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铅冷快堆用不锈钢液态铅铋环境相容性评价研究进展

英文摘要

he environmental compatibility issue of structural materials in liquid lead bismuth eutectic (LBE) is a bottleneck problem restricting the development and construction of lead-cold fast reactors. 9-12Cr ferritic/martensitic and austenitic stainless steels are the preferred materials for fuel cladding and reactor vessel. However, they face severe liquid metal corrosion (oxidation and dissolution) problems in high-temperature liquid LBE environments. Usually, an appropriate amount of Si or Al is added to the alloy to enhance its resistance to liquid metal corrosion. This paper reviews the research progress on corrosion, dissolution, slow strain rate tensile, creep, fatigue and crack propagation behavior of 9-12Cr ferritic/martensitic steels, austenitic stainless steels, Si-reinforced ferritic/martensitic steels and austenitic stainless steels, and Al forming austenitic stainless steels in the liquid LBE environment. The liquid metal embrittlement sensitivity and damage mechanism of ferritic/martensitic steels (body-centered cubic) and austenitic stainless steels (face-centered cubic) in liquid LBE environment are discussed. The existing problems in the current research are pointed out, and the future research directions are prospected.

谭季波

中国科学院金属研究所-腐蚀基础与前沿研究部

核反应堆工程反应堆、核电厂

铅冷快堆不锈钢液态金属腐蚀液态金属脆化力学性能

Lead-cooled fast reactorStainless steelliquid metal corrosionliquid metal embrittlementmechanical property

谭季波.铅冷快堆用不锈钢液态铅铋环境相容性评价研究进展[EB/OL].(2025-04-19)[2025-08-02].https://chinaxiv.org/abs/202504.00262.点此复制

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