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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Bibliographic Details
Date:2016
Main Authors: Kotsuba, O., Vorobyov, Yu., Zhabin, O., Gumenyk, D.
Format: Article
Language:Ukrainian
Published: State Scientific and Technical Center for Nuclear and Radiation Safety 2016
Online Access:https://nuclear-journal.com/index.php/journal/article/view/41
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Journal Title:Nuclear and Radiation Safety

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Nuclear and Radiation Safety