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    Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods 

    Source: Journal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 003:;page 31302-1
    Author(s): Wojtaszek, Daniel T.; Bromley, Blair P.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Small modular reactors (SMRs) based on high-temperature gas-cooled reactor (HTGR) technology are being developed for providing high-temperature process heat and high-efficiency (>40%) electrical power generation. However, ...
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    Physics Assessment of the Impact of Modified End Pellets on Axial Power Peaking for Advanced/Nonconventional Uranium-Based Fuels in Pressure Tube Heavy Water Reactors 

    Source: Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 009 ):;issue: 001:;page 11503
    Author(s): Yan, Huiping V.;Bromley, Blair P.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Axial power peaking is a phenomenon with safety implications for pressure tube heavy water reactors (PT-HWRs). Since PT-HWRs use shorter (∼50 cm) bundles, there are small axial gaps, which expose the ends of the fuel ...
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    Physics Evaluation of Alternative Uranium-Based Oxy-Carbide Annular Fuel Concepts for Potential Use in Compact High-Temperature Gas-Cooled Reactors 

    Source: Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 009 ):;issue: 001:;page 11504
    Author(s): Wojtaszek, Daniel T.;Bromley, Blair P.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Lattice physics calculations have been carried out to evaluate the performance and safety characteristics of a modified high temperature gas-cooled reactor (HTGR) prismatic fuel block concept, based on the MHTGR-350 benchmark ...
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    Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2023:;volume( 010 ):;issue: 002:;page 21502-1
    Author(s): Yan, Huiping V.; Bromley, Blair P.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Fluoride-salt-cooled high temperature reactor (FHR) effectively combines the solid fuel and moderator design of high-temperature gas-cooled reactor (HTGR) technology with the fluoride salt coolant (LiF-BeF2, FLiBe) of ...
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    TSUNAMI Analyses of the Similarity and Applicability of Zero Energy Deuterium 2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor Design Concept 

    Source: Journal of Nuclear Engineering and Radiation Science:;2024:;volume( 011 ):;issue: 002:;page 21501-1
    Author(s): Masala, Eugene; Blomeley, Laura; Watts, David G.; Bromley, Blair P.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper presents the findings of studies conducted at Canadian Nuclear Laboratories (CNL) to support the development of small modular reactor (SMR) designs. The primary focus of this research was to evaluate the suitability ...
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    Review of Canadian Experience With the Fabrication of Thoria-Based Fuels for Advanced Reactors and Fuel Cycles for Long-Term Nuclear Energy Sustainability and Security 

    Source: Journal of Nuclear Engineering and Radiation Science:;2024:;volume( 011 ):;issue: 002:;page 21604-1
    Author(s): Cota-Sanchez, Germán; Spencer, Madalena S.; Leeder, Kristin; Dimayuga, Ike; Bromley, Blair P.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Advanced fuels and fuel cycles are important for the current and next generation of advanced reactors, small modular reactors, and microreactors, in order to maximize the utilization of fissile and fertile nuclear fuel ...
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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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    Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels 

    Source: Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 008 ):;issue: 003:;page 31601
    Author(s): Bayomy, Ayman M.;Bromley, Blair P.;Nava Dominguez, Armando;Kelly, Samuel
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Thermalhydraulic analyses using subchannel codes (e.g., ASSERT-PV) are performed as a support tool to evaluate safety margins and the key parameters. Advanced fuels have recently attracted the international community's ...
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    Development and Testing of a System Thermal-Hydraulics Model for a 50-MWel-Class Pressurized Water Reactor–Small Modular Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 002:;page 21402-1
    Author(s): Wang, Shujun; Huang, Xianmin; Rao, Yanfei; Bromley, Blair P.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper describes the development, analysis, testing of a RELAP5-3D system thermal-hydraulics model for a 50-MWel-class pressurized water reactor–small modular reactor (PWR–SMR), similar to that by NuScale Power. This ...
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