Assessment of core radial power profile effect model for REFLA code by using CCTF data.
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概要
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A simple model was developed to evaluate the effect of the radial power profile on the thermo-hydraulics in the core during reflood phase of loss-of-coolant accident in PWRs. It was incorporated into REFLA code, a reflood analysis code.<BR>The model assumes that the fluid mixes completely among subchannels and additionally that the fuel temperature is not affected each other among fuels. This model is featuring no three-dimensional treatment for the evaluation on effect of the radial power profile.<BR>The model improved the predictability of clad temperature and gave a better prediction than a method which is generally used in the safety analysis. The model predicted a poorer core cooling in high radial power region than data. The error of the prediction increased with the increase in radial power ratio. These indicates the conservativeness of the model on the maximum clad temperature prediction. The reason of the conservativeness is due to the neglection of the heat transfer enhancement by two-dimensional effect in high power region.
- 一般社団法人 日本原子力学会の論文
著者
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Akimoto Hajime
Japan Atomic Energy Agency
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MURAO Yoshio
Japan Atomic Energy Research Institute
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IGUCHI Tadashi
Japan Atomic Energy Research Institute
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