SYMPOSIA PAPER Published: 01 January 1982
STP34341S

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

Source

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.

Author Information

Puigh, RJ
Westinghouse Hanford Company, Richland, Washington
Gilbert, ER
Pacific Northwest Laboratory, Richland, Washington
Chin, BA
Auburn University, Auburn, Alabama
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Details
Developed by Committee: E10
Pages: 108–121
DOI: 10.1520/STP34341S
ISBN-EB: 978-0-8031-4846-8
ISBN-13: 978-0-8031-0753-3