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- W2023806879 abstract "Preliminary study on direct recycling of PWR spent fuel to support SUPEL (Straight Utilization of sPEnt LWR fuel in LWR system) scenario has been conducted. Several spent PWR fuel compositions in loaded PWR fuel has been evaluated to obtain the criticality of reactor. The reactor can achieve it criticality for U-235 enrichment in the loaded fresh fuel is at least 4.0 a% with the minimum fraction of the spent fuel in the core is 15.0 %. The neutron spectra become harder with the escalating of U-235 enrichment in the loaded fresh fuel as well as the amount of the spent fuel in the core." @default.
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- W2023806879 date "2012-01-01" @default.
- W2023806879 modified "2023-09-27" @default.
- W2023806879 title "Preliminary study on direct recycling of spent PWR fuel in PWR system" @default.
- W2023806879 doi "https://doi.org/10.1063/1.4725448" @default.
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