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    Special Section: CNS's 8th International Conference on Simulation Methods in Nuclear Science and Engineering 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 001:;page 010304-1
    Author(s): Buijs, Adriaan; Nichita, Eleodor
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Adriaan Buijs, Conference ChairThe eighth edition of the International Conference on Simulation Methods in Nuclear Science and Engineering was organized by the Canadian Nuclear Society and held in Ottawa, ON, Canada in ...
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    Temperature Distribution Inside Fresh Fuel Pins of Pressure Tube Supercritical Water Cooled Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001:;page 11008
    Author(s): Kovaltchouk, Vitali; Nichita, Eleodor; Saltanov, Eugene
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The radial temperature profile for ThO2PuO2 freshfuel pins of the pressuretube supercriticalwatercooled reactor (PTSCWR) is simulated for two different radial distributions of the ThO2 and PuO2, one whereby the ThO2 and ...
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    Axial Power and Coolant Temperature Profiles for a Non Re Entrant Pressure Tube Supercritical Water Cooled Reactor Fuel Channel 

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001:;page 11009
    Author(s): Kovaltchouk, Vitali; Nichita, Eleodor; Saltanov, Eugene
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The axial power and coolanttemperature distributions in a fuel channel of the Generation IV pressuretube supercritical watercooled reactor (PTSCWR) are found using coupled neutronicsthermalhydraulics calculations. The ...
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    A Study of Superhomogenization Applied to PHWR Lattices 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 001:;page 011109-1
    Author(s): Ferguson, Thomas A.; Nichita, Eleodor M.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: To reduce computational expenses, full-core production-type neutronics calculations are customarily performed using a simplified core-model whereby large regions of the core, called nodes, are assumed to be homogeneous. ...
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    Comparison of the Reactivity Effects Calculated by DRAGON and Serpent for a PHWR 37-Element Fuel Bundle 

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 001:;page 11011
    Author(s): Haroon, Jawad; Kicka, Leslie; Mohapatra, Subhramanyu; Nichita, Eleodor; Schwanke, Peter
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Deterministic and Monte Carlo methods are regularly employed to conduct lattice calculations. Monte Carlo methods can effectively model a large range of complex geometries and, compared to deterministic methods, they have ...
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