EPJ Web of Conferences
Volume 42, 2013WONDER-2012 – 3rd International Workshop On Nuclear Data Evaluation for Reactor applications
|Number of page(s)||5|
|Section||Processing and Benchmarking|
|Published online||18 March 2013|
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
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 2.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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