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Crystal growth methods dedicated to low solubility actinide oxalates

 C. Tamain , B. Arab-Chapelet , M. Rivenet , S. Grandjean , F. Abraham
Journal of Solid State Chemistry, 2016, 236, pp.246 - 256. ⟨10.1016/j.jssc.2015.07.045⟩
Article dans une revue hal-01780814v1

Aspects of fabrication of curium-based fuels and targets

 S. Pillon , J. Somers , S. Grandjean , J. Lacquement
Journal of Nuclear Materials, 2003, 320, ⟨10.1016/S0022-3115(03)00168-5⟩
Article dans une revue istex cea-02360129v1
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Study of irradiated and non-irradiated MOX fuel reprocessing

 M. Bertrand , A. Salvatores , S. Grandjean , S. Lalleman , E. Buravand , et al.
TOP FUEL 2019, Sep 2019, Seattle, United States
Communication dans un congrès cea-02394092v1

Oxidation of plutonium dioxide an X-ray absorption spectroscopy study

 P. Martin , S. Grandjean , M. Ripert , M. Freyss , P. Blanc , et al.
Journal of Nuclear Materials, 2003, 320, ⟨10.1016/S0022-3115(03)00180-6⟩
Article dans une revue istex cea-02360103v1

Precipitation of Mixed ZirconiumIV CeriumIV Molybdate in Nitric Acid.

 M. Nadolny , M. Rivenet , S. Costenoble , C. Lavalette , S. Grandjean
ATALANTE 2016 - Nuclear Chemistry for Sustainable Fuel Cycles, Jun 2016, Montpellier, France
Communication dans un congrès hal-02416318v1
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La spéciation des actinides - Pierre angulaire de la chimie dans le cycle du combustible nucléaire

 P.M. Martin , Claire Le Naour , Marie-Christine Charbonnel , S. Grandjean , Nicolas Dacheux , et al.
L'Actualité Chimique, 2021, 460-461
Article dans une revue in2p3-03430378v1

Hydrothermal synthesis and crystal structures of new uranyl oxalate hydroxides: α and β-[(UO2)2(C2O4)(OH)2(H2O)2] and [(UO2)2(C2O4)(OH)2(H2O) 2]∙H2O.

 L. Duvieubourg G. Nowogrocki F. Abraham & S. Grandjean.
Journal of Solid State Chemistry, 2005, 178, pp.3437-3444
Article dans une revue hal-00105274v1

Nano Single Crystals of Yttria-Stabilized Zirconia

 C. Guiot , S. Grandjean , S. Lemonnier , Jean-Pierre Jolivet , P. Batail
Crystal Growth & Design, 2009, 9 (54), pp.3548-3550. ⟨10.1021/cg900292h⟩
Article dans une revue hal-00451085v1

Recycling the actinides, a beneficial contribution to the overall environmental sustainability of nuclear energy systems.

 S. Bourg , S. Grandjean , B. Boullis , C. Poinssot
GLOBAL 2015, Sep 2015, Paris, France
Communication dans un congrès cea-02504526v1

New Insights Into The Head-End Treatment Process Of Spent Fast Neutron Reactor Mox Fuels For Improved Plutonium Dissolution

 S. Grandjean , N. Reynier-Tronche , E. Buravand , S. Lalleman , G. Leturcq , et al.
12th International Conference on Advanced Nuclear Fuel Cycle and Related Nuclear Systems (GLOBAL - 2017), Sep 2017, Seoul, South Korea
Communication dans un congrès cea-02434545v1

Demonstration of uranium - plutonium separation and purification from spent nuclear fuel with monoamide solvent

 C. Sorel , S. Costenoble , Mj. Bollesteros , F. Antegnard , M. Montuir , et al.
International Nuclear Fuel Cycle Conference (GLOBAL 2017), Sep 2017, Seoul, South Korea
Communication dans un congrès hal-02419644v1

Study of combustion synthesis of solid solutions (U1-yAn/Lny)O2±x under air atmosphere

 G. Peter-Soldani , E. Welcomme , Xavier Deschanels , F. Abraham , S. Grandjean
Plutonium Futures - The Science 2016, Sep 2016, Baden-Baden, Germany
Communication dans un congrès hal-02441896v1
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Influence of additives on the structure and microstructure of lanthanides and actinides oxalate

 B. Haidon , A.-L. Vitart , M. Rivenet , B. Arab-Chapelet , P. Roussel , et al.
SCF 2015 - Congrès de la Société Chimique de France, Jul 2015, Lille, France
Communication dans un congrès cea-02506795v1

Influence de composes organiques sur la microstructure, la morphologie et la croissance cristalline de l'oxalate de thorium (IV), modele de l'oxalate de plutonium (IV)

 M. Rivenet , B. Haidon , Pierre Farger , Pascal Roussel , S. Grandjean , et al.
Cristal 9, 2019, Nancy, France
Communication dans un congrès cea-02394045v1
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Potentialities os simulation Tools for NRTA

 B. Dinh , S. Grandjean , A. Salvatores , P. Baron
Symposium on International Safeguards : Building Future Safeguards facilities, Nov 2018, Vienne, Austria
Communication dans un congrès cea-02338718v1

XAS study of U(1-y)PuyO2 solid solutions

 P. Martin , S. Grandjean , C. Valot , G. Carlot , M. Ripert , et al.
Journal of Alloys and Compounds, 2006
Article dans une revue cea-02356023v1
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CEA's R&D on advanced fuel treatment with multi-recycling of plutonium and uranium

 S. Grandjean , N. Reyniertronche , A. Salvatores , N. Herlet , X. Heres , et al.
GLOBAL - 2015 - 21st International Conference and Exhibition "Nuclear Fuel Cycle For a Low-Carbon Future", Sep 2015, Paris, France
Communication dans un congrès cea-02492564v1

Precipitation of lanthanides and actinides oxalates in presence of additives orientation of the microstructure.

