Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations
1 CEA, DEN, Cadarache, F-13108 Saint Paul Les Durance, France
2 Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN, USA, 37831
3 JRC-EC IRMM, Retiseweg, 2440 Geel, Belgium
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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