Implementation of uranium enrichment cascade model to nuclear fuel cycle simulator

阿部 拓海; 鈴木 大河*; 岡村 知拓*; 中瀬 正彦*; 西原 健司; 竹下 健二*

no journal, , 

Nuclear power is gaining attention as a stable decarbonized energy source, with a global goal to triple capacity by 2050. However, increasing uranium demand raises concerns about supply shortages. Re-enriching recovered uranium (RU) from reprocessing can help reduce natural U consumption but requires consideration of isotopic composition for fuel design and radiation management. To analyze RU utilization, a uranium enrichment model based on an ideal cascade was implemented into the nuclear fuel cycle simulator NMB4. The model supports both gas diffusion and gas centrifuge methods, solving material balance and cascade equations for multiple isotopes. Validation against actual re-enriched RU fuel data showed good agreement.