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

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

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.

Bibliographic Details
Main Authors: Schillebeeckx P., Leal L., De Saint Jean C., Vidal J.F., Peneliau Y., Blaise P., Leconte P., Bernard D., Bouland O., Noguere G., Kopecky S., Lampoudis C.
Format: Article
Language:English
Published: EDP Sciences 2013-03-01
Series:EPJ Web of Conferences
Online Access:http://dx.doi.org/10.1051/epjconf/20134205005

Internet

http://dx.doi.org/10.1051/epjconf/20134205005

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