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Evaluation of ferritic alloy Fe-2 1/4Cr-1Mo after neutron irradiation: irradiation creep and swelling

Conference ·
OSTI ID:6693951
Irradiation creep and swelling measurements are reported for Fe-2 1/4Cr-1Mo after irradiation by fast neutrons over the temperature range 370 to 570/sup 0/C. Diameter change measurements on thin walled pressurized tubes in a bainitic condition and density change measurements on rods in a nonstandard condition were made following irradiation in the Experimental Breeder Reactor II. The irradiation creep specimens were irradiated to a fluence of 5.7 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV) or 30 dpa and the swelling specimens were irradiated to a peak fluence of 2.4 x 10/sup 23/ n/cm/sup 2/ or 115 dpa. These results have been used as a basis to establish in-reactor creep and swelling correlations for 2 1/4Cr-1Mo in a bainitic condition. The correlations predict moderate swelling and moderate irradiation enhanced creep at 390/sup 0/C to 480/sup 0/C. The in-reactor creep data at 570/sup 0/C indicates that thermal creep mechanisms become important at this irradiation temperature.
Research Organization:
Hanford Engineering Development Lab., Richland, WA (USA)
DOE Contract Number:
AC06-76FF02170
OSTI ID:
6693951
Report Number(s):
HEDL-SA-3031-FP; CONF-840604-12; ON: DE84014647
Country of Publication:
United States
Language:
English