Вплив урахування рециркуляції в парогенераторi на динаміку перехідних процесів реакторної установки, розрахованих з використанням коду Melcor

This paper focuses on modeling of the nuclear steam supply system (NSSS) with use of the MELCOR computer code. Two models of NSSS with a steam generator presented as one and three volumes are compared. The volume of the steam generator is divided to evaluate the effect of recirculation of the second...

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Bibliographic Details
Date:2011
Main Authors: Chuklin, A., Sheveljov, D.
Format: Article
Language:Ukrainian
Published: State Scientific and Technical Center for Nuclear and Radiation Safety 2011
Online Access:https://nuclear-journal.com/index.php/journal/article/view/537
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Journal Title:Nuclear and Radiation Safety

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Nuclear and Radiation Safety