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    Computational Fluid Dynamic Simulations of Heat Transfer From a 2 × 2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001:;page 11008
    Author(s): Podila, Krishna; Rao, Yanfei
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Within the Generation-IV International Forum, Canadian Nuclear Laboratories (CNL) led the conceptual fuel bundle design effort for the Canadian supercritical water cooled reactor (SCWR). The proposed fuel rod assembly for ...
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    Assessment of Computational Tools in Support of Heat Transfer Correlation Development for Fuel Assembly of Canadian Supercritical Water Cooled Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001:;page 11006
    Author(s): Leung, Laurence K. H.; Rao, Yanfei; Podila, Krishna
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Experimental data and correlations are not available for the fuelassembly concept of the Canadian supercritical watercooled reactor (SCWR). To facilitate the safety analyses, a strategy for developing a heattransfer ...
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    Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels 

    Source: Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 009 ):;issue: 001:;page 11402
    Author(s): Li, Chenguang;Podila, Krishna;Bromley, Blair P.;Rao, Yanfei
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Pressure loss coefficients are generally required by subchannel and system thermalhydraulics codes. These coefficients are not readily available for small modular reactors (SMRs) featuring nonconventional designs and novel ...
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    Summary on the Results of Two Computational Fluid Dynamic Benchmarks of Tube and Different Channel Geometries 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001:;page 11001
    Author(s): Kiss, Attila; Churkin, Andrey; Pilkhwal, Darwan S.; Vaidya, Abhijeet M.; Ambrosini, Walter; Pucciarelli, Andrea; Podila, Krishna; Rao, Yanfei; Leung, Laurence; Yuzhou, Chen; Anderson, Mark; Zhao, Meng
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Two computational fluid dynamic (CFD) benchmarks have been performed to assess the prediction accuracy and sensitivity of CFD codes for heat transfer in different geometries. The first benchmark focused on heat transfer ...
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