Senior scientist, Westinghouse Hanford Company, Richland, Washington
Senior engineer, Pacific Northwest Laboratory, Richland, Washington
Associate professor, Auburn University, Auburn, Alabama
Pages: 14 Published: Jan 1982
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
Paper ID: STP34341S