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Assessment of the $^{153}$Eu and $^{154}$Eu neutron capture cross sections from the Integral Data Assimilation of spent nuclear fuel experimentsAnnals of Nuclear Energy, 2018, 124, pp.524-532
Journal articles
cea-02339612v1
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Work plan for improving the DARWIN2.3 depleted material balance calculation of nuclides of interest for the fuel cycleInternational Conference on Nuclear Data for Science and Technology (ND - 2016), Sep 2016, Bruges, Belgium
Conference papers
cea-02438367v1
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