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

摘要

The in-reactor creep rupture tests of 20% cold worked modified 316 stainless steel were conducted in the temperature range from 878 to 1023 K using MOTA of FFTF, and were compared with the out-of-reactor tests. In-reactor creep rupture, lives become shorter than those of the out-of-reactor tests. In-reactor creep strain rate was significantly accelerated, and sufficient ductility 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 dislocation recovery due to the neutron irradiation as well as to the solute elements dissolution into sodium under the sodium exposure environment. (C) 2000 Elsevier Science B.V. All rights reserved. [References: 11]