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Report No.
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Nuclear data for prediction of isotope generation and depletion

Okumura, Keisuke 

First, calculation schemes of nuclide generation and depletion are briefly shown by taking up three different burn-up calculation codes, MVP-BURN, MOSRA-SRAC and ORIGEN2. Then, as examples of validation of burn-up calculations with these codes and JENDL-4.0, we show results of post irradiation examination analyses for LWR spent fuel compositions. At last, recent progress is introduced on inventory prediction of $$^{79}$$Se in LWR spent fuels, which is very important for long-term safety assessment of a geological disposal of the vitrified wastes.

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