Abstract
To clarify the generation pathway of 232U, an important nuclide for dose evaluation at various stages in the reuse of uranium, concentrations of 232U generated through various pathways were evaluated for UO2 and mixed oxide (MOX) fuels. Burnup calculation was conducted with ORIGEN2.2 code adopting ORLIBJ40 library, a set of cross-section libraries based on JENDL-4.0. It was found that differences in 232U concentrations in UO2 and MOX fuels mainly arise from differences in the initial compositions of 234U, 235U, and 236U. It was also found that the contribution of plutonium and americium isotopes in MOX fuels is small compared with that of uranium isotopes. The results clarified that the capture cross sections of 230Th, 231Pa, 235U, and 236U, as well as the (n,2n) cross sections of 237Np and 238U, have a large effect on the generation of 232U. Additional investigation showed that 232U concentration is strongly affected not only by time after irradiation but also by time before irradiation.
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