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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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    Two-Phase Flow Analysis of Concentration Profiles 

    Source: Journal of Hydraulic Engineering:;2001:;Volume ( 127 ):;issue: 009
    Author(s): Blair P. Greimann; Forrest M. Holly Jr.
    Publisher: American Society of Civil Engineers
    Abstract: Two-phase flow analysis is used to analyze sediment concentration profiles in uniform open-channel flows over flat, sediment-starved beds that have high concentrations of single-sized sediment. Two-phase flow analysis can ...
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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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    Soft Bedrock Erosion Modeling with a Two-Dimensional Depth-Averaged Model 

    Source: Journal of Hydraulic Engineering:;2011:;Volume ( 137 ):;issue: 008
    Author(s): Yong G. Lai; Blair P. Greimann; Kuowei Wu
    Publisher: American Society of Civil Engineers
    Abstract: Many rivers in Taiwan have steep slopes, are subject to typhoon-induced flood flows, and contain soft bedrock that is exposed at many locations and easily erodible. The occurrence of extensive bedrock erosion has been a ...
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    Evaluation of Parameter and Model Uncertainty in Simple Applications of a 1D Sediment Transport Model 

    Source: Journal of Hydraulic Engineering:;2015:;Volume ( 141 ):;issue: 005
    Author(s): Shaina M. Sabatine; Jeffrey D. Niemann; Blair P. Greimann
    Publisher: American Society of Civil Engineers
    Abstract: This paper separately evaluates two methods from Bayesian Statistics to estimate parameter and model uncertainty in simulations from a one-dimensional (1D) sediment transport model. The first method, multivariate shuffled ...
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    Combining Predictions and Assessing Uncertainty from Sediment Transport Equations Using Multivariate Bayesian Model Averaging 

    Source: Journal of Hydraulic Engineering:;2018:;Volume ( 144 ):;issue: 004
    Author(s): Jung Jeffrey Y.;Niemann Jeffrey D.;Greimann Blair P.
    Publisher: American Society of Civil Engineers
    Abstract: A key assumption in the use of numerical sediment transport models is the selection and application of an equation to describe sediment transport capacity. This assumption introduces uncertainty in the model predictions ...
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