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    Special Section: Selected Papers From the Ninth International Symposium on Supercritical Water-Cooled Reactors 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 003:;page 030301-1
    Author(s): Leung, Laurence; Guzonas, David; Schulenberg, Thomas
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The Ninth International Symposium on Supercritical Water-Cooled Reactors (IS-SCWRs) was successfully held on Mar. 11–13, 2019 at the Vancouver Marriott Hotel, Vancouver, BC, Canada. It was hosted by the Canadian Nuclear ...
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    Professor Pavel Leonidovich Kirillov on His 90th Birthday 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001:;page 10204
    Author(s): Pioro, Igor; Churkin, Andrey; Leung, Laurence
    Publisher: The American Society of Mechanical Engineers (ASME)
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    Thermal-Hydraulics Program in Support of Canadian SCWR Concept Development 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001:;page 11002
    Author(s): Leung, Laurence K. H.; Nava-Dominguez, Armando
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The thermal-hydraulics program in support of the development of the Canadian supercritical water-cooled reactor (SCWR) concept has undergone several phases. It focused on key parameters such as heat transfer, critical flow, ...
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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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    Assessment of Convective Heat Transfer Correlations Against an Expanded Database for Different Fluids at Supercritical Pressures 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001:;page 11004
    Author(s): Zahlan, Hussam A. M.; Leung, Laurence K. H.; Huang, Yan-Ping; Liu, Guang-Xu
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Canadian Nuclear Laboratories (CNL) has recently expanded the supercritical heat transfer (SCHT) databank with additional data provided by the Nuclear Power Institute of China (NPIC). These additional data cover flow ...
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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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