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All issues EPJ Nuclear Sci. Technol., 3 (2017) 13 Article references

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Dissolution of (U,Th)O2 heterogeneous mixed oxides

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DOI: 10.1016/j.jnucmat.2023.154658
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Analysing the impact of autocatalysis on the dissolution kinetics of uranium and plutonium mixed oxide powders by optical microscopy

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DOI: 10.1016/j.hydromet.2022.106010
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Influence of Sintering Conditions on the Structure and Redox Speciation of Homogeneous (U,Ce)O2+δ Ceramics: A Synchrotron Study

Malvina Massonnet, Laurent Claparede, Julien Martinez, et al.
Inorganic Chemistry 62 (19) 7173 (2023)
DOI: 10.1021/acs.inorgchem.2c03945
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Mechanochemical activation and oxidation of U(iv)O2

Dmytro V. Kravchuk and Tori Z. Forbes
Chemical Communications 58 (28) 4528 (2022)
DOI: 10.1039/D2CC00242F
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Impact of ruthenium metallic particles on the dissolution of UO2 in nitric acid

Thibault Kaczmarek, Stéphanie Szenknect, Laurent Claparède, et al.
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DOI: 10.1038/s41529-022-00246-0
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Recovery and separation of uranium in a microbial fuel cell using a titanium dioxide nanotube array cathode

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Environmental Science: Nano 8 (8) 2214 (2021)
DOI: 10.1039/D1EN00270H
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Influence of the concentration of nitric acid on the composition of NOX gas evolved during the dissolution of nuclear fuel and its implications on the PUREX process

N. Desigan, N.K. Pandey and J.B. Joshi
Progress in Nuclear Energy 135 103704 (2021)
DOI: 10.1016/j.pnucene.2021.103704
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Dissolution of Th0.25U0.75O2 sintered pellets: Impact of nitrate ions and nitrous acid

Thomas Dalger, Laurent Claparede, Stéphanie Szenknect, Philippe Moisy and Nicolas Dacheux
Hydrometallurgy 204 105717 (2021)
DOI: 10.1016/j.hydromet.2021.105717
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Dissolution behavior of fast reactor MOX nuclear fuel pellets in nitric acid medium

N. Desigan, S. Ganesh and N.K. Pandey
Journal of Nuclear Materials 554 153077 (2021)
DOI: 10.1016/j.jnucmat.2021.153077
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Dissolution behavior of irradiated fuels in nitric acid and characteristics of insoluble residue

F. Liu, T. H. Yan, B. Li and G. A. Ye
Journal of Radioanalytical and Nuclear Chemistry 326 (1) 337 (2020)
DOI: 10.1007/s10967-020-07350-y
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Two-person game model of long-term safeguards for a final repository for spent nuclear fuel

Heejae Ju, Il-Soon Hwang and Sungyeol Choi
Progress in Nuclear Energy 118 103058 (2020)
DOI: 10.1016/j.pnucene.2019.103058
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NOx speciation from copper dissolution in nitric acid/water solutions using FTIR spectroscopy

Jacquelyn M. Dorhout, Aaron S. Anderson, Enrique Batista, et al.
Journal of Molecular Spectroscopy 372 111334 (2020)
DOI: 10.1016/j.jms.2020.111334
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Effect of surface orientation on dissolution rate and surface dynamics of UO2 single crystals in nitric acid

Solène Bertolotto, Stéphanie Szenknect, Sophie Lalleman, et al.
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DOI: 10.1016/j.corsci.2020.109020
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Mechanistic Study of the Production of NOx Gases from the Reaction of Copper with Nitric Acid

Rebecca K. Carlson, Ping Yang, Samuel M. Clegg and Enrique R. Batista
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DOI: 10.1021/acs.inorgchem.0c00607
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Dissolution behaviour of simulated MOX nuclear fuel pellets in nitric acid medium

N. Desigan, Dasarath Maji, K. Ananthasivan, et al.
Progress in Nuclear Energy 116 1 (2019)
DOI: 10.1016/j.pnucene.2019.03.027
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Microstructural evolution of UO2 pellets containing metallic particles of Ru, Rh and Pd during dissolution in nitric acid solution: 3D-ESEM monitoring

T. Cordara, S. Szenknect, R. Podor, et al.
Hydrometallurgy 188 182 (2019)
DOI: 10.1016/j.hydromet.2019.07.001
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A method for phenomenological and chemical kinetics study of autocatalytic reactive dissolution by optical microscopy. The case of uranium dioxide dissolution in nitric acid media

Philippe Marc, Alastair Magnaldo, Jérémy Godard and Éric Schaer
EPJ Nuclear Sciences & Technologies 4 2 (2018)
DOI: 10.1051/epjn/2017026
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Kinetics of dissolution of Th0.25U0.75O2 sintered pellets in various acidic conditions

Thomas Dalger, Stéphanie Szenknect, Florent Tocino, et al.
Journal of Nuclear Materials 510 109 (2018)
DOI: 10.1016/j.jnucmat.2018.07.050
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Kinetics of dissolution of UO 2 in nitric acid solutions: A multiparametric study of the non-catalysed reaction

T. Cordara, S. Szenknect, L. Claparede, et al.
Journal of Nuclear Materials 496 251 (2017)
DOI: 10.1016/j.jnucmat.2017.09.038
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