STP1220

    J-Integral Characterization of the Nozzle Steels from Intermediate Test Vessels IV-5 and IV-9

    Published: Jan 1995


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    Abstract

    Reported here are the results of elastic-plastic fracture toughness tests performed on low alloy steels from the nozzles of the intermediate test vessels IV-5 and IV-9 from the Heavy Steel Section Technology Program at Oak Ridge National Laboratory. These vessels had been given prototypic nozzle corner flaw tests prior to the development of the ASTM E-813 standard test procedure for J-integral testing. The objective of this work is to provide J-integral material test support for future elastic-plastic fracture mechanics analysis of the nozzles. J-integral tests at 88‡C (190‡F) of the IV-5 nozzle material produced stable ductile tearing. The tearing resistance data are expected to support analysis of the observed similar stable tearing response of the nozzle corner flaw. J-integral tests at 24‡C (75‡F) of the IV-9 nozzle produced elastic-plastic fracture instability preceded by stable tearing. A similar response was observed in the IV-9 nozzle corner flaw test. It will be a major and important challenge to develop a fracture mechanics rationale that reconciles these small specimen and nozzle corner flaw test results. These test results are being made available to allow their use by a wide variety of organizations in developing such a rationale, which would be a significant contribution to quantifying the flaw tolerance of reactor pressure vessels.

    Keywords:

    J-resistance curve, J, IC, ductile tearing, intermediate vessels, HSST program


    Author Information:

    Auten, TA
    Senior Engineer, Principal Engineer, Test Engineer, Specialist, Knolls Atomic Power Laboratory, Schenectady, New York

    Macdonald, BD
    Senior Engineer, Principal Engineer, Test Engineer, Specialist, Knolls Atomic Power Laboratory, Schenectady, New York

    Scavone, DW
    Senior Engineer, Principal Engineer, Test Engineer, Specialist, Knolls Atomic Power Laboratory, Schenectady, New York

    Bozik, D
    Senior Engineer, Principal Engineer, Test Engineer, Specialist, Knolls Atomic Power Laboratory, Schenectady, New York


    Paper ID: STP14607S

    Committee/Subcommittee: E08.08

    DOI: 10.1520/STP14607S


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