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    Analyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 001::page 11017
    Author:
    Gad-Briggs, A.
    ,
    Pilidis, P.
    DOI: 10.1115/1.4033398
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: As a nongreenhouse gas-emitting source, the benefits of nuclear as a main power-generation alternative are yet to be fully explored; part of the reason is due to the significant implementation costs. However, with cycle efficiencies of 45–50% in current studies, it can be argued that the long-term benefits outweigh the initial costs, if developed under the Generation-IV (Gen-IV) framework. The main objective of this study is to analyze the effects of pressure and temperature ratios (TRs) including sensitivity analyses of component efficiencies, ambient temperature, component losses and pressure losses on cycle efficiency and specific work. The results obtained indicate that pressure losses and recuperator effectiveness have the greatest impact on cycle efficiency and specific work. The analyses intend to aid development of the simple cycle recuperated (SCR) and intercooled cycle recuperated (ICR) cycles, applicable to gas-cooled fast reactors (GFRs) and very-high-temperature reactors (VHTRs), in which helium is the coolant.
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      Analyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants

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    https://yetl.yabesh.ir/yetl1/handle/yetl/4235414
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorGad-Briggs, A.
    contributor authorPilidis, P.
    date accessioned2017-11-25T07:18:47Z
    date available2017-11-25T07:18:47Z
    date copyright2016/20/12
    date issued2017
    identifier issn2332-8983
    identifier otherners_3_1_011017.pdf
    identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4235414
    description abstractAs a nongreenhouse gas-emitting source, the benefits of nuclear as a main power-generation alternative are yet to be fully explored; part of the reason is due to the significant implementation costs. However, with cycle efficiencies of 45–50% in current studies, it can be argued that the long-term benefits outweigh the initial costs, if developed under the Generation-IV (Gen-IV) framework. The main objective of this study is to analyze the effects of pressure and temperature ratios (TRs) including sensitivity analyses of component efficiencies, ambient temperature, component losses and pressure losses on cycle efficiency and specific work. The results obtained indicate that pressure losses and recuperator effectiveness have the greatest impact on cycle efficiency and specific work. The analyses intend to aid development of the simple cycle recuperated (SCR) and intercooled cycle recuperated (ICR) cycles, applicable to gas-cooled fast reactors (GFRs) and very-high-temperature reactors (VHTRs), in which helium is the coolant.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleAnalyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants
    typeJournal Paper
    journal volume3
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4033398
    journal fristpage11017
    journal lastpage011017-8
    treeJournal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 001
    contenttypeFulltext
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