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