 B. Haidon , B. Arab-Chapelet , T. Delahaye , A. Vitart , S. Grandjean , et al.
EMRS, May 2015, Lille, France
Communication dans un congrès cea-02509082v1

Modes de coordination des oxalates M2(C2O4)3(H2O)6·nH2O (avec M=Ln, An) : comparaison des séries 4f et 5f

 C. Tamain , B. Arab-Chapelet , M. Rivenet , X. F Le Goff , S. Grandjean , et al.
SCF d'avenir, Apr 2016, Bagnols Sur Ceze, France
Communication dans un congrès hal-02442244v1

French Perspective On The Respective Interests Of Hydro- And Pyro-Chemical Processes For Recycling Future Spent Nuclear Fuels

 C. Poinssot , S. Grandjean , S. Bourg , J. Serp , E. Touron , et al.
GLOBAL 2017, Sep 2017, Seoul, South Korea
Communication dans un congrès cea-02434536v1
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Lab-scale implementation of a next-generation uranium and plutonium separation and purification process from spent nuclear fuel using monoamide solvent

 S. Costenoble , M.-J. Bollesteros , F. Antegnard , C. Sorel , V. Vanel , et al.
ISEC 2017 (The 21st International Solvent Extraction Conference), Nov 2017, Miyazaki, Japan
Communication dans un congrès cea-02434002v1
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Improving Actinides Recycling, a Key Step towards a More Sustainable Nuclear Energy

 C. Poinssot , S. Grandjean , M. Masson , B. Boullis
Waste Management 2015, Mar 2015, Phoenix, United States
Communication dans un congrès cea-02489506v1
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First assessment of a digestion method applied to recover plutonium from refractory residues after dissolving spent SFR MOX fuel in nitric acid

 E. Buravand , N. Reyniertronche , B. Catanese , P. Huot , E. Esbelin , et al.
FR17 - Fast reactors and related fuel cycles Next Generation Nuclear Systems for Sustainable Development, Jun 2017, Yetaterinburg, Russia
Communication dans un congrès cea-02438381v1
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Calcined Resin Microsphere Pelletization (CRMP) a novel process for sintered metallic oxide pellets synthesis.

 E. Remy , S. Picart , S. Grandjean , T. Delahaye , N. Herlet , et al.
Journal of the European Ceramic Society, 2012, 32 (12), pp.3199-3209. ⟨10.1016/j.jeurceramsoc.2012.04.011⟩
Article dans une revue cea-02349240v1

Neutron fluctuations: The importance of being delayed

 C. Tamain , B. Arab-Chapelet , M. Rivenet , S. Grandjean , F. Abraham , et al.
Physical Review E : Statistical, Nonlinear, and Soft Matter Physics, 2015, 92 (5), pp.246-256. ⟨10.1103/PhysRevE.92.052114⟩
Article dans une revue hal-02446897v1

Structural diversity of the lanthanide oxalates: Condensation of neodymium oxygen polyhedra under hydrothermal conditions

 A. Mer , M. Rivenet , L. de Almeida , S. Grandjean , F. Abraham
Inorganic Chemistry Communications, 2013, 31, pp.90 - 95. ⟨10.1016/j.inoche.2013.02.014⟩
Article dans une revue hal-01780829v1

Synthesis and characterization of mixed An(IV)An(III) oxalates (An(IV) = Th, Np, U or Pu and An(III) = Pu or Am)

 B. Arab-Chapelet , S. Grandjean , G. Nowogrocki , F. Abraham
Journal of Nuclear Materials, 2008, 373 (1-3), pp.259-268. ⟨10.1016/j.jnucmat.2007.06.004⟩
Article dans une revue cea-02355753v1

Development of process monitoring tools for the uranium-plutonium separation and purification from spent nuclear fuel by liquid-liquid extraction

 S. Costenoble , S. Broussard , J. Sinot , V. Vanel , C. Sorel , et al.
RANC 2019, May 2019, Budapest, Hungary
Communication dans un congrès hal-02411085v1
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First assessment of a digestion method applied to recovery of plutonium from refractory residues after dissolving spent sfr mox fuel in nitric acid

 E. Buravand , N. Reynier-Tronche , B. Catanese , P. Huot , E. Esbelin , et al.
International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Jun 2017, Yekaterinburg, Russia
Communication dans un congrès hal-02419693v1

Coordination Modes of Americium in the Am2(C2O4)3(H2O)6·4H2O Oxalate: Synthesis, Crystal Structure, Spectroscopic Characterizations and Comparison in the M2(C2O4)3(H2O)6·nH2O (M = Ln, An) Series

 C. Tamain , B. Arab-Chapelet , B. Rivenet , X. F Le Goff , G. Loubert , et al.
Inorganic Chemistry, 2016, 55 (1), pp.51-61. ⟨10.1021/acs.inorgchem.5b01781⟩
Article dans une revue hal-01998374v1
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