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Report No.
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Evaluation of prediction accuracy of iodine-129 inventory in spent fuel of light water reactor

Okumura, Keisuke ; Okamoto, Tsutomu; Kojima, Kensuke; Hagura, Hiroyuki; Suyama, Kenya

In order to confirm the prediction accuracy of I-129 inventory in the nuclear spent fuels of light water reactors, the post irradiation examination analysis was performed for the fuel samples irradiated in a Japanese PWR (Mihama-3) and for the samples irradiated in a foreign PWR, by using recent nuclear data libraries such as JENDL-4.0 and the lattice burnup calculation module of the MOSRA system. As a result, it was found that the fission yield data of JENDL-4.0 and ENDF/B-VII.0 give underestimation of the I-129 inventory by about 20% compared with the assay data. On the other hand, the fission yield data of JNDC/V-2 and JEFF-3.1 give better results although they still give underestiomation (about 7%). Then, we made a simple evaluation formula to predict the I-129 inventory from the assay data.

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