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    Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident 

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 004:;page 41601
    Author(s): Pandey, Pradeep; Kulkarni, Parimal P.; Nayak, Arun; Prasad, Sumit V.
    Publisher: American Society of Mechanical Engineers (ASME)
    Abstract: In some of the older design of pressurized heavy water reactors (PHWRs), such as in Rajasthan Atomic Power Station (RAPS) and Madras Atomic Power Station (MAPS), in case of a severe accident, the debris/corium may cause ...
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    Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 007 ):;issue: 001:;page 011702-1
    Author(s): Pandey, Pradeep; Kulkarni, Parimal P.; Nayak, Arun; Prasad, Sumit V.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Retention of molten corium inside calandria vessel is crucial for arresting accident progression in pressurized heavy water reactors (PHWRs) during severe accidents. Our earlier tests have demonstrated corium retention and ...
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