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An empirical in-reactor creep equation has been developed for 20% cold worked 316SS. This equation is based upon creep data obtained predominately from pressurized tube specimens irradiated in the Experimental Breeder Reactor EBR-II at specific irradiation temperatures between 400 and 730°C and to a peak fluence of 7×1022n/cm2 (E >0.1 MeV). The correlation includes both thermal and irradiation induced creep terms to model the observed primary, steady-state, and tertiary creep behaviors for this alloy. The thermal creep tertiary term has been modified to reflect the observed delay in the onset of tertiary creep for the in-reactor creep data. The correlation is compared to the in-reactor data base and the 1σ uncertainty has been found to be 30% of the calculated strain where data exist.
stainless steel, creep, irradiation, model, 316SS
Senior scientist, Westinghouse Hanford Company, Richland, Washington
Senior engineer, Pacific Northwest Laboratory, Richland, Washington
Associate professor, Auburn University, Auburn, Alabama