Search Results - "Iltis, X."
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1
Microstructure evolution and phase transformation of heavy-ion irradiated U–Mo/Al fuels
Published in Journal of nuclear materials (01-12-2020)“…The microstructure evolution and phase transformation of the interdiffusion layer resulting from the interaction between U–Mo and Al in U–Mo/Al bilayer systems…”
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2
Influence of intra-granular void distribution on the grain sub-structure of UO2 pellets after high temperature compression tests
Published in Journal of nuclear materials (01-03-2021)“…The aim of this work is to study the role of intra-granular voids on the macroscopic behavior and the microstructure of uranium dioxide (UO2) for different…”
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3
Influence of strain conditions on the grain sub-structuration in crept uranium dioxide pellets
Published in Journal of nuclear materials (01-05-2019)“…Stoichiometric uranium dioxide (UO2) pellets were deformed by uniaxial compression creep tests at 1500 °C. Strains comprised between 3% and 11% were applied at…”
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Journal Article -
4
Microstructure of as atomized and annealed U-Mo7 particles: A SEM/EBSD study of grain growth
Published in Journal of nuclear materials (01-11-2017)“…Significant progresses in the performances under in-pile irradiation of particular U-Mo based fuels have been observed over the last fifteen years. One of the…”
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5
Thermodynamics of chromium in UO2 fuel: A solubility model
Published in Journal of nuclear materials (01-04-2014)“…The solubility and speciation of chromium in doped uranium oxide are measured in carefully controlled temperature and oxygen potential conditions using…”
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6
Alumina coatings on silica powders by Fluidized Bed Chemical Vapor Deposition from aluminium acetylacetonate
Published in Chemical engineering journal (Lausanne, Switzerland : 1996) (15-11-2012)“…► The Fluidized Bed Chemical Vapor Deposition process has been studied to coat SiO2 powder by alumina. ► A metal organic precursor, aluminium acetylacetonate…”
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7
Microstructural evolution of uranium dioxide following compression creep tests: An EBSD and image analysis study
Published in Journal of nuclear materials (01-01-2015)“…•Image analysis and EBSD are performed on creep tested UO2 pellets.•Development of intergranular voids, with increasing strain, is quantified.•EBSD evidences a…”
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8
About molybdenum behaviour during U(Mo)/Al(Si) interaction processes
Published in Journal of nuclear materials (01-02-2013)“…U(Mo)/Al(Si) diffusion couples are studied to provide a better understanding of the interaction processes between the U(Mo) fuel and the Al(Si) matrix and,…”
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9
Microstructure of as-fabricated UMo/Al(Si) plates prepared with ground and atomized powder
Published in Journal of nuclear materials (01-07-2013)“…UMo-Al based fuel plates prepared with ground U8wt%Mo, ground U8wt%MoX (X=1wt%Pt, 1wt%Ti, 1.5wt%Nb or 3wt%Nb) and atomized U7wt%Mo have been examined. The…”
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10
Development of characterisation methods on U(Mo) powders for material testing reactors (MTRs)
Published in Powder technology (01-03-2014)“…The necessity for Material Testing Reactors (MTRs) to use a low-enriched uranium (LEU) fuel has leaded to the development of a dense fissile material based on…”
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Journal Article Conference Proceeding -
11
U–Mo/Al–Si interaction: Influence of Si concentration
Published in Journal of nuclear materials (30-04-2010)“…Within the framework of the development of low enriched nuclear fuels for research reactors, U–Mo/Al is the most promising option that has however to be…”
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12
Analysis of the interaction products in U(Mo,X)/Al and U(Mo,X)/Al(Si) diffusion couples, with X=Cr, Ti, Zr
Published in Journal of nuclear materials (01-03-2014)“…In the framework of the development of a low 235U enriched nuclear fuel for material testing reactors, γ-U(Mo)/Al based materials are considered as the most…”
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13
Study of the γ-U(Mo) phase decomposition for atomised and ground powders
Published in Progress in nuclear energy (New series) (01-08-2015)“…U(Mo) particles are obtained by centrifugal atomisation or by mechanical grinding fabrication processes and display microstructures which strongly influence…”
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14
Interdiffusion behaviors in doped molybdenum uranium and aluminum or aluminum silicon dispersion fuels: Effects of the microstructure
Published in Journal of nuclear materials (01-09-2011)“…Si addition to Al is considered as a promising route to reduce (U,Mo)–Al interaction kinetics, due to its accumulation in the interaction layer, yielding the…”
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Journal Article Conference Proceeding -
15
First evidence of metallisation circle in a Chromium doped UO2 pellet submitted to a thermal gradient
Published in Journal of nuclear materials (01-08-2024)“…In order to better understand the formation of metallic fission product precipitates at the centre of power ramped UO2 fuel, we performed a separate effects…”
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Journal Article -
16
Microstructural characterization of atomized U 3 Si 2 powders with different silicon contents (7.4-7.8 wt%)
Published in Journal of nuclear materials (01-01-2023)“…Atomization processes are used to produce uranium-based powders for the manufacturing of dispersion fuel for nuclear research reactors. Whereas this process is…”
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17
Dislocation analysis of a complex sub-grain boundary in UO2 ceramic using accurate electron channelling contrast imaging in a scanning electron microscope
Published in Ceramics international (15-10-2019)“…In this work, accurate electron channelling contrast imaging (A-ECCI) assisted by high resolution selected area channelling patterns (HR-SACP) was used to…”
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18
Microstructural characterization of atomized U3Si2 powders with different silicon contents (7.4–7.8 wt%)
Published in Journal of nuclear materials (01-01-2023)“…Atomization processes are used to produce uranium-based powders for the manufacturing of dispersion fuel for nuclear research reactors. Whereas this process is…”
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Journal Article -
19
From arc-melted ingot to MTR fuel plate: A SEM/EBSD microstructural study of U3Si2
Published in Journal of nuclear materials (15-08-2020)“…U3Si2/Al fuel plates are widely used in Material Testing Reactors (MTRs) as Low Enriched Uranium driver fuel. In this paper, a reinvestigation of the…”
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Journal Article -
20
Short communication: Spark plasma sintering as an innovative process for nuclear fuel plate manufacturing
Published in Journal of nuclear materials (01-01-2021)“…•An alternative process using spark plasma sintering is proposed to manufacture nuclear fuel plate for research reactors.•It presents significant flexibility…”
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