Search Results - "Palancher, H."

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  1. 1

    Evolution of extended defects in polycrystalline UO2 under heavy ion irradiation: combined TEM, XRD and Raman study by Onofri, C., Sabathier, C., Palancher, H., Carlot, G., Miro, S., Serruys, Y., Desgranges, L., Legros, M.

    “…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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    Journal Article
  2. 2

    Evolution of extended defects in polycrystalline Au-irradiated UO2 using in situ TEM: Temperature and fluence effects by Onofri, C., Sabathier, C., Baumier, C., Bachelet, C., Palancher, H., Legros, M.

    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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    Journal Article
  3. 3
  4. 4

    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
  5. 5

    Full characterization of dislocations in ion-irradiated polycrystalline UO2 by Onofri, C., Legros, M., Léchelle, J., Palancher, H., Baumier, C., Bachelet, C., Sabathier, C.

    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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    Journal Article
  6. 6

    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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  7. 7

    Laue pattern analysis for two-dimensional strain mapping in light-ion-implanted polycrystals by Ibrahim, M., Castelier, É., Palancher, H., Bornert, M., Caré, S., Micha, J.-S.

    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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    Journal Article
  8. 8

    Strain profiles in ion implanted ceramic polycrystals: An approach based on reciprocal-space crystal selection by Palancher, H., Goudeau, P., Boulle, A., Rieutord, F., Favre-Nicolin, V., Blanc, N., Martin, G., Fouet, J., Onofri, C.

    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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    Journal Article
  9. 9

    Mechanical behaviour near grain boundaries of He-implanted UO2 ceramic polycrystals by Ibrahim, M., Castelier, É., Palancher, H., Bornert, M., Caré, S., Micha, J.-S.

    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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    Journal Article
  10. 10

    Quantitative crystallographic analysis of as-fabricated full size U–Mo/Al(Si) nuclear fuel plates by Palancher, H., Bonnin, A., Honkimäki, V., Buslaps, T., Grasse, M., Stepnik, B., Zweifel, T.

    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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    Journal Article
  11. 11

    Crystallographic study of Si and ZrN coated U–Mo atomised particles and of their interaction with al under thermal annealing by Zweifel, T., Palancher, H., Leenaers, A., Bonnin, A., Honkimaki, V., Tucoulou, R., Van Den Berghe, S., Jungwirth, R., Charollais, F., Petry, W.

    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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    Journal Article
  12. 12

    Annealing tests of in-pile irradiated oxide coated U–Mo/Al–Si dispersed nuclear fuel by Zweifel, T., Valot, Ch, Pontillon, Y., Lamontagne, J., Vermersch, A., Barrallier, L., Blay, T., Petry, W., Palancher, H.

    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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    Journal Article
  13. 13

    Multi-scale X-ray diffraction study of strains induced by He implantation in UO2 polycrystals by Richard, A., Castelier, E., Palancher, H., Micha, J.S., Rouquette, H., Ambard, A., Garcia, Ph, Goudeau, Ph

    “…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. 14

    Evidence of amorphous interdiffusion layer in heavy ion irradiated U–8wt%Mo/Al interfaces by Chiang, H-Y., Zweifel, T., Palancher, H., Bonnin, A., Beck, L., Weiser, P., Döblinger, M., Sabathier, C., Jungwirth, R., Petry, W.

    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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    Journal Article
  15. 15

    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
  16. 16

    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
  17. 17

    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
  18. 18

    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
  19. 19

    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
  20. 20

    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