Search Results - "Iltis, X."

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  1. 1

    Microstructure evolution and phase transformation of heavy-ion irradiated U–Mo/Al fuels by Shi, J., Onofri, C., Palancher, H., Iltis, X., Drouan, D., Breitkreutz, H., Petry, W.

    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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    Journal Article
  2. 2

    Influence of intra-granular void distribution on the grain sub-structure of UO2 pellets after high temperature compression tests by Saada, M. Ben, Iltis, X., Gey, N., Miard, A., Garcia, P., Maloufi, N.

    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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    Journal Article
  3. 3

    Influence of strain conditions on the grain sub-structuration in crept uranium dioxide pellets by Ben Saada, M., Iltis, X., Gey, N., Beausir, B., Miard, A., Garcia, P., Maloufi, N.

    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. 4

    Microstructure of as atomized and annealed U-Mo7 particles: A SEM/EBSD study of grain growth by Iltis, X., Zacharie-Aubrun, I., Ryu, H.J., Park, J.M., Leenaers, A., Yacout, A.M., Keiser, D.D., Vanni, F., Stepnik, B., Blay, T., Tarisien, N., Tanguy, C., Palancher, H.

    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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    Journal Article
  5. 5

    Thermodynamics of chromium in UO2 fuel: A solubility model by Riglet-Martial, Ch, Martin, Ph, Testemale, D., Sabathier-Devals, C., Carlot, G., Matheron, P., Iltis, X., Pasquet, U., Valot, C., Delafoy, C., Largenton, R.

    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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    Journal Article
  6. 6

    Alumina coatings on silica powders by Fluidized Bed Chemical Vapor Deposition from aluminium acetylacetonate by Rodriguez, Ph, Caussat, B., Iltis, X., Ablitzer, C., Brothier, M.

    “…► 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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    Journal Article
  7. 7

    Microstructural evolution of uranium dioxide following compression creep tests: An EBSD and image analysis study by Iltis, X., Gey, N., Cagna, C., Hazotte, A., Sornay, Ph

    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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    Journal Article
  8. 8

    About molybdenum behaviour during U(Mo)/Al(Si) interaction processes by Iltis, X., Allenou, J., Verhaeghe, B., Palancher, H., Tougait, O., Bonnin, A., Tucoulou, R.

    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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    Journal Article
  9. 9

    Microstructure of as-fabricated UMo/Al(Si) plates prepared with ground and atomized powder by Jungwirth, R., Palancher, H., Bonnin, A., Bertrand-Drira, C., Borca, C., Honkimäki, V., Jarousse, C., Stepnik, B., Park, S.-H., Iltis, X., Schmahl, W.W., Petry, W.

    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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    Journal Article
  10. 10

    Development of characterisation methods on U(Mo) powders for material testing reactors (MTRs) by Champion, G., Belin, R., Palancher, H., Iltis, X., Rouquette, H., Pasturel, M., Demange, V., Castany, P., Dorcet, V., Tougait, O.

    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. 11

    U–Mo/Al–Si interaction: Influence of Si concentration by Allenou, J., Palancher, H., Iltis, X., Cornen, M., Tougait, O., Tucoulou, R., Welcomme, E., Martin, Ph, Valot, C., Charollais, F., Anselmet, M.C., Lemoine, P.

    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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    Journal Article
  12. 12

    Analysis of the interaction products in U(Mo,X)/Al and U(Mo,X)/Al(Si) diffusion couples, with X=Cr, Ti, Zr by Allenou, J., Palancher, H., Iltis, X., Tougait, O., El Bekkachi, H., Bonnin, A., Tucoulou, R.

    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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    Journal Article
  13. 13

    Study of the γ-U(Mo) phase decomposition for atomised and ground powders by Champion, G., Iltis, X., Tougait, O., Pasturel, M., Belin, R., Palancher, H., Richaud, J.-C.

    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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    Journal Article
  14. 14

    Interdiffusion behaviors in doped molybdenum uranium and aluminum or aluminum silicon dispersion fuels: Effects of the microstructure by Allenou, J., Tougait, O., Pasturel, M., Iltis, X., Charollais, F., Anselmet, M.C., Lemoine, P.

    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. 15

    First evidence of metallisation circle in a Chromium doped UO2 pellet submitted to a thermal gradient by Devillaire, A., Le Berre, L., Desgranges, L., Martin, F., Charmasson, P., Colin, C., Tarisien, N., Iltis, X., Hanifi, K., Canizares, A.

    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. 16

    Microstructural characterization of atomized U 3 Si 2 powders with different silicon contents (7.4-7.8 wt%) by Iltis, X., Havette, J., Klosek, V., Onofri, C., Lee, K.H., Kim, J.H., Jeong, Y.J., Pasturel, M., Palancher, H.

    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
  17. 17

    Dislocation analysis of a complex sub-grain boundary in UO2 ceramic using accurate electron channelling contrast imaging in a scanning electron microscope by Mansour, H., Crimp, M.A., Gey, N., Iltis, X., Maloufi, N.

    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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    Journal Article
  18. 18

    Microstructural characterization of atomized U3Si2 powders with different silicon contents (7.4–7.8 wt%) by Iltis, X., Havette, J., Klosek, V., Onofri, C., Lee, K.H., Kim, J.H., Jeong, Y.J., Pasturel, M., Palancher, H.

    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. 19

    From arc-melted ingot to MTR fuel plate: A SEM/EBSD microstructural study of U3Si2 by Havette, Julien, Iltis, Xavière, Palancher, Hervé, Drouan, Doris, Fiquet, Olivier, Castelier, Etienne, Pasturel, Mathieu

    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. 20

    Short communication: Spark plasma sintering as an innovative process for nuclear fuel plate manufacturing by Havette, Julien, Iltis, Xavière, Palancher, Hervé, Fiquet, Olivier, Pasturel, Mathieu

    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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    Journal Article