Перевірка критеріїв безпеки змішаних завантажень ядерного палива для реакторів типу ВВЕР-1000
The thermal-hydraulic aspects of modeling the mixed core (several types of nuclear fuel) with TVSA, TVS-W and TVS-WR fuel are analyzed. The safety criteria for the maximal fuel cladding temperature are evaluated for representative events of design basis accident (DBA) analysis for WWER-1000 reactors...
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| Date: | 2015 |
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| Main Authors: | , |
| Format: | Article |
| Language: | Ukrainian |
| Published: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2015
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| Online Access: | https://nuclear-journal.com/index.php/journal/article/view/334 |
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| Journal Title: | Nuclear and Radiation Safety |
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Nuclear and Radiation Safety| Summary: | The thermal-hydraulic aspects of modeling the mixed core (several types of nuclear fuel) with TVSA, TVS-W and TVS-WR fuel are analyzed. The safety criteria for the maximal fuel cladding temperature are evaluated for representative events of design basis accident (DBA) analysis for WWER-1000 reactors using RELAP5/MOD3.2 computer code. It is shown that the maximal cladding temperature increases with introduction of new TVS-WR or TVS-W fuel as compared to TVSA. Preliminary analyses have shown that the maximal cladding temperature does not exceed its limit of 1200°С in the events involving seizure of the main coolant pump (MCP) and double-ended cold leg break of the main coolant piping. The results confirm the need for further thermal-hydraulic analysis of WWER-1000 mixed cores. DBA analysis has to be complemented with calculations for mixed cores. |
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