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    Analysis of Possibility of Pressure Tube Cold Pressurization During ECCS Injection for a Small Break LOCA 

    Source: Journal of Pressure Vessel Technology:;2002:;volume( 124 ):;issue: 004:;page 483
    Author(s): D. Mukhopadhyay; S. K. Gupta; V. Venkat Raj
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: ECCS is designed to keep the reactor fuel temperatures within safe limits. The paper describes an additional criterion for Indian pressurized heavy water reactors (IPHWRs) evolving from the need ...
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    Thermal Analysis of Severe Channel Damage Caused by a Stagnation Channel Break in a PHWR 

    Source: Journal of Pressure Vessel Technology:;2002:;volume( 124 ):;issue: 002:;page 161
    Author(s): D. Mukhopadhyay; P. Majumdar; G. Behera; S. K. Gupta; V. Venkat Raj
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The reactor channel of the horizontal core of pressurized heavy water reactors experiences very low sustained flow during loss of coolant accident (LOCA) at the reactor inlet feeders caused by ...
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    Assessment of the Code “PTCREEP ” for IPHWR Pressure Tube Ballooning Study 

    Source: Journal of Pressure Vessel Technology:;2011:;volume( 133 ):;issue: 001:;page 14503
    Author(s): P. Majumdar; G. Nandan; D. Mukhopadhyay; H. G. Lele; B. Chatterjee
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In Indian pressurized heavy water reactor (PHWR), loss of coolant accident with simultaneous failure of emergency core cooling system can lead to significant temperature rise in the pressure ...
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