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    Coupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001::page 11017
    Author:
    Madokoro, Hiroshi
    ,
    Miassoedov, Alexei
    ,
    Schulenberg, Thomas
    DOI: 10.1115/1.4041278
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Due to the recent high interest on in-vessel melt retention (IVR), development of detailed thermal and structural analysis tool, which can be used in a core-melt severe accident, is inevitable. Although RELAP/SCDAPSIM is a reactor analysis code, originally developed for U.S. NRC, which is still widely used for severe accident analysis, the modeling of the lower head is rather simple, considering only a homogeneous pool. PECM/S, a thermal structural analysis solver for the reactor pressure vessel (RPV) lower head, has a capability of predicting molten pool heat transfer as well as detailed mechanical behavior including creep, plasticity, and material damage. The boundary condition, however, needs to be given manually and thus the application of the stand-alone PECM/S to reactor analyses is limited. By coupling these codes, the strength of both codes can be fully utilized. Coupled analysis is realized through a message passing interface, OpenMPI. The validation simulations have been performed using LIVE test series and the calculation results are compared not only with the measured values but also with the results of stand-alone RELAP/SCDAPSIM simulations.
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      Coupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4255626
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorMadokoro, Hiroshi
    contributor authorMiassoedov, Alexei
    contributor authorSchulenberg, Thomas
    date accessioned2019-03-17T09:41:58Z
    date available2019-03-17T09:41:58Z
    date copyright1/24/2019 12:00:00 AM
    date issued2019
    identifier issn2332-8983
    identifier otherners_005_01_011017.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4255626
    description abstractDue to the recent high interest on in-vessel melt retention (IVR), development of detailed thermal and structural analysis tool, which can be used in a core-melt severe accident, is inevitable. Although RELAP/SCDAPSIM is a reactor analysis code, originally developed for U.S. NRC, which is still widely used for severe accident analysis, the modeling of the lower head is rather simple, considering only a homogeneous pool. PECM/S, a thermal structural analysis solver for the reactor pressure vessel (RPV) lower head, has a capability of predicting molten pool heat transfer as well as detailed mechanical behavior including creep, plasticity, and material damage. The boundary condition, however, needs to be given manually and thus the application of the stand-alone PECM/S to reactor analyses is limited. By coupling these codes, the strength of both codes can be fully utilized. Coupled analysis is realized through a message passing interface, OpenMPI. The validation simulations have been performed using LIVE test series and the calculation results are compared not only with the measured values but also with the results of stand-alone RELAP/SCDAPSIM simulations.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleCoupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver
    typeJournal Paper
    journal volume5
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4041278
    journal fristpage11017
    journal lastpage011017-9
    treeJournal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001
    contenttypeFulltext
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