STP1175

    Study on the Irradiation Embrittlement of a Microalloyed Ferritic Steel

    Published: Jan 1994


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    Abstract

    The embrittlement of microalloyed and grain-refined high tensile strength steel plates, which are to be extensively used as structural components in nuclear reactors in India, was studied after irradiating to neutron fluences between 1.7 x 1017 and 1.0 x 1019 n.cm2 (E > 1 MeV). The irradiations were carried out at less than 150°C. The results of room temperature tension tests and the instrumented impact tests over a range of temperature are presented. Irradiation stability of the steel is monitored by measuring the increase in yield strength and the elevation in the ductile-brittle-transition temperature after neutron irradiation. Attempts have been made to assess the extent of embrittlement as a function of neutron exposure. The results have been compared with both vintage and advanced pressure vessel steels.

    Keywords:

    microalloyed ferritic steel, irradiation embrittlement, ductile-brittle-transition temperature (DBTT), static and dynamic yield strength, ductility, Charpy V-notch, neutron flux, neutron fluence, upper shelf energy


    Author Information:

    Ganguly, C
    Head, scientific officer, and scientific officer, Bhabha Atomic Research Centre, Bombay,

    Viswanathan, UK
    Head, scientific officer, and scientific officer, Bhabha Atomic Research Centre, Bombay,

    Balakrishnan, KS
    Head, scientific officer, and scientific officer, Bhabha Atomic Research Centre, Bombay,


    Paper ID: STP23936S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP23936S


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