[2B18-21] MOX Reprocessing and Cycle Evaluation

[2B20] Implementation of a calculation model to simulate re-enrichment of recovered uranium in nuclear fuel cycle simulator NMB4.0

*Takumi Abe¹, Kenji Nishihara¹ (1. JAEA)

Keywords:Nuclear fuel cycle, Recovered uranium, Re-enrichment of uranium, Scenario analysis, NMB4.0

In the nuclear fuel cycle simulator NMB4.0 being developed at JAEA, a model to numerically calculate the composition of new fuel when recovered uranium is re-enriched has been implemented. Using this function, we evaluated various quantities of re-enrichment of recovered uranium in the case of future nuclear power use in Japan, using the U-235 fraction of depleted uranium and other parameters. In this presentation, we will report the calculation method used in the function and the results of the evaluation of various quantities.