STP803V2: J-R Curve Characterization of Irradiated Low-Shelf Nuclear Vessel Steels

    Loss, FJ
    Technical director, senior engineer, and mechanical engineer, Materials Engineering Associates, Inc., Lanham, Md.

    Menke, BH
    Technical director, senior engineer, and mechanical engineer, Materials Engineering Associates, Inc., Lanham, Md.

    Hiser, AL
    Technical director, senior engineer, and mechanical engineer, Materials Engineering Associates, Inc., Lanham, Md.

    Watson, HE
    Supervisory mechanical engineer, Naval Research Laboratory, Washington, D.C.

    Pages: 19    Published: Jan 1983


    Abstract

    The J-R curve behavior of irradiated nuclear pressure vessel steels is characterized in the ductile upper-shelf regime in order to provide a materials basis with which to assess the margin of safety against fracture for water reactor vessels exhibiting a low upper-shelf CV energy. With the single specimen compliance technique, the R-curve is shown to follow a power-law behavior for small crack extension, and this phenomenon has led to a proposed new indexing procedure forJIc. In addition, a specimen size dependence of the R-curve has been suggested by the results of similar compact tension specimens up to 100 mm thick and which have sufficiently deep side grooves to produce a straight crack-front extension.

    R-curve data are presented in terms of a J versus T instability diagram which couples material and structural parameters, thereby permitting an analysis to be made of the margin against failure in terms of J. Also, a correlation has been suggested between the R-curve parameters and CV shelf energy; this could enhance the structural significance of CV reactor surveillance data.

    Keywords:

    J-integral, R-curve, elastic-plastic fracture, reactor pressure vessels, fracture toughness, radiation, tearing modulus, size effect


    Paper ID: STP36798S

    Committee/Subcommittee: E08.08

    DOI: 10.1520/STP36798S


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