Оцінка застосовності моделі деформації оболонок твелів розрахункового коду RELAP5/MOD3.2 для палива реакторів ВВЕР-1000
Applicability of cladding deformation model in RELAP5/MOD3.2 code is analyzed for VVER‑1000 fuel cladding from Zr+1%Nb alloy. Experimental data and calculation model of fuel assembly channel of the core are used for this purpose. The model applicability is tested for the cladding temperature range f...
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/303 |
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| Назва журналу: | Nuclear and Radiation Safety |
Репозитарії
Nuclear and Radiation Safety| Резюме: | Applicability of cladding deformation model in RELAP5/MOD3.2 code is analyzed for VVER‑1000 fuel cladding from Zr+1%Nb alloy. Experimental data and calculation model of fuel assembly channel of the core are used for this purpose. The model applicability is tested for the cladding temperature range from 600 to 1200°С and pressure range from 1 to 12 MPa. Evaluation results demonstrate limited applicability of built-in RELAP5/MOD3.2 cladding deformation model to the estimation of Zr+1%Nb cladding rupture conditions. The limitations found shall be considered in application of RELAP5/MOD3.2 cladding deformation model in the design-basis accident analysis of VVER reactors. |
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