Теплогідравлічний аналіз безпеки змішаних паливних завантажень для АЕС України з реакторами ВВЕР-1000
The paper presents thermal-hydraulic analysis of mixed core loads to confirm compliance with safety criteria. The objective is to verify reliability of nuclear fuel cooling in representative events of the design-basis accident analysis. RELAP5/MOD3.2 computer code was applied to show that maximum fu...
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| Date: | 2016 |
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| Main Authors: | , , , |
| Format: | Article |
| Language: | Ukrainian |
| Published: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2016
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| Online Access: | https://nuclear-journal.com/index.php/journal/article/view/14 |
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| Journal Title: | Nuclear and Radiation Safety |
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Nuclear and Radiation Safety| Summary: | The paper presents thermal-hydraulic analysis of mixed core loads to confirm compliance with safety criteria. The objective is to verify reliability of nuclear fuel cooling in representative events of the design-basis accident analysis. RELAP5/MOD3.2 computer code was applied to show that maximum fuel cladding temperature does not exceed 1200 °C in mixed TVSA-12, TVS-WR and TVSA cores.
The analysis led to the conclusion on possible safe implementation of new fuel at Ukrainian NPPs. |
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