STP611: Effect of Fast Reactor Irradiation on the Tensile Properties of 20 Percent Cold-Worked Type 316 Stainless Steel

    Fish, RL
    Advanced engineer and manager, Duct, Cladding and Control Elements, Hanford Engineering Development Laboratory, Westinghouse Hanford Company, Richland, Wash.

    Watrous, JD
    Advanced engineer and manager, Duct, Cladding and Control Elements, Hanford Engineering Development Laboratory, Westinghouse Hanford Company, Richland, Wash.

    Pages: 10    Published: Jan 1976


    Abstract

    Fast neutron irradiation effects on the tensile properties of 20 percent cold-worked Type 316 stainless steel are presented to fluences of 3.6 × 1022 neutrons (n)/cm2, E > 0.1 MeV (3.6 × 1026 n/m2, E > 16 fJ), at irradiation temperatures of 700 to 1125°F (644 to 880 K). The tests were performed over the range of room temperature to 1600°F (1144 K) employing strain rates of 1.82 × 10-3 to 1.82/min (3 × 10-5 to 3 × 10-2/s).

    Irradiation defect hardening at irradiation temperatures below 900°F (755 K) resulted in strength increases. Thermal annealing of the original cold-work operated to reduce the strength of material irradiated near 1000 and 1100°F (811 and 866 K), in the fluence range investigated. Elongation values initially increased at most irradiation temperatures and then decreased with fluence beyond 1022 n/cm2 (1026 n/m2). Both strength and ductility decreased with increasing temperature at fluences beyond 1022 n/cm2 (1026 n/m2). The 450°F (505 K) unirradiated elongation level was maintained or improved for all irradiation conditions investigated, which suggests that low ductility will not present a problem during refueling operations.

    Keywords:

    radiation, irradiation, stainless steels, tensile strength, fast reactor, strain rate, ductility


    Paper ID: STP38042S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP38042S


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