STP1114

    Observations in Conducting J-R Curve Tests on Nuclear Piping Materials

    Published: Jan 1991


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    Abstract

    This paper describes some of Battelle's experiences in developing J-R data for nuclear piping materials. Compact specimens were machined from both carbon steel and stainless steel pipe and subjected to testing at elevated temperatures, similar to temperatures encountered in nuclear reactor coolant piping. In many cases, the specimens displayed toughness levels above those considered valid by ASTM standard methods of testing. Furthermore, cracks were grown by about 50% of the original ligament, well in excess of the 10% limit imposed by ASTM Test Method for Determining J-R Curves (E 1152-87).

    Topics discussed in the paper include: (1) monitoring crack extension using the direct-current electric potential method, (2) specimen thickness changes ahead of the growing crack, (3) observations of fracture appearance and crack growth direction in ferritic versus austenitic steels, (4) observations of ductile-crack jumps in carbon steels tested at 288°C (550°F), (5) unusual effects of partial unloadings in testing carbon steels at 288°C (550°F), and (6) difficulties with certain ASTM definitions in testing highly ductile materials.

    Keywords:

    elastic-plastic fracture, test methods, J, -resistance curves, nuclear piping steels, electric potential method, ductile crack growth, crack instabilities, unloading effects


    Author Information:

    Marschall, CW
    Senior research scientist and research scientist, Battelle, Columbus, OH

    Landow, MP
    Senior research scientist and research scientist, Battelle, Columbus, OH


    Paper ID: STP16858S

    Committee/Subcommittee: E08.08

    DOI: 10.1520/STP16858S


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