STP484

    The Effect of Fast Neutron Irradiation on the Mechanical Properties of Some Quenched and Tempered Steels

    Published: Jan 1970


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    Abstract

    Specimens from seven heats of AISI 403, five heats of A542, and one heat of AISI 431 were irradiated at 300 C in pressurized water to find the effect of chemical composition on their irradiated properties. The change in ductile-brittle transition temperature ΔT after the maximum integrated fast neutron flux of 1×1020 n/cm2, E > 1 MeV, was similar for these steels. Some of the heats were also tested after an integrated flux of 6×1019 n/cm2, E > 1 MeV, and the results showed that the latter flux caused saturation of damage in AISI 403. The total impurity concentration of AISI 403 appeared to control the size of ΔT at saturation, but there was no such correlation in the other steels. Obversely, the nitrogen concentration of A542 did affect its change of transition temperature for a given flux; a titanium concentration of 0.1 weight percent increased the unirradiated transition temperature but not ΔT. AISI 431 is unsuitable for use at 300 C as it is thermally embrittled. Although the ΔT values for AISI 403 and A542 were the same, the latter had a lower initial transition temperature.

    Keywords:

    irradiation, neutron irradiation, radiation tolerance, radiation damage, neutron flux, mechanical properties, chemical composition, grain size, quenching (cooling), tempering, martensitic stainless steels, alloy steels, pressure vessels


    Author Information:

    Hosbons, RR
    Research engineers, Chalk River Nuclear Laboratories, Atomic Energy of Canada Ltd., Chalk River, Ontario

    Wotton, BL
    Research engineers, Chalk River Nuclear Laboratories, Atomic Energy of Canada Ltd., Chalk River, Ontario


    Paper ID: STP26617S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP26617S


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