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    Design Option of Heat Exchanger for the Next Generation Nuclear Plant

    Source: Journal of Engineering for Gas Turbines and Power:;2010:;volume( 132 ):;issue: 003::page 32903
    Author:
    Chang H. Oh
    ,
    Eung S. Kim
    ,
    Mike Patterson
    DOI: 10.1115/1.3126780
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The next generation nuclear plant (NGNP), a very high temperature gas-cooled reactor (VHTR) concept, will provide the first demonstration of a closed-loop Brayton cycle at a commercial scale, producing a few hundred megawatts of power in the form of electricity and hydrogen. The power conversion unit for the NGNP will take advantage of the significantly higher reactor outlet temperatures of the VHTRs to provide higher efficiencies than can be achieved with the current generation of light water reactors. Besides demonstrating a system design that can be used directly for subsequent commercial deployment, the NGNP will demonstrate key technology elements that can be used in subsequent advanced power conversion systems for other Generation IV reactors. In anticipation of the design, development, and procurement of an advanced power conversion system for the NGNP, the system integration of the NGNP and hydrogen plant was initiated to identify the important design and technology options that must be considered in evaluating the performance of the proposed NGNP. As part of the system integration of the VHTRs and the hydrogen production plant, the intermediate heat exchanger is used to transfer the process heat from VHTRs to the hydrogen plant. Therefore, the design and configuration of the intermediate heat exchanger are very important. This paper describes analyses of one stage versus two-stage heat exchanger design configurations and simple stress analyses of a printed circuit heat exchanger (PCHE), helical-coil heat exchanger, and shell-and-tube heat exchanger.
    keyword(s): Design , Heat exchangers , Temperature , Shells , High temperature AND Heat transfer ,
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      Design Option of Heat Exchanger for the Next Generation Nuclear Plant

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    http://yetl.yabesh.ir/yetl1/handle/yetl/143263
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    • Journal of Engineering for Gas Turbines and Power

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    contributor authorChang H. Oh
    contributor authorEung S. Kim
    contributor authorMike Patterson
    date accessioned2017-05-09T00:37:51Z
    date available2017-05-09T00:37:51Z
    date copyrightMarch, 2010
    date issued2010
    identifier issn1528-8919
    identifier otherJETPEZ-27100#032903_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/143263
    description abstractThe next generation nuclear plant (NGNP), a very high temperature gas-cooled reactor (VHTR) concept, will provide the first demonstration of a closed-loop Brayton cycle at a commercial scale, producing a few hundred megawatts of power in the form of electricity and hydrogen. The power conversion unit for the NGNP will take advantage of the significantly higher reactor outlet temperatures of the VHTRs to provide higher efficiencies than can be achieved with the current generation of light water reactors. Besides demonstrating a system design that can be used directly for subsequent commercial deployment, the NGNP will demonstrate key technology elements that can be used in subsequent advanced power conversion systems for other Generation IV reactors. In anticipation of the design, development, and procurement of an advanced power conversion system for the NGNP, the system integration of the NGNP and hydrogen plant was initiated to identify the important design and technology options that must be considered in evaluating the performance of the proposed NGNP. As part of the system integration of the VHTRs and the hydrogen production plant, the intermediate heat exchanger is used to transfer the process heat from VHTRs to the hydrogen plant. Therefore, the design and configuration of the intermediate heat exchanger are very important. This paper describes analyses of one stage versus two-stage heat exchanger design configurations and simple stress analyses of a printed circuit heat exchanger (PCHE), helical-coil heat exchanger, and shell-and-tube heat exchanger.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleDesign Option of Heat Exchanger for the Next Generation Nuclear Plant
    typeJournal Paper
    journal volume132
    journal issue3
    journal titleJournal of Engineering for Gas Turbines and Power
    identifier doi10.1115/1.3126780
    journal fristpage32903
    identifier eissn0742-4795
    keywordsDesign
    keywordsHeat exchangers
    keywordsTemperature
    keywordsShells
    keywordsHigh temperature AND Heat transfer
    treeJournal of Engineering for Gas Turbines and Power:;2010:;volume( 132 ):;issue: 003
    contenttypeFulltext
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