New measurement of the 242Pu(n,γ) cross section at n_TOF

The use of MOX fuel (mixed-oxide fuel made of UO2 and PuO2) in nuclear reactors allows substituting a large fraction of the enriched Uranium by Plutonium reprocessed from spent fuel. With the use of such new fuel composition rich in Pu, a better knowledge of the capture and fission cross sections of...

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Bibliographic Details
Main Authors: Lerendegui-Marco J., Guerrero C., Cortés-Giraldo M. A., Quesada J. M., Mendoza E., Cano-Ott D., Eberhardt K., Junghans A.
Format: Article
Language:English
Published: EDP Sciences 2016-01-01
Series:EPJ Web of Conferences
Online Access:http://dx.doi.org/10.1051/epjconf/201611102005

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