Аналіз важких аварій в басейні витримки відпрацьованого ядерного палива АЕС «Фукусіма-Даїчі» з використанням розрахункового коду MELCOR 1.8.6

The paper presents specific approaches to modeling the spent fuel pool (SFP) of Fukushima Daiichi NPP and results of thermohydraulic calculations of severe accidents in SFP using MELCOR 1.8.6 computer code. The dynamics of main processes accompanying severe accident progression in SFP of such a type...

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Bibliographische Detailangaben
Datum:2016
Hauptverfasser: Kotsuba, O., Vorobyov, Yu., Zhabin, O., Gumenyk, D.
Format: Artikel
Sprache:Ukrainian
Veröffentlicht: State Scientific and Technical Center for Nuclear and Radiation Safety 2016
Online Zugang:https://nuclear-journal.com/index.php/journal/article/view/41
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Назва журналу:Nuclear and Radiation Safety

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Nuclear and Radiation Safety
Beschreibung
Zusammenfassung:The paper presents specific approaches to modeling the spent fuel pool (SFP) of Fukushima Daiichi NPP and results of thermohydraulic calculations of severe accidents in SFP using MELCOR 1.8.6 computer code. The dynamics of main processes accompanying severe accident progression in SFP of such a type was defined based on computer analysis. Obtained results may be used to improve available SFP computer models to receive more reliable data on the progression of emergency processes in NPP SFPs.