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Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations

EPJ Web of Conferences (2013) 42
DOI: 10.1051/epjconf/20134205005
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Abstract

Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the critical keff for core configurations of MOX fuel assemblies. The present work investigates possible improvements of the C/E results by using new evaluations for Am-241, Pu-239 and Pu-240. © Owned by the authors, published by EDP Sciences, 2013.

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APA

Noguere, G., Bouland, O., Bernard, D., Leconte, P., Blaise, P., Peneliau, Y., … Lampoudis, C. (2013). Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations. In EPJ Web of Conferences (Vol. 42). https://doi.org/10.1051/epjconf/20134205005

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