In-reactor creep rupture properties of 20% CW modified 316 stainless steel

The in-reactor creep rupture tests of 20% cold worked modified 316 stainles s steel were conducted in the temperature range from 878 to 1023 K using MO TA of FFTF, and were compared with the out-of-reactor tests. In-reactor cre ep rupture, lives become shorter than those of the out-of-reactor tests. In -reactor creep strain rate was significantly accelerated, and sufficient du ctility appears to be maintained even under the irradiation. Considering 0. 2% proof strength after neutron irradiation, sodium exposure or aging, the degraded rupture lives of in-reactor creep are ascribed to the enhanced dis location recovery due to the neutron irradiation as well as to the solute e lements dissolution into sodium under the sodium exposure environment. (C) 2000 Elsevier Science B.V. All rights reserved.