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    Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

    Source: Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 008 ):;issue: 003::page 31401-1
    Author:
    Baisov, A. M.
    ,
    Churkin, A. N.
    ,
    Deev, V. I.
    ,
    Kharitonov, V. S.
    DOI: 10.1115/1.4053049
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The paper describes a modified version of the tempa-sc computer program designed to calculate temperature fields in bundles of rods cooled by a supercritical pressure (SCP) fluid. This version of the program is based on the subchannel method that was used in the tempa-1f program, developed earlier in the OKB “GIDROPRESS” for calculating heat and mass transfer in the core of VVER-type reactors cooled by single-phase water at subcritical pressure. As the relations that close the system of equations of mass, momentum, and energy conservation, the new version of the program includes correlations for calculating heat transfer and friction resistance, taking into account the strong dependence of the properties of the coolant on temperature and pressure. In particular, the use of the universal calculation model of heat transfer, developed by the authors of this paper, allows us to perform calculations in a wide range of flow parameters of various fluids, including the modes of normal, improved and deteriorated heat transfer. The results of tests of the tempa-sc program are presented in comparison with the available experimental data for water and modeling fluids (carbon dioxide, freons R-12 and R-134a) at SCPs, as well as with the published data of calculations by using similar subchannel programs (cobra-sc, assert-pv) and CFD codes. A qualitative agreement between the calculated and experimental data is shown.
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      Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4284046
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorBaisov, A. M.
    contributor authorChurkin, A. N.
    contributor authorDeev, V. I.
    contributor authorKharitonov, V. S.
    date accessioned2022-05-08T08:32:02Z
    date available2022-05-08T08:32:02Z
    date copyright3/22/2022 12:00:00 AM
    date issued2022
    identifier issn2332-8983
    identifier otherners_008_03_031401.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4284046
    description abstractThe paper describes a modified version of the tempa-sc computer program designed to calculate temperature fields in bundles of rods cooled by a supercritical pressure (SCP) fluid. This version of the program is based on the subchannel method that was used in the tempa-1f program, developed earlier in the OKB “GIDROPRESS” for calculating heat and mass transfer in the core of VVER-type reactors cooled by single-phase water at subcritical pressure. As the relations that close the system of equations of mass, momentum, and energy conservation, the new version of the program includes correlations for calculating heat transfer and friction resistance, taking into account the strong dependence of the properties of the coolant on temperature and pressure. In particular, the use of the universal calculation model of heat transfer, developed by the authors of this paper, allows us to perform calculations in a wide range of flow parameters of various fluids, including the modes of normal, improved and deteriorated heat transfer. The results of tests of the tempa-sc program are presented in comparison with the available experimental data for water and modeling fluids (carbon dioxide, freons R-12 and R-134a) at SCPs, as well as with the published data of calculations by using similar subchannel programs (cobra-sc, assert-pv) and CFD codes. A qualitative agreement between the calculated and experimental data is shown.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleTesting the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes
    typeJournal Paper
    journal volume8
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4053049
    journal fristpage31401-1
    journal lastpage31401-9
    page9
    treeJournal of Nuclear Engineering and Radiation Science:;2022:;volume( 008 ):;issue: 003
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
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