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    核反应堆用奥氏体不锈钢辐照损伤的研究进展

    Research Progress on Irradiation Damage of Austenitic Stainless Steel for Nuclear Reactor

    • 摘要: 总结了核反应堆中应用非常广泛的奥氏体不锈钢的不同辐照损伤行为,包括辐照诱导显微结构变化、辐照诱导偏析、辐照诱导析出、辐照诱导应力腐蚀断裂等;从试验方法和奥氏体不锈钢种类等方面提出了核反应堆用奥氏体不锈钢辐照损伤的研究方向。

       

      Abstract: Different irradiation damage behavior, including irradiation induced change of microstructure, irradiation induced segregation, irradiation induced precipitation and irradiation induced stress corrosion cracking of austenitic stainless steels commonly used in nuclear reactors is summarized. The research direction of irradiation damage of austenitic stainless steels for nuclear reactors is proposed from the aspects of test methods and category of austenitic stainless steel.

       

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