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Behavior of fission gases in nuclear fuel: XAS characterization of Kr in UO2Journal of Nuclear Materials, 2015, 466, pp.379-392. ⟨10.1016/j.jnucmat.2015.08.019⟩
Article dans une revue
hal-02530523v1
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Behavior of fission gases in nuclear fuel: XAS characterization of Kr in UO$_2$Journal of Nuclear Materials, 2015, 466, pp.379-392. ⟨10.1016/j.jnucmat.2015.08.019⟩
Article dans une revue
cea-02066509v1
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Advances in first-principles modelling of point defects in UO 2 : f electron correlations and the issue of local energy minimaJournal of Physics: Condensed Matter, 2013, 25 (33), pp.333201. ⟨10.1088/0953-8984/25/33/333201⟩
Article dans une revue
cea-02066753v1
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Nucleation and growth of intragranular defect and insoluble atom clusters in nuclear oxide fuelsNuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2011, 277, pp.98-108. ⟨10.1016/j.nimb.2011.12.031⟩
Article dans une revue
in2p3-00658341v1
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