermomechanically treated and oxide dispersion–strengthened options) and silicon carbide ceramic composites emerge as robust structural materials options. Materials modeling (including computational thermodynamics) and advanced manufacturing methods are poised to exert a major impact in the next ten years.
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