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Report No.
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Impact of the uncertainty of the PIE analysis on the criticality analysis

Tada, Kenichi; Suyama, Kenya

To investigate the applicability of the burnup calculation code SWAT4.0, we calculated the post irradiation examination which is 8$$times$$8 BWR fuel assembly and loaded in Fukushima Daini Nuclear Power Plant unit 2. In this study, we investigate the impact of the difference of the number density of nuclide on the criticality analysis for the fuel debris. The calculation was carried out by the infinite pin-cell geometry and calculation results indicates that the impact of the difference of the number density of nuclide on the k-effective is less than 3%$$Delta$$k/k. Since we adopt the upper subcriticality limit of 0.95 in usual criticality safety evaluation, this result indicates that SWAT4.0 has adequate prediction accuracy of the isotopic composition to be adopted in the burnup credit analysis of the fuel debris from the Fukushima Daiichi Nuclear Power Plant.

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