method for the treatment of an austenitic stainless steel in order to decrease the loss of the hochtemperaturduktilitaet on irradiation in the nuclear reactor

摘要

Austenitic stainless steel is worked, and then annealed at 800 DEG - 900 DEG C., the working and annealing being repeated at least once, in order to bring about formation of a coarse precipitate of all the matter which is insoluble at the annealing temperature, whereby the ductility of the steel after irradiation is improved. Particular compositions exemplified are .(a).(b) .C 0.02.C 0.18 .Mn 0.78.Cr 16.8 .Si 0.44.Ni 13.85 .Cr 21.2.Mo 2.64 .Ni 25.3.Mn 0.49 .Nb 0.65.S 0.014 .N 0.011.P 0.013 .Fe balance.Si 0.46 ..N 0.0135 ..Co 0.003 ..B 0.0002 ..Fe balance Samples were annealed within the specified range and also at 1000 DEG C., and 1050 DEG C. for comparative purposes.