Застосування імовірнісних методів аналізу безпеки АЕС у дослідженні порушення крихкої міцності корпусу реактора
The paper describes analysis of PSA-1 models. The objectives of the analysis are to identify, group and assess the frequency of potential scenarios of brittle fracture of the reactor pressure vessel due to thermal shock and cold overpressure using Zaporizhzhya NPP Unit No. 1 as an example. The most...
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| Date: | 2013 |
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| Main Authors: | , , , |
| Format: | Article |
| Language: | Ukrainian |
| Published: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2013
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| Online Access: | https://nuclear-journal.com/index.php/journal/article/view/526 |
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| Journal Title: | Nuclear and Radiation Safety |
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Nuclear and Radiation Safety| Summary: | The paper describes analysis of PSA-1 models. The objectives of the analysis are to identify, group and assess the frequency of potential scenarios of brittle fracture of the reactor pressure vessel due to thermal shock and cold overpressure using Zaporizhzhya NPP Unit No. 1 as an example. The most significant potential scenarios of brittle fracture for the reactor vessel in terms of risks were identified by calculations using the modified PSA-1 models. |
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