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Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temperatures Pages: 30 Published: Jan 1970
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View License Agreement Source: STP484-EB Abstract Uniaxial fatigue properties from tests at 400, 500, 600, and 700 C on Type 304, 304L (Ti modified), and 316 stainless steel specimens irradiated at 450 C in sodium and 750 C in argon at fluences of 0.03 to 9.3×1021 n/cm2, E>0.1 MeV, are given and compared with control specimens. Material was tested in the annealed, cold-worked, and chilled-swaged-tempered condition, while primary controls received a pretest anneal of 1500 h at 750 C. The data at 400, 500, and 600 C are compared with proposed design curves for 18-8 steels. Some data on microstructural changes due to irradiation are given. A reduction in the fatigue life by a factor of less than 2.5 was found in the annealed material, which was attributed to irradiation damage. A beneficial effect on fatigue life of pretreatment by swaging was found after irradiation at 450 and 750 C for 2550 h. Keywords: neutron irradiation, radiation effects, liquid metal cooled reactors, fast reactors (nuclear), stainless steels, helium, carbides, voids, microstructure, ductility, embrittlement, fatigue (materials), cold working, axial strains, mechanical properties, fatigue tests, high-temperature tests Paper ID: STP26641S Committee/Subcommittee: E10.07 DOI: 10.1520/STP26641S ASTM International is a member of CrossRef. | ||