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    Yield Criterion for Thin Perforated Plates With Square Penetration Pattern 

    Source: Journal of Pressure Vessel Technology:;2004:;volume( 126 ):;issue: 002:;page 169
    Author(s): A. Bhattacharya; V. Venkat Raj
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Second and fourth order polynomials describing the yield criterion for perforated plates with square penetration pattern were developed following the methodology shown by Hill (1950) and later ...
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    Flow Regime Identification in Horizontal Channels With Different Types of Rod Clusters 

    Source: Journal of Fluids Engineering:;1998:;volume( 120 ):;issue: 001:;page 207
    Author(s): H. G. Lele; V. Venkat Raj; S. K. Gupta
    Publisher: The American Society of Mechanical Engineers (ASME)
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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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    Analysis of the Thermal Hydraulic Consequences Following Common Mode Pump Seizure in a Nuclear Power Plant 

    Source: Journal of Pressure Vessel Technology:;2002:;volume( 124 ):;issue: 004:;page 415
    Author(s): B. Chatterjee; S. K. Gupta; H. S. Kushwaha; V. Venkat Raj
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In nuclear power plants, the primary heat transport system (PHTS) is designed according to ASME Section 3 Division 1. The PHTS together with Primary Coolant Pumps (PCPs) is designed so that ...
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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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