STP457: Notch Ductility, Tensile and Neutron Spectrum Analyses of PM-2A Reactor Pressure Vessel

    Serpan, C. Z.
    Research chemist and mechanical engineerpersonal member ASTM, Naval Research Laboratory (Code 6390), Washington, D. C.

    Watson, H. E.
    Research chemist and mechanical engineerpersonal member ASTM, Naval Research Laboratory (Code 6390), Washington, D. C.

    Pages: 21    Published: Jan 1969


    Abstract

    Following the pressurization-to-failure testing of the PM-2A reactor pressure vessel, several sections of steel were removed from the vessel wall in a region adjacent to the artificial defect. Charpy V-notch and tension test specimens machined from one of these sections were evaluated. The irradiated-condition 30 ft-lb transition temperatures for the 1/4 thickness (nearest to the core) and 3/4 thickness locations in the vessel wall were +115 and +55 F, respectively, for measured fission spectrum fluences of 7.3 and 4.0 × 1018 n/cm2 ⟩1 MeV. The 1/4 thickness properties and fluence most nearly represented those at the tip of the artificial defect. The 0.2 percent yield strength for the 1/4 thickness location was 97,620 psi at -20 F (failure temperature) and 92,200 psi at +72 F (temperature at time of acid sharpening treatment of artificial defect). Significant uniform elongation, reduction of area, and elongation in 1 in. were retained by the steel. An assessment of the stress, temperature, and flaw size conditions for the PM-2A failure, as indexed by the irradiated-condition mechanical properties, indicates that the failure is in agreement with the generalized fracture analysis diagram.

    Keywords:

    reactors, power, notch ductility, tensile properties, neutron fluence, neutron spectrum, irradiation, embrittlement, tests, evaluation


    Paper ID: STP41846S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP41846S


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