Optimization of waste management for mixed oxide fuel in light-water reactors: Evaluation of the effectiveness of blending spent uo2 and mixed oxide fuels in reprocessing

The heat generated by Am-241 poses a challenge in the vitrification of spent mixed oxide (MOX) fuel after reprocessing. When the buffer material temperature exceeds the limit temperature of 100℃ due to the heat generated by vitrified waste, the buffer material quality is degraded, thereby affecting nuclide migration. Therefore, the waste-loading ratio of vitrified waste is estimated by heat generation, which determines the number of glass canisters and repository footprint. An option to reduce heat generation is to blend MOX high-level waste (HLW) with UO2 HLW. This study evaluated the thermal impact of blending MOX HLW with UO2 HLW while considering the cooling period and blending ratio. The maximum loading ratio was calculated for each blending condition in the range of buffer material temperatures below 100 °C, and the results were used to estimate the number of glass canisters and assess the repository footprint. Graphical abstract

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Optimization of waste management for mixed oxide fuel in light-water reactors: Evaluation of the effectiveness of blending spent uo2 and mixed oxide fuels in reprocessing

Cited by 3 publications

References 5 publications

Impact of MOX fuel use in light-water reactors: long-term radiological consequences of disposal of high-level waste in a geological repository

Impact of MOX fuel use in light-water reactors: long-term radiological consequences of disposal of high-level waste in a geological repository

Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations

Impact on repository footprint of blending spent mixed oxide fuels with UO2 fuels during reprocessing

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