Search Results - "Tarisien, N."

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  1. 1

    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
  2. 2

    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
  3. 3

    In situ control of oxygen partial pressure in a buffered UO2 fuel: A manufacturing process by Khair, M., Riglet-Martial, Ch, Matheron, P., Lechelle, J., Palancher, H., Iltis, X., Tarisien, N., Heintz, J.-M.

    Published in Journal of the European Ceramic Society (01-04-2020)
    “…An innovative laboratory process making use of the specific properties of solid redox buffers was developed for producing O2 self-regulated UO2 fuel samples…”
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    Journal Article