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    The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 003
    Author(s): Tucker, M. D.; Novog, D. R.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Within emerging best-estimate-plus-uncertainty (BEPU) approaches, code output uncertainties can be inferred from the propagation of fundamental or microscopic uncertainties. This paper examines the propagation of fundamental ...
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    Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002:;page 21003
    Author(s): Salaun, F.; Novog, D. R.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The Canadian supercritical water-cooled reactor (SCWR) design is part of Canada's Generation IV reactor development program. The reactor uses batch fueling, light water above the thermodynamic critical point as a coolant ...
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    A Blind, Numerical Benchmark Study on Supercritical Water Heat Transfer Experiments in a 7 Rod Bundle 

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 002:;page 21012
    Author(s): Rohde, M.; Peeters, J. W. R.; Pucciarelli, A.; Kiss, A.; Rao, Y. F.; Onder, E. N.; Muehlbauer, P.; Batta, A.; Hartig, M.; Chatoorgoon, V.; Thiele, R.; Chang, D.; Tavoularis, S.; Novog, D.; McClure, D.; Gradecka, M.; Takase, K.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Heat transfer in supercritical water reactors (SCWRs) shows a complex behavior, especially when the temperatures of the water are near the pseudocritical value. For example, a significant deterioration of heat transfer may ...
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