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mischoxid (9) 9
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Journal of Applied Crystallography, ISSN 1600-5767, 12/2017, Volume 50, Issue 6, pp. 1782 - 1790
Plutonium–americium mixed oxides, Pu1−yAmyO2−x, with various Am contents (y= 0.018, 0.077, 0.21, 0.49, 0.80 and 1.00) were studiedin situby high-temperature... 
Journal Article
Ceramics International, ISSN 0272-8842, 08/2014, Volume 40, Issue 7, pp. 10991 - 10999
The ternary thermodynamic U–Pu–O system has been studied for decades for MOX fuel applications but the phase diagram is still not precisely described mostly in... 
Nuclear fuel | Uranium–plutonium mixed oxide | A. Sintering | Ceramic processing | Uranium-plutonium mixed oxide | Material chemistry | Chemical Sciences
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 02/2018, Volume 499, p. 88
In this study, Raman spectroscopy technique was implemented to characterize un-irradiated MIMAS (MIcronized-MASter blend) MOX fuel samples with average 7 wt.%... 
Stoichiometry | Electron microprobe | Spatial discrimination | Radiation | Irradiated | Spectroscopic analysis | Mimas | Fabrication | Oxidation resistance | Uranium | Phases | Agglomerates | Oxidation | Uranium dioxide | Spectroscopy | Annealing | Damage assessment | Raman spectroscopy | Nuclear fuels | MOX | Electron probe analysis | Plutonium | Deviation | Spatial resolution | Radiation damage | Impact damage
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 06/2015, Volume 465, pp. 349 - 357
Abstract In the present work, TGA, XAS and XRD were used to evidence the spontaneous oxidation of biphasic U 1-y Pu y O 2-x samples, with y = 0.28 and 0.45, at... 
Uranium-plutonium mixed oxide | Hypostoichiometry | MOX | Nuclear fuel | XAS | XRD | TGA
Journal Article
Journal of the European Ceramic Society, ISSN 0955-2219, 09/2014, Volume 34, Issue 10, pp. 2543 - 2551
Journal Article
Ceramics International, ISSN 0272-8842, 08/2014, Volume 40, Issue 7, p. 10991
The ternary thermodynamic U-Pu-O system has been studied for decades for MOX fuel applications but the phase diagram is still not precisely described mostly in... 
Thermodynamics | Uranium | Uranium industry | Sintering | Oxides | Metal powders | Plutonium | Metal powder products | Electric properties | Nuclear facilities
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 12/2015, Volume 467, p. 886
Atomic transport properties in uranium-plutonium mixed oxides U.sub.1-yPu.sub.yO.sub.2 are of essential concern because they impact numerous aspects of their... 
Oxides | Annealing | Uranium | Plutonium | Tracers (Biology) | Mass spectrometry | Nuclear industry | Nuclear energy
Journal Article
Inorganic Chemistry, ISSN 0020-1669, 07/2017, Volume 56, Issue 13, pp. 7416 - 7432
In the frame of minor actinide transmutation, americium can be diluted in UO2 and (U, Pu)­O2 fuels burned in fast neutron reactors. The first mandatory step to... 
REFINEMENT | ENTHALPY | THERMAL-EXPANSION | KINETICS | X-RAY-DIFFRACTION | FABRICATION | AMERICIUM OXIDES | OXYGEN SYSTEM | PLUTONIUM MIXED OXIDES | DIAGRAM | CHEMISTRY, INORGANIC & NUCLEAR
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 10/2015, Volume 465, p. 349
In the present work, TGA, XAS and XRD were used to evidence the spontaneous oxidation of biphasic U.sub.1-yPu.sub.yO.sub.2-x samples, with y = 0.28 and 0.45,... 
Uranium | Oxides | Oxidation-reduction reaction | Chemical properties | Plutonium
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 02/2018, Volume 499, pp. 88 - 97
In this study, Raman spectroscopy technique was implemented to characterize un-irradiated MIMAS (MIcronized - MASter blend) MOX fuel samples with average... 
Oxidation | Raman spectroscopy | Uranium-plutonium mixed oxides | Radiation damage | PLUTONIUM DIOXIDE | AIR-OXIDATION | MATERIALS SCIENCE, MULTIDISCIPLINARY | URANIUM-DIOXIDE | SELF-RADIATION DAMAGE | TEMPERATURES | NUCLEAR SCIENCE & TECHNOLOGY | X-RAY | NUCLEAR-MATERIALS | UO2 | OXIDES | SPECTROMETRY | Oxides | Annealing | Uranium | Analysis | Radiation
Journal Article
Inorganic Chemistry, ISSN 0020-1669, 03/2016, Volume 55, Issue 5, pp. 2123 - 2132
Innovative americium-bearing uranium–plutonium mixed oxides U1–y Pu y O2–x are envisioned as nuclear fuel for sodium-cooled fast neutron reactors (SFRs). The... 
TRANSMUTATION | CHARGE-DISTRIBUTION | SOLID-SOLUTIONS | X-RAY-DIFFRACTION | FABRICATION | THERMAL-CONDUCTIVITY | LOCAL-STRUCTURE | NUCLEAR-FUELS | CHEMISTRY, INORGANIC & NUCLEAR
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 12/2015, Volume 467, pp. 886 - 893
Atomic transport properties in uranium–plutonium mixed oxides U Pu O are of essential concern because they impact numerous aspects of their physicochemical... 
Point defects | Actinides | Isotopic exchange | MOX | Oxygen self-diffusion | Nuclear fuel | SIMS | Uranium–plutonium mixed oxide | Atomic transport | Uranium-plutonium mixed oxide | OXIDATION | SYSTEM | POINT-DEFECT CHEMISTRY | MATERIALS SCIENCE, MULTIDISCIPLINARY | DIOXIDE | X-RAY-DIFFRACTION | NUCLEAR-FUELS | NUCLEAR SCIENCE & TECHNOLOGY | MINING & MINERAL PROCESSING | UO2 | EXCHANGE
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 01/2015, Volume 456, pp. 115 - 119
The impact of the cation distribution homogeneity of the U Pu Am O mixed oxide on the americium oxidation state was studied by coupling X-ray diffraction... 
Material chemistry | Chemical Sciences
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 10/2015, Volume 465, pp. 349 - 357
In the present work, TGA, XAS and XRD were used to evidence the spontaneous oxidation of biphasic U Pu O samples, with y = 0.28 and 0.45, at room temperature... 
Hypostoichiometry | MOX | Nuclear fuel | Uranium–plutonium mixed oxide | XAS | XRD | TGA | RAY-ABSORPTION SPECTROSCOPY | MATERIALS SCIENCE, MULTIDISCIPLINARY | DIOXIDE | THERMAL-CONDUCTIVITY | TERNARY-SYSTEM | NUCLEAR-FUELS | Uranium-plutonium mixed oxide | REFINEMENT | SOLID-SOLUTION | UO2-PUO2-PU2O3 | NUCLEAR SCIENCE & TECHNOLOGY | MINING & MINERAL PROCESSING | DIFFRACTION
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 01/2015, Volume 456, pp. 115 - 119
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 01/2015, Volume 456, pp. 115 - 119
The impact of the cation distribution homogeneity of the U sub(0.54)Pu sub(0.45)Am sub(0.01)O sub(2-x) mixed oxide on the americium oxidation state was studied... 
Heterogeneity | Valence | X-rays | Homogeneity | X-ray diffraction | Nuclear engineering | Cations | Americium | Mixed oxides
Journal Article
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