Influence of operation conditions on structure and properties of 12% Cr steels as candidate structural materials for fusion reactor

• Published in: Journal of nuclear materials Vol. 258; pp. 1312 - 1318
• Main Authors: Ioltukhovsky, A.G, Leontyeva-Smirnova, M.V, Kazennov, Y.I, Medvedeva, E.A, Tselishchev, A.V, Shamardin, V.K, Povstyanko, A.V, Ostrovsky, S.E, Dvoryashin, A.M, Porollo, S.I, Vorobyev, A.N, Khabarov, V.S
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.10.1998
• Subjects: S06; M03; M05; S10; F04
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/S0022-3115(98)00396-1

The Russian experience in the development and operation of the nuclear core components in fast reactors with a sodium coolant demonstrates that 12% Cr steels may be successfully used at temperatures of 270–650°C and at high neutron damage dose (up to 100 dpa and above). The priority of the temperature but not of dose of the irradiation is noted for the steels at 270–350°C. In addition, the following may take place: a sharp decrease in the ductility of material, a change in the mechanism of fracture with which the ductile–brittle-transition-temperature (DBTT) shift is associated. With an increase in irradiation temperature to 350–500°C and the irradiation dose (up to 100 dpa) chromium steels are observed to strengthen; their ductility increased monotonously, and embrittlement does not show up. With the irradiation temperature increased above 500°C (up to 650–690°C), the material becomes plastic and some of its strength properties are decreased. The high level of the irradiation resistance of 12% Cr steels is a result of their structure and phase transformations. The properties of the welded joints of 12% Cr steels under the conditions of the neutron irradiation are slightly inferior to the properties of the base metal.