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...
Збережено в:
| Видавець: | State Scientific and Technical Center for Nuclear and Radiation Safety |
|---|---|
| Дата: | 2011 |
| Автори: | , |
| Формат: | Стаття |
| Мова: | Ukrainian |
| Опубліковано: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2011
|
| Онлайн доступ: | https://nuclear-journal.com/index.php/journal/article/view/537 |
| Теги: |
Додати тег
Немає тегів, Будьте першим, хто поставить тег для цього запису!
|
Репозиторії
Nuclear and Radiation Safety| Резюме: | 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. |
|---|