<abstract xmlns="http://www.w3.org/1999/xhtml"><p> 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.</p></abstract>

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.

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

Department of Nuclear Energy, Faculty of Energy and Fuels, AGH University of Science and Technology, 30 Mickiewicza Ave., 30-059 Krakow, Poland, Tel.: +48 12 617 5186, Fax: +48 12 617 4547

Nukleonika

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

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...

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

Published Online: Sep 25, 2015

Page range: 571 - 580

Received: Sep 24, 2014

Accepted: May 20, 2015

DOI: https://doi.org/10.1515/nuka-2015-0102

Keywords
comparative analysis · major actinides · MCB · Monte Carlo · pressurized water reactor (PWR)

© by Mikołaj Oettingen

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

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

Published Online: Sep 25, 2015

Page range: 571 - 580

Received: Sep 24, 2014

Accepted: May 20, 2015

DOI: https://doi.org/10.1515/nuka-2015-0102

Keywordscomparative analysis · major actinides · MCB · Monte Carlo · pressurized water reactor (PWR)

© by Mikołaj Oettingen

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

Keywords
comparative analysis · major actinides · MCB · Monte Carlo · pressurized water reactor (PWR)