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An In-Reactor Creep Correlation for 20% Cold Worked AISI 316 Stainless Steel

出版	ASTM International, 1982
URL	http://books.google.com.hk/books?id=VtN6zgEACAAJ&hl=&source=gbs_api

註釋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 7x1022n/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 1? uncertainty has been found to be 30% of the calculated strain where data exist.