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Journal
2015 | 60 | 3 | 571-580
Article title

Comparative analysis between measured and calculated concentrations of major actinides using destructive assay data from Ohi-2 PWR

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Languages of publication
EN
Abstracts
EN
In the paper, we assess the accuracy of the Monte Carlo continuous energy burnup code (MCB) in predicting final concentrations of major actinides in the spent nuclear fuel from commercial PWR. The Ohi-2 PWR irradiation experiment was chosen for the numerical reconstruction due to the availability of the final concentrations for eleven major actinides including five uranium isotopes (U-232, U-234, U-235, U-236, U-238) and six plutonium isotopes (Pu-236, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242). The main results were presented as a calculated-to-experimental ratio (C/E) for measured and calculated final actinide concentrations. The good agreement in the range of ±5% was obtained for 78% C/E factors (43 out of 55). The MCB modeling shows significant improvement compared with the results of previous studies conducted on the Ohi-2 experiment, which proves the reliability and accuracy of the developed methodology.
Publisher
Journal
Year
Volume
60
Issue
3
Pages
571-580
Physical description
Dates
published
1 - 9 - 2015
accepted
20 - 5 - 2015
received
24 - 9 - 2014
online
25 - 9 - 2015
References
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Document Type
Publication order reference
YADDA identifier
bwmeta1.element.-psjd-doi-10_1515_nuka-2015-0102
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