STP426: Review of Swedish Work on Irradiation Effects in Canning and Core Support Materials

    Grounes, M.
    Head, Structural Materials Laboratory, Studsvik, Nyköping

    Pages: ???    Published: Jan 1967


    A survey is given of the irradiation-effects studies made and in progress on several different materials under varying conditions: Tension specimens of Zircaloy-2 with varying hydrogen contents were irradiated to neutron doses above 7 x 102t n/cm2 (>1 Mev) at 40 C (105 F) and to 5 x 1019 n/cm- (>1 Mev) at 220 to 270 C (430 to 520 F). Stress-relaxation tests of Zircaloy-2 and Zr-2.5 per cent columbium are in progress at 270 C (520 F) to 1019 n/cm2 (>1 Mev). Tension specimens of annealed and cold-worked steels similar to AISI Types 304 and 316 were irradiated to 4 x 1021 n/cm2 (>1 Mev) at 40 C (105 F) and about 5 x 1020 n/cm2 (>1 Mev) at 270 C (520 F). Tension specimens of nickel-base alloys (Hastelloy X, Incoloy 800, 20Cr/25Ni/Cb) were irradiated at 550 to 700 C (1020 to 1290 F) to 1020 to 1021 n/cm2 (>1 Mev). Impact tests were made on AISI 406 steel (13 per cent Cr, 4 per cent Al) after 1020 n/cm2 (>1 Mev) at 550 C (1020 F). Work in progress on postirradiation creep, in-pile creep, in-pile fatigue, and in-pile corrosion is briefly described. The significance of irradiation-effects data is discussed for in-pile loop tubes in a materials testing reactor.


    irradiation, radiation effects, nuclear reactors, Zircaloy, neutron irradiation, tension tests, stress-relaxation, steels, stainless steels, nickel-base alloys, creep, fatigue (materials), corrosion, impact tests

    Paper ID: STP41324S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP41324S

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