Thermodynamic Assessment of UO<sub>2</sub> Pellet Oxidation in Mixture Atmospheres under Spent Fuel Pool Accident
- 1 LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea
- 2 LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea
- 3 LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea
- 4 LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea
- 5 LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea
- 6 LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea
Abstract
For an analysis of the oxidation behavior of UO 2 nuclear fuel pellet under a loss of water coolant accident in a spent nuclear fuel pool of an LWR, thermodynamic assessments of UO 2 oxidation were carried out under various atmospheric conditions. In a steam atmosphere, it was assessed that UO 2 would not be fully oxidized into U 3 O 8 due to the relatively lower oxygen partial pressure, while UO 2 will be fully oxidized into U 3 O 8 in an air atmosphere. In an air and steam mixture atmosphere, the UO 2 oxidation was dominantly affected by the air volumetric fraction, because of the relatively higher oxygen partial pressure of air. In addition, the effect of H 2 volumetric fraction on the oxygen partial pressure under a mixture atmosphere was calculated, and it was revealed that UO 2 pellet oxidation could be reduced above the critical value of H 2 volumetric fraction.
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