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    Investigation of Centrifugal Pump Performance Under Two-Phase Flow Conditions

    Source: Journal of Fluids Engineering:;1995:;volume( 117 ):;issue: 001::page 129
    Author:
    G. R. Noghrehkar
    ,
    A. M. C. Chan
    ,
    H. Nakamura
    ,
    Y. Kukita
    ,
    M. Kawaji
    DOI: 10.1115/1.2816802
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A one-dimensional two-fluid model has been used to study the centrifugal pump head degradation phenomena and to analyze the gas-liquid interaction within the pump impeller under high pressure, steam-water two-phase flow conditions. The analytical model was used to predict the two-phase pump head data for the small-scale and full-scale nuclear reactor pumps and the predictions of the head degradation compared favorably with the test data for different suction void fractions. The physical mechanisms responsible for head degradation were also investigated.
    keyword(s): Two-phase flow , Centrifugal pumps , Pumps , Fluids , Suction , High pressure (Physics) , Nuclear reactors , Steam , Water , Pump impellers AND Mechanisms ,
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      Investigation of Centrifugal Pump Performance Under Two-Phase Flow Conditions

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/115554
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    • Journal of Fluids Engineering

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    contributor authorG. R. Noghrehkar
    contributor authorA. M. C. Chan
    contributor authorH. Nakamura
    contributor authorY. Kukita
    contributor authorM. Kawaji
    date accessioned2017-05-08T23:47:38Z
    date available2017-05-08T23:47:38Z
    date copyrightMarch, 1995
    date issued1995
    identifier issn0098-2202
    identifier otherJFEGA4-27093#129_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/115554
    description abstractA one-dimensional two-fluid model has been used to study the centrifugal pump head degradation phenomena and to analyze the gas-liquid interaction within the pump impeller under high pressure, steam-water two-phase flow conditions. The analytical model was used to predict the two-phase pump head data for the small-scale and full-scale nuclear reactor pumps and the predictions of the head degradation compared favorably with the test data for different suction void fractions. The physical mechanisms responsible for head degradation were also investigated.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleInvestigation of Centrifugal Pump Performance Under Two-Phase Flow Conditions
    typeJournal Paper
    journal volume117
    journal issue1
    journal titleJournal of Fluids Engineering
    identifier doi10.1115/1.2816802
    journal fristpage129
    journal lastpage137
    identifier eissn1528-901X
    keywordsTwo-phase flow
    keywordsCentrifugal pumps
    keywordsPumps
    keywordsFluids
    keywordsSuction
    keywordsHigh pressure (Physics)
    keywordsNuclear reactors
    keywordsSteam
    keywordsWater
    keywordsPump impellers AND Mechanisms
    treeJournal of Fluids Engineering:;1995:;volume( 117 ):;issue: 001
    contenttypeFulltext
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