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Gilbert, Edgar R.; Garner, Francis A.
Pacific Northwest National Lab., Richland, WA (United States). Funding organisation: US Department of Energy (United States)2006
Pacific Northwest National Lab., Richland, WA (United States). Funding organisation: US Department of Energy (United States)2006
AbstractAbstract
[en] Pressurized tubes of AISI 316 stainless steel irradiated in the P-1 experiment in the EBR-II fast reactor have been measured to determine the dependence of irradiation-induced strains resulting from plastic deformation, irradiation creep, void swelling and precipitation. It is shown that the Soderberg relation predicting no axial creep strains in biaxially-loaded tubes is correct for both plastic and creep strains. Swelling strains are shown to be isotropically distributed both for stress-free and stress-affected swelling, while precipitation strains are somewhat anisotropic in their distribution. When corrected for stress-enhancement of swelling, the derived irradiation creep strains appear to be identical for both annealed and 20% cold-worked specimens, and also for tubes strained by rise to power increases in pressure. For relatively small creep strains it is often difficult to separate the creep and non-creep components of deformation
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1 Sep 2006; vp; Oak Ridge National Laboratory; Oak Ridge, TN (United States); AT6020100; AC05-76RL01830; Available from Oak Ridge National Laboratory, Oak Ridge, TN (US); Fusion Materials Semiannual Progress Report for the period ending June 30, 2006, DOE/ER-313/40, 95-103
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Miscellaneous
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ALLOYS, CARBON ADDITIONS, DEFORMATION, EPITHERMAL REACTORS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, MECHANICAL PROPERTIES, ORGANIC COMPOUNDS, ORGANIC POLYMERS, PETROCHEMICALS, PETROLEUM PRODUCTS, POLYMERS, REACTORS, SEPARATION PROCESSES, STEELS, SYNTHETIC MATERIALS, TRANSITION ELEMENT ALLOYS
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