Search Results - "Palancher, H."
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Evolution of extended defects in polycrystalline UO2 under heavy ion irradiation: combined TEM, XRD and Raman study
Published in Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms (01-05-2016)“…A well-suited way to understand the behavior under irradiation of the UO2 nuclear fuel is to use ion implantations and further analyze the microstructure. The…”
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2
Evolution of extended defects in polycrystalline Au-irradiated UO2 using in situ TEM: Temperature and fluence effects
Published in Journal of nuclear materials (15-12-2016)“…In situ Transmission Electron Microscopy irradiations were performed on polycrystalline UO2 thin foils with 4 MeV gold ions at three different temperatures:…”
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3
Evaluation of Equivalent Cladding Reacted parameters of Cr-coated claddings oxidized in steam at 1200 °C in relation with oxygen diffusion/partitioning and post-quench ductility
Published in Journal of nuclear materials (01-05-2020)“…Cr-coated M5Framatome1 cladding materials are studied and developed within the CEA-Framatome-EDF French nuclear fuel joint program as Enhanced Accident…”
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4
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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5
Full characterization of dislocations in ion-irradiated polycrystalline UO2
Published in Journal of nuclear materials (01-10-2017)“…In order to fully characterize the dislocation loops and lines features (Burgers vectors, habit/slip planes, interstitial or vacancy type) induced by…”
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6
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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7
Laue pattern analysis for two-dimensional strain mapping in light-ion-implanted polycrystals
Published in Journal of applied crystallography (01-08-2015)“…In polycrystals implanted by light ions, a thin layer close to the surface is deformed. X‐ray microdiffraction in Laue mode is used to measure the induced…”
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Strain profiles in ion implanted ceramic polycrystals: An approach based on reciprocal-space crystal selection
Published in Applied physics letters (18-01-2016)“…The determination of the state of strain in implanted materials is a key issue in the study of their mechanical stability. Whereas this question is nowadays…”
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9
Mechanical behaviour near grain boundaries of He-implanted UO2 ceramic polycrystals
Published in Journal of nuclear materials (01-01-2017)“…For studying the micromechanical behaviour of UO2 and characterising the intergranular interaction, polycrystals are implanted with helium ions, inducing…”
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10
Quantitative crystallographic analysis of as-fabricated full size U–Mo/Al(Si) nuclear fuel plates
Published in Journal of alloys and compounds (25-06-2012)“…► New methodology for quantitative analysis of U–Mo/Al(Si) fuel plates. ► Measurement of Si-rich and oxide average layer thickness. ► Accurate study of the Si…”
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11
Crystallographic study of Si and ZrN coated U–Mo atomised particles and of their interaction with al under thermal annealing
Published in Journal of nuclear materials (01-11-2013)“…A new type of high density fuel is needed for the conversion of research and test reactors from high to lower enriched uranium. The most promising one is a…”
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12
Annealing tests of in-pile irradiated oxide coated U–Mo/Al–Si dispersed nuclear fuel
Published in Journal of nuclear materials (01-09-2014)“…U–Mo/Al based nuclear fuels have been worldwide considered as a promising high density fuel for the conversion of high flux research reactors from highly…”
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13
Multi-scale X-ray diffraction study of strains induced by He implantation in UO2 polycrystals
Published in Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms (01-05-2014)“…Mechanical behaviour of 60keV He implanted UO2 polycrystals has been analysed at a macroscopic scale using X-ray diffraction techniques (conventional θ/θ mode…”
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14
Evidence of amorphous interdiffusion layer in heavy ion irradiated U–8wt%Mo/Al interfaces
Published in Journal of nuclear materials (01-09-2013)“…U–Mo/Al based nuclear fuels are worldwide considered as the most promising high density fuel for the conversion of high flux research and test reactors from…”
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15
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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16
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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17
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 -
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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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19
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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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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