Розрахунок фізики реактора і термомеханічних характеристик топливних стрижнів, що знаходяться поряд з поглиначами в реакторі ВВЕР-440
The WER-440 absorber withdrawal can lead to relatively large local power increase. In spite of the Hf shielding, the largest local power changes can frequently occur next to the absorber, which can lead to an increased hoop stress and fatigue of the cladding. The paper is summarizing the related rea...
Збережено в:
| Дата: | 2007 |
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| Автори: | , , , , , |
| Формат: | Стаття |
| Мова: | English |
| Опубліковано: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2007
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| Онлайн доступ: | https://nuclear-journal.com/index.php/journal/article/view/1071 |
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| Назва журналу: | Nuclear and Radiation Safety |
Репозитарії
Nuclear and Radiation Safety| Резюме: | The WER-440 absorber withdrawal can lead to relatively large local power increase. In spite of the Hf shielding, the largest local power changes can frequently occur next to the absorber, which can lead to an increased hoop stress and fatigue of the cladding. The paper is summarizing the related reactor physics methods, applied in the KARATE code system and in the supporting by Monte Carlo calculations. The validation procedure using measurements and Monte Carlo results is also detailed. The reactor physics results were used in the further stress and fatigue thermal mechanics calculations. The FUROM code was applied for this purpose. The FUROM results are utilized to evaluate the WER-440 maneuvering capability meanwhile the influence of the Hf shielding is pointed out. |
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