STP457: Postirradiation Tensile Behavior of 300 Series Stainless Steels

    Holmes, J. J.
    Managerresearch scientistresearch engineer, Battelle Memorial Institute, Pacific Northwest Laboratory, Richland, Wash.

    Robbins, R. E.
    Managerresearch scientistresearch engineer, Battelle Memorial Institute, Pacific Northwest Laboratory, Richland, Wash.

    Lovell, A. J.
    Managerresearch scientistresearch engineer, Battelle Memorial Institute, Pacific Northwest Laboratory, Richland, Wash.

    Pages: 19    Published: Jan 1969


    Abstract

    The effects of neutron irradiation on the tensile properties of several austenitic stainless steels are considered over a wide fluence and temperature range. At low fluence levels (about 1020 neutrons (n)/cm2, E > 1 MeV), displacement damage results in radiation hardening if the irradiation and test temperatures are below one half the absolute melting temperature (0.5 Tm) of the steel. Above 0.5 Tm, hardening no longer exists, but a ductility loss due to helium embrittlement is observed. The temperature above which radiation hardening is no longer significant increases with increasing fluence. Elevated temperature hardening after fast reactor irradiations is the result of void formation. The hardening observed after thermal reactor irradiations appears to be due to the formation of gas filled bubbles, but the nature of the gas is not clear.

    Keywords:

    neutron irradiation, hardening, yield strength, work hardening, particle fluence, elevated temperature, voids, gas bubbles, displacement damage, embrittlement, temperature domains, tensile behavior, stainless steels, electron microscopy, annealing, dislocations, plastic instability, tension test, evaluation, tests


    Paper ID: STP41858S

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP41858S


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