Change in the properties of FeCrNi and FeCrMn austenitic steels under mixed and fast neutron irradiation

• Published in: Journal of nuclear materials Vol. 233; no. 1-3; pp. 162 - 168
• Main Authors: Shamardin, V.K., Bulanova, T.M., Golovanov, V.N., Neustroyev, V.S., Povstyanko, A.V., Ostrovsky, Z.E.
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.10.1996
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/S0022-3115(96)00276-0

Detailed investigations are performed on mechanical properties, swelling and structure of different types of FeCrNi and FeCrMn austenitic stainless steels irradiated in the SM-2 high-flux research reactor and BOR-60 fast reactor. Steel irradiation temperatures are ranging from 100 up to 800°C and the maximum achieved level of damage doses is 60 dpa for FeCrMn steel (with 4–5% of Ni) and 30 dpa for steels of the C12Cr20MnWT type. Presented are dose dependencies of swelling and mechanical properties of FeCrNi and FeCrMn steels. It is shown that at temperatures below 530°C the investigated FeCrMn steel systems are less susceptible to swelling as compared to FeCrNi ones. FeCrMn steels showed a lower value of irradiation embrittlement after irradiation in the mixed spectrum at temperatures from 100 up to 400°C and much higher embrittlement after irradiation from 350 up to 400°C in the fast spectrum in comparison with FeCrNi steels. Higher hardening rate of FeCrMn steels after their irradiation in BOR-60 is attributed to the presence of dislocation loops and defects of high density in the structure. The structural change features in FeCrMn steels under irradiation are considered taking into account austenite stabilization in the initial state.