STP1125

    Mechanical Property Evaluation of Rajasthan Atomic Power Station Coolant Channel Components

    Published: Jan 1992


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    Abstract

    Longitudinal tension specimens fabricated from a reactor-operated pressure tube that had experienced 3.6 effective full power years of operation when tested at 573 K showed increases in the yield and tensile strength of 39 and 30%, respectively. The residual uniform elongation was 1.8%. The irradiation-induced tensile property changes were observed to be lower than those reported in unstressed tension specimens.

    Reactor-operated garter springs which had also experienced 3.6 effective full power years of operation were subjected to load extension tests up to 9 kg of load. These springs exhibited lower residual extension at all loads up to 9 kg as compared to unirradiated springs and retained adequate spring properties. The girdle wires had uniform elongation of 4% typical.

    Half-size Charpy specimens of end shield material were evaluated for increases in nil ductility transition temperature (NDTT) and dynamic fracture toughness (KId), after irradiating the specimens at a temperature lower than 423 K in a CIRUS test reactor to fluence levels of 1.5, 7, and 14 × 1019 n/cm2 (> 1 MeV). A saturation trend in NDTT was observed beyond the fluence level of 7 × 1019 n/cm2. KId values evaluated at 338 K were 44.7, 39.0, and 30.1 MPa√m for the three fluence levels studied.

    Keywords:

    zirconium alloys, ferritic steel, coolant channel components, tension properties, transition temperature, fracture toughness, load-extension test, irradiation


    Author Information:

    Chatterjee, S
    Group leader, scientific officer, and head of postirradiation examination section (on superannuation), Bhabha Atomic Research Centre, Bombay,

    Anantharaman, S
    Group leader, scientific officer, and head of postirradiation examination section (on superannuation), Bhabha Atomic Research Centre, Bombay,

    Sivaramakrishnan, KS
    Group leader, scientific officer, and head of postirradiation examination section (on superannuation), Bhabha Atomic Research Centre, Bombay,


    Paper ID: STP17876S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP17876S


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