Експериментальні дослідження фрагмента попередньо напруженої захисної оболонки енергоблока атомної станції

Containment is a protective element of the reactor plant that isolates it from the environment and ensures the localization of radioactive substances in the subcontainment space in design basis accident. To ensure the tightness of the reactor compartment along the inner reinforced concrete surface o...

Повний опис

Збережено в:
Бібліографічні деталі
Видавець:State Scientific and Technical Center for Nuclear and Radiation Safety
Дата:2021
Автори: Bambura, А., Sazonova, I., Karpenko, А., Zharko, L., Fesenko, O., Iniushev, V., Zhygalov, I., Posokh, V.
Формат: Стаття
Мова:Ukrainian
Опубліковано: State Scientific and Technical Center for Nuclear and Radiation Safety 2021
Онлайн доступ:https://nuclear-journal.com/index.php/journal/article/view/767
Теги: Додати тег
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Репозиторії

Nuclear and Radiation Safety
Опис
Резюме:Containment is a protective element of the reactor plant that isolates it from the environment and ensures the localization of radioactive substances in the subcontainment space in design basis accident. To ensure the tightness of the reactor compartment along the inner reinforced concrete surface of containment, there is an 8 mm thick envelope steel wall (ESW). In accordance with current construction regulations, ESW should be checked for loss of stability when calculating the structure of containment. Testing the ESW elements for stability loss by the method described in the current regulation, PNAE G-10-007-89, has showed stability loss of ESW elements in maximum design basis accident (MDBA) what makes it impossible to extend the life of the reactor. To study this issue, a program of experimental studies was drawn up in order to maintain ESW integrity including integrity of welding joints in case of possible stability loss due to applied forces and thermal actions. The purpose of experimental study was to research the stress-strain state of physically and geometrically sound models of the containment of nuclear power plants in order to maintain ESW integrity including integrity of welding joints in case of stability loss under the influence of loads arising in maximum design basis accident. In preparing the experimental study engineering solutions were developed for test samples, models, and test equipment. The results from inspection of technical condition of containment and data on the real strength and composition of concrete were used in the development of test samples. According to the results of the survey of three test samples, it was found no stability loss of steel envelope of test samples thus no failure, damage, or leakage of the test samples were recorded.