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    Swelling and Tensile Property Changes in Neutron-Irradiated Type 316 Stainless Steel

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    Specimens of Type 316 stainless steel, given different thermomechanical treatments resulting in either a cold-worked or solution-annealed and aged structure, were irradiated in the Experimental Breeder Reactor-II (EBR-II) at 500 to 600 °C (932 to 1112°F) to a fluence of 7.4 × 1026 neutrons (n)/m2 (E > 0.1 MeV). Three specimen configurations were used: small sheet tension specimens, small right-circular cylinders for immersion density, and thin foils for transmission electron microscopy (TEM). TEM revealed voids in all specimens. Immersion density indicated swelling in cold-rolled specimens only after irradiation at temperatures near 600°C (1112°F). Considerable recovery and precipitation were observed in the cold-rolled specimens. Results of tension tests revealed an increase in strength and decrease in ductility for specimens originally in a solution-annealed and aged condition. Cold-rolled specimens exhibited a decrease in strength and a slight increase in total elongation. True stress-true plastic strain was best described by the Ludwigson equation, σ = K3εn3 ± exp (K4 + n4ε), in all cases. Irradiation causes a decrease in the work-hardening exponent, n3, and strength factor, K3. After irradiation, the values of n3 and K3 tended toward common values for both preirradiation treatments.


    radiation, stainless steels, mechanical properties, swelling, voids, stress-strain diagrams, irradiation

    Author Information:

    Garr, KR
    Rockwell International Corporation, Canoga Park, Calif.

    Pard, AG
    Rockwell International Corporation, Canoga Park, Calif.

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP38041S