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    Effects of a Venturi Type Flow Restrictor on the Thermal Hydraulic Response of the Secondary Side of a Pressurized Water Reactor Steam Generator to a Main Steam Line Break 

    Source: Journal of Pressure Vessel Technology:;2016:;volume( 138 ):;issue: 004:;page 41304
    Author(s): Chull Jo, Jong; Moody, Frederick J.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A numerical analysis has been performed to simulate the transient thermalhydraulic response to a main steam line break (MSLB) for the secondary side of a steam generator (SG) model equipped with a venturitype SG outlet ...
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    Evaluation of a Numerical Analysis Model for the Transient Response of Nuclear Steam Generator Secondary Side to a Sudden Steam Line Break 

    Source: Journal of Pressure Vessel Technology:;2017:;volume( 139 ):;issue: 003:;page 31305
    Author(s): Chull Jo, Jong; Ki Min, Bok; Jun Jeong, Jae
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper presents an evaluation of the applicability of a numerical analysis model to the transient thermal-hydraulic response of steam generator (SG) secondary side to blowdown following a steam line break (SLB) at a ...
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    Transient Hydraulic Response of a Pressurized Water Reactor Steam Generator to a Feedwater Line Break Using the Nonflashing Liquid Flow Model 

    Source: Journal of Pressure Vessel Technology:;2017:;volume( 139 ):;issue: 003:;page 31302
    Author(s): Chull Jo, Jong; Jun Jeong, Jae; Moody, Frederick J.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In this study, a computational fluid dynamics (CFD) analysis of the transient flow field inside the secondary side of a nuclear reactor steam generator (SG) during blowdown following a feedwater line break (FWLB) accident ...
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    Analytical Study of Flow Instability in a Natural Circulation Pressurized Water Reactor Auxiliary Feedwater System1 

    Source: Journal of Pressure Vessel Technology:;2015:;volume( 137 ):;issue: 002:;page 24501
    Author(s): Chull Jo, Jong; Moody, Frederick J.; Sik Do, Kyu
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A pressurized water reactor (PWR) incorporates a passive auxiliary feedwater system (PAFS), a closed natural circulation loop which is aligned to feed condensed water to its corresponding steam generator (SG). During its ...
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