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    HAO Yuchen, ZHAO Meiling, LUO Laima. Research Progress on Irradiation Damage of Austenitic Stainless Steel for Nuclear Reactor[J]. Materials and Mechanical Engineering, 2018, 42(7): 1-5. DOI: 10.11973/jxgccl201807001
    Citation: HAO Yuchen, ZHAO Meiling, LUO Laima. Research Progress on Irradiation Damage of Austenitic Stainless Steel for Nuclear Reactor[J]. Materials and Mechanical Engineering, 2018, 42(7): 1-5. DOI: 10.11973/jxgccl201807001

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

    • 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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