학술논문
Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations.
Document Type
Article
Author
Source
Subject
*FUEL
*DATA libraries
*NEUTRONS
*MONTE Carlo method
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*
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Language
ISSN
2101-6275
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. [ABSTRACT FROM AUTHOR]