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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| Date: | 2011 |
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| Main Authors: | , |
| Format: | Article |
| Language: | Ukrainian |
| Published: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2011
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| 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| Summary: | 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 secondary steamandwater mixture on the processes that occur in the reactor. |
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