STP426

    An Evaluation of Radiation Damage to Reactor Vessel Steels Using Both Transition Temperature and Fracture Mechanics Approaches

    Published: Jan 1967


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    Abstract

    As part of the Westinghouse APD irradiation effects program on structural materials, fracture toughness specimens including both Charpy V impact tests (transition temperature approach) and wedge opening loading (WOL) specimens (fracture mechanics approach) were irradiated. The reactor vessel materials investigated were two heats of SA302 Grade B including the ASTM reference correlation monitor material. The shift in the nil-ductility transition temperature (NDTT) based on Charpy impact tests and the change in fracture toughness based on WOL tests were determined. The neutron doses were 2.7 × 1010 to 1.25 × 1020 n/cm2 > 1 Mev at 550 F. Because of transition temperature shifts, stresses would be limited in the temperature range of 220 to 405 F during normal startup and shutdown procedures for reactor vessels. However, fracture mechanics tests showed that flaws greater than 9 in. in depth under stresses of 10,000 psi would not limit operating procedures at temperatures above 300 F.

    Keywords:

    radiation effects, metals, steels, nuclear reactors, transition temperature, fracture mechanics, defects


    Author Information:

    Landerman, E.
    Pittsburgh, Pa

    Yanichko, S. E.
    Pittsburgh, Pa

    Hazelton, W. S.
    Pittsburgh, Pa


    Paper ID: STP41326S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP41326S


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