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    Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 003::page 31016
    Author:
    Fernández-Cosials, Kevin
    ,
    Jiménez, Gonzalo
    ,
    Serrano, César
    ,
    Ibáñez, Luisa
    ,
    Peinado, Ángel
    DOI: 10.1115/1.4038595
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: During a severe accident (SA) in a nuclear power plant (NPP), there are several challenges that need to be faced. To coup with a containment overpressure, the venting action will lower the pressure but it will release radioactivity to the environment. In order to reduce the radioactivity released, a filtered containment venting system (FCVS) can be used to retain iodine and aerosols radioactive releases coming from the containment atmosphere. However, during a SA, large quantities of hydrogen can also be generated. Hydrogen reacts violently with oxygen and its combustion could impair systems, components, or structures. For this reason, to protect the integrity of the FCVS against hydrogen explosions, an inertization system is found necessary. This system should create an inert atmosphere previous to any containment venting that impedes the contact of hydrogen and oxygen. In this paper, the inertization system for Cofrentes NPP is presented. It consists of a nitrogen injection located in three different points. A computational model of the FCVS as well as the inertization system has been created. The results show that if the nitrogen sweeps and the containment venting are properly synchronized, the hydrogen risk could be reduced to a minimum and therefore, the integrity of the FCVS would be preserved.
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      Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant

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    contributor authorFernández-Cosials, Kevin
    contributor authorJiménez, Gonzalo
    contributor authorSerrano, César
    contributor authorIbáñez, Luisa
    contributor authorPeinado, Ángel
    date accessioned2019-02-28T11:05:24Z
    date available2019-02-28T11:05:24Z
    date copyright5/16/2018 12:00:00 AM
    date issued2018
    identifier issn2332-8983
    identifier otherners_004_03_031016.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252559
    description abstractDuring a severe accident (SA) in a nuclear power plant (NPP), there are several challenges that need to be faced. To coup with a containment overpressure, the venting action will lower the pressure but it will release radioactivity to the environment. In order to reduce the radioactivity released, a filtered containment venting system (FCVS) can be used to retain iodine and aerosols radioactive releases coming from the containment atmosphere. However, during a SA, large quantities of hydrogen can also be generated. Hydrogen reacts violently with oxygen and its combustion could impair systems, components, or structures. For this reason, to protect the integrity of the FCVS against hydrogen explosions, an inertization system is found necessary. This system should create an inert atmosphere previous to any containment venting that impedes the contact of hydrogen and oxygen. In this paper, the inertization system for Cofrentes NPP is presented. It consists of a nitrogen injection located in three different points. A computational model of the FCVS as well as the inertization system has been created. The results show that if the nitrogen sweeps and the containment venting are properly synchronized, the hydrogen risk could be reduced to a minimum and therefore, the integrity of the FCVS would be preserved.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleAnalysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant
    typeJournal Paper
    journal volume4
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4038595
    journal fristpage31016
    journal lastpage031016-13
    treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 003
    contenttypeFulltext
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