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A Study of the generation of $$^{232}$$U in UO$$_{2}$$ and MOX fuels

Yamamoto, Kento; Okumura, Keisuke

To clarify the generation pathway of $$^{232}$$U in burned fuels, which is an important nuclide for dose evaluation at various stages in fuel cycle, concentrations of $$^{232}$$U generated through various pathways were evaluated for UO$$_{2}$$ and MOX fuels at 45 GWd/t using the ORIGEN2.2 code. It was found that the difference of $$^{232}$$U concentrations in UO$$_{2}$$ and MOX fuel are mainly derived from the difference of the initial compositions of $$^{234}$$U, $$^{235}$$U and $$^{236}$$U and the contribution of plutonium and americium isotopes in MOX fuels is not so large compared with that of uranium isotopes. The results clarified that the capture cross sections of $$^{230}$$Th, $$^{231}$$Pa, $$^{235}$$U and $$^{236}$$U and ($$n$$,2$$n$$) cross sections of $$^{232}$$Np and $$^{238}$$U have a large effect on generation of $$^{232}$$U. The additional investigation showed that not only time after irradiation but also time before irradiation has a strong effect on $$^{232}$$U concentration.

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Category:Nuclear Science & Technology

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