Аналіз умов виникнення термоудару корпусу реактора з урахуванням виконаних модернізацій систем, важливих для безпеки
The paper analyzes conditions of pressurized thermal shock on the reactor pressure vessel taking into account upgrading of the emergency core cooling system and primary overpressure protection system. For representative accident scenarios, calculation and comparative analysis was carried out. These...
Збережено в:
Дата: | 2015 |
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Автори: | , |
Формат: | Стаття |
Мова: | Ukrainian |
Опубліковано: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2015
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Онлайн доступ: | https://nuclear-journal.com/index.php/journal/article/view/336 |
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Назва журналу: | Nuclear and Radiation Safety |
Репозитарії
Nuclear and Radiation SafetyРезюме: | The paper analyzes conditions of pressurized thermal shock on the reactor pressure vessel taking into account upgrading of the emergency core cooling system and primary overpressure protection system. For representative accident scenarios, calculation and comparative analysis was carried out. These scenarios include a small leak from the hot leg and PRZ SV stuck opening with reclosure after 3600 sec and 3 SG heat transfer tube rupture.
The efficiency of mass flow control by valves on the pump head (emergency core cooling systems) and cold overpressure protection (primary overpressure protection system) was analyzed.
The thermal hydraulic model for RELAP5/Mod3.2 code with detailed downcomer (DC) model and changes in accordance with upgrades was used for calculations. Detailed (realistic) modeling of piping and equipment was performed.
The upgrades prevent excessive primary cooling and, consequently, help to preserve the RPV integrity and to avoid the formation of a through crack, which can lead to a severe accident. |
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