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    Comparison Analysis on the Hydraulic Performance and Flow Characteristics on a Reactor Coolant Pump Under Rated Operating Condition Between Lead–Bismuth Eutectic and Water Mediums

    Source: Journal of Fluids Engineering:;2025:;volume( 147 ):;issue: 006::page 61204-1
    Author:
    Lu, Shangxiang
    ,
    Jiang, Huimeng
    ,
    Wu, Peng
    ,
    Huang, Bin
    ,
    Wu, Dazhuan
    DOI: 10.1115/1.4067550
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Advanced Generation IV nuclear reactors aim to enhance the sustainability, passive safety, reliability, and economic efficiency of reactor operations. Within that, the reactor coolant pump is a critical component in the reactor's cooling system, due to the unique characteristics of the transported medium, posing challenges for engineering applications. This study focuses on a mixed-flow nuclear reactor coolant pump, indicating that significant differences in hydraulic performance and flow characteristics arise due to the varying flow Reynolds numbers under identical operating conditions for the two mediums. Research employing quantitative analysis of boundary layer friction losses and flow separation-induced flow blockage elucidates the origins of hydraulic performance differences. Subsequent studies focusing on the flow characteristics within the impeller reveal that, while the flow patterns inside the impeller show no fundamental differences, an increase in Reynolds number intensifies flow slippage phenomenon, partially diminishing the impeller's work capability. Analysis in static components indicates that the stronger centrifugal forces lead to increased nonuniformity in flow distribution within the guide vanes and an amplified wake phenomenon within the outlet pipe.
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      Comparison Analysis on the Hydraulic Performance and Flow Characteristics on a Reactor Coolant Pump Under Rated Operating Condition Between Lead–Bismuth Eutectic and Water Mediums

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/4306532
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    contributor authorLu, Shangxiang
    contributor authorJiang, Huimeng
    contributor authorWu, Peng
    contributor authorHuang, Bin
    contributor authorWu, Dazhuan
    date accessioned2025-04-21T10:36:11Z
    date available2025-04-21T10:36:11Z
    date copyright1/23/2025 12:00:00 AM
    date issued2025
    identifier issn0098-2202
    identifier otherfe_147_06_061204.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4306532
    description abstractAdvanced Generation IV nuclear reactors aim to enhance the sustainability, passive safety, reliability, and economic efficiency of reactor operations. Within that, the reactor coolant pump is a critical component in the reactor's cooling system, due to the unique characteristics of the transported medium, posing challenges for engineering applications. This study focuses on a mixed-flow nuclear reactor coolant pump, indicating that significant differences in hydraulic performance and flow characteristics arise due to the varying flow Reynolds numbers under identical operating conditions for the two mediums. Research employing quantitative analysis of boundary layer friction losses and flow separation-induced flow blockage elucidates the origins of hydraulic performance differences. Subsequent studies focusing on the flow characteristics within the impeller reveal that, while the flow patterns inside the impeller show no fundamental differences, an increase in Reynolds number intensifies flow slippage phenomenon, partially diminishing the impeller's work capability. Analysis in static components indicates that the stronger centrifugal forces lead to increased nonuniformity in flow distribution within the guide vanes and an amplified wake phenomenon within the outlet pipe.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleComparison Analysis on the Hydraulic Performance and Flow Characteristics on a Reactor Coolant Pump Under Rated Operating Condition Between Lead–Bismuth Eutectic and Water Mediums
    typeJournal Paper
    journal volume147
    journal issue6
    journal titleJournal of Fluids Engineering
    identifier doi10.1115/1.4067550
    journal fristpage61204-1
    journal lastpage61204-12
    page12
    treeJournal of Fluids Engineering:;2025:;volume( 147 ):;issue: 006
    contenttypeFulltext
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