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Розрахунок фізики реактора і термомеханічних характеристик топливних стрижнів, що знаходяться поряд з поглиначами в реакторі ВВЕР-440

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...

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Bibliographic Details
Main Authors: Keresztúri, A., Griger, Á., Maráczy, Cs., Hegyi, Gy., Hordósy, G., Temesvári, E.
Format: Article
Language:English
Published: State Scientific and Technical Center for Nuclear and Radiation Safety 2007
Online Access:https://nuclear-journal.com/index.php/journal/article/view/1071
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Summary: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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