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    Study on Melt Coolability and Water Ingression Through Melt Pool in Scaled Down Core Catcher—The Influence of Vessel Angle 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 007 ):;issue: 001:;page 011301-1
    Author(s): V., Ganesh; Kulkarni, Parimal P.; Nayak, Arun K.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: An ex-vessel core catcher is generally used in advanced reactors to mitigate core melt scenarios by stabilizing and cooling the corium for prolonged period by strategically flooding it. The side indirect cooling along with ...
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    Experimental Investigation of Melt Coolability Behavior in an ExVessel Core Catcher: The Effect of Flooding Time 

    Source: Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 008 ):;issue: 003:;page 31401
    Author(s): V, Ganesh;Kulkarni, Parimal P.;Nayak, Arun K.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Some of the advanced nuclear reactors employ an exvessel core catcher to mitigate core melt scenarios by stabilizing and cooling the corium for a prolonged period by strategically flooding it. The side indirect cooling ...
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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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    Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher 

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 004:;page 41206
    Author(s): Munot, Samyak S.; V, Ganesh; Kulkarni, Parimal P.; Nayak, Arun K.
    Publisher: American Society of Mechanical Engineers (ASME)
    Abstract: To minimize the potential risk of design extension conditions (DEC) with core meltdown, some advanced reactors employ ex-vessel core catchers which stabilize and cool the corium for prolonged period by strategically flooding ...
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