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    Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 004::page 041301-1
    Author:
    Bittan, Jeremy
    ,
    Bore, Clement
    ,
    Guidez, Joel
    DOI: 10.1115/1.4048991
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In the frame of the ESFR-SMART European project, aiming at improving the safety level of the European sodium cooled fast reactor (ESFR), this paper presents the preliminary assessment of decay heat removal systems (DHRSs) in the ESFR-SMART design: the role of natural air convection around steam generators (SGs) outer shells in accidental conditions. Both theoretical and CATHARE code (thermal hydraulics reference code) calculations are presented. The impact of an additional chimney at the top of each casing as well as running primary and secondary pumps on the heat removal capacity is equally evaluated. This paper shows that the evacuation of decay heat thanks to completely passive air natural circulation alone, in case of Fukushima like accident, should lead to temperatures of sodium in the reactor vessel temporarily exceeding the safety criterion of 650 °C. The addition of chimneys increases the capacities but is not sufficient to evacuate the decay heat safely. If the primary and secondary side pumps are running, the safety criterion should be met.
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      Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4276554
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    contributor authorBittan, Jeremy
    contributor authorBore, Clement
    contributor authorGuidez, Joel
    date accessioned2022-02-05T21:54:29Z
    date available2022-02-05T21:54:29Z
    date copyright4/16/2021 12:00:00 AM
    date issued2021
    identifier issn2332-8983
    identifier otherners_007_04_041301.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4276554
    description abstractIn the frame of the ESFR-SMART European project, aiming at improving the safety level of the European sodium cooled fast reactor (ESFR), this paper presents the preliminary assessment of decay heat removal systems (DHRSs) in the ESFR-SMART design: the role of natural air convection around steam generators (SGs) outer shells in accidental conditions. Both theoretical and CATHARE code (thermal hydraulics reference code) calculations are presented. The impact of an additional chimney at the top of each casing as well as running primary and secondary pumps on the heat removal capacity is equally evaluated. This paper shows that the evacuation of decay heat thanks to completely passive air natural circulation alone, in case of Fukushima like accident, should lead to temperatures of sodium in the reactor vessel temporarily exceeding the safety criterion of 650 °C. The addition of chimneys increases the capacities but is not sufficient to evacuate the decay heat safely. If the primary and secondary side pumps are running, the safety criterion should be met.
    publisherThe American Society of Mechanical Engineers (ASME)
    titlePreliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions
    typeJournal Paper
    journal volume7
    journal issue4
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4048991
    journal fristpage041301-1
    journal lastpage041301-9
    page9
    treeJournal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 004
    contenttypeFulltext
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