Uniaxial and Biaxial Creep Rupture of Type 316 Stainless Steel After Fast Reactor Irradiation

    Published: Jan 1970

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    The degradation in creep rupture properties of Type 316 stainless steel after fast reactor irradiation has been determined for both uniaxial and biaxial loading conditions. Uniaxial specimens (rod type) and biaxial specimens (tube type) were irradiated in the 7C4 position of the EBR-II to a total fluence of 1.2×1022 n/cm2 (1×1022 n/cm2, E>0.1 MeV) at∼ 480 C. Postirradiation tests were performed over a temperature range of 538 to 760 C.

    The results from both uniaxial and biaxial tests at 538 C show significant losses in rupture life relative to unirradiated specimens when compared on the basis of initial true stress. Rupture life was reduced by factors down to 1/20 for uniaxial and 1/40 for biaxial tests. The substantial loss in rupture life at 538 C was primarily a result of high creep rates, and the contribution from ductility loss was relatively small. Uniaxial test results at 593 C show reductions in rupture life to a factor of 1/5 at high stresses and only small reductions at low stresses. The rupture life for both uniaxial and biaxial tests at 649 C show only a decrease of 1/2 after irradiation. The decrease becomes more substantial again at 760 C, with a reduction in life to 1/10 to 1/7. The rupture life reductions at 593, 649, and 760 C were the results of reduced ductility, with no significant contributions from creep rate differences. The underlying cause of the low ductility at these higher temperatures is associated with helium embrittlement and defect structure.


    irradiation, neutron irradiation, degradation, fast neutrons, axial stress, bursting, creep properties, creep rate, creep rupture strength, creep tests, ductility, embrittlement, structural steels, austenitic stainless steels, fast reactors (nuclear), liquid metal cooled reactors

    Author Information:

    Lovell, AJ
    Senior research engineerengineer, Pacific Northwest Laboratory, Battelle Memorial Institute, Richland, Wash.

    Barker, RW
    Senior research engineerengineer, Pacific Northwest Laboratory, Battelle Memorial Institute, Richland, Wash.

    Paper ID: STP26645S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP26645S

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