Search Results - "Ribis, J"

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  1. 1

    Interfacial strained structure and orientation relationships of the nanosized oxide particles deduced from elasticity-driven morphology in oxide dispersion strengthened materials by Ribis, J., de Carlan, Y.

    Published in Acta materialia (2012)
    “…Fe–Cr–Ti–Y 2O 3 oxide dispersion strengthened materials have a high density of nano-oxides (Y, Ti, O) that are stable at high temperature. In this work based…”
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    Journal Article
  2. 2

    Structural and chemical matrix evolution following neutron irradiation in a MA957 oxide dispersion strengthened material by Ribis, J.

    Published in Journal of nuclear materials (01-03-2013)
    “…The MA957 alloy has been irradiated in the french Phenix reactor at 412°C up to 50dpa and at 430°C up to 75dpa. For both irradiation conditions, the evolution…”
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    Journal Article
  3. 3

    Nano-cluster stability following neutron irradiation in MA957 oxide dispersion strengthened material by Ribis, J., Lozano-Perez, S.

    Published in Journal of nuclear materials (01-01-2014)
    “…ODS steels are promising materials for Sodium cooled Fast Reactors since their fine distribution of nano-clusters confers excellent mechanical properties…”
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    Journal Article
  4. 4

    Shape, orientation relationships and interface structure of beta-Nb nano-particles in neutron irradiated zirconium alloy by Ribis, J., Doriot, S., Onimus, F.

    Published in Journal of nuclear materials (01-12-2018)
    “…Under neutron irradiation, radiation enhanced beta-Nb nano-precipitates develop within the α-grains of the Zr-Nb alloys. This radiation enhanced precipitation…”
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    Journal Article
  5. 5

    Interface roughening in irradiated oxide dispersion strengthened steels by Ribis, J., Leprêtre, F.

    Published in Applied physics letters (25-12-2017)
    “…Oxide Dispersion Strengthened steels are considered as promising candidates for nuclear applications as cladding tubes for GEN IV reactors. These materials are…”
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    Journal Article
  6. 6

    HRTEM and chemical study of an ion-irradiated chromium/zircaloy-4 interface by Wu, A., Ribis, J., Brachet, J.-C., Clouet, E., Leprêtre, F., Bordas, E., Arnal, B.

    Published in Journal of nuclear materials (01-06-2018)
    “…Chromium-coated zirconium alloys are being studied as Enhanced Accident Tolerant Fuel Cladding for Light Water Reactors (LWRs). Those materials are especially…”
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    Journal Article
  7. 7

    Radiation-induced Ostwald ripening in oxide dispersion strengthened ferritic steels irradiated at high ion dose by Lescoat, M.-L., Ribis, J., Chen, Y., Marquis, E.A., Bordas, E., Trocellier, P., Serruys, Y., Gentils, A., Kaïtasov, O., de Carlan, Y., Legris, A.

    Published in Acta materialia (01-10-2014)
    “…Oxide dispersion strengthened (ODS) ferritic steels are considered promising candidates as cladding tubes for Generation IV nuclear reactors. In such reactors,…”
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    Journal Article
  8. 8

    Atomic-scale interface structure of a Cr-coated Zircaloy-4 material by Ribis, J., Wu, A., Brachet, J.-C., Barcelo, F., Arnal, B.

    Published in Journal of materials science (01-07-2018)
    “…Highly adherent, thin Cr coatings on Zr-based nuclear fuel claddings can be potentially used for the development of accident-tolerant fuels in light water…”
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    Journal Article
  9. 9

    Orientation relationships and interface structure of α′-Cr nanoclusters embedded in α-Fe matrix after α–α′ demixing in neutron irradiated Oxide Dispersion Strengthened material by Ribis, J., Lozano-Perez, S.

    Published in Materials letters (01-05-2012)
    “…A nanoscale characterization of neutron irradiated Oxide Dispersion Strengthened (ODS) alloys has been used to reveal the α–α′ demixing and the population of…”
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    Journal Article
  10. 10

    Influence of plastic deformation on the precipitation sequence in an AA6061 alloy by Chbihi, A., Vincent, S., Ribis, J., Toffolon-Masclet, C., Garnier, J.

    Published in Journal of materials science (01-05-2017)
    “…The purpose of this work is to study the effect of prior plastic deformation on the precipitation mechanisms of Mg x Si y in an AA6061 alloy. Differential…”
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    Journal Article
  11. 11

    In situ TEM study of the stability of nano-oxides in ODS steels under ion-irradiation by Lescoat, M-L., Ribis, J., Gentils, A., Kaïtasov, O., de Carlan, Y., Legris, A.

    Published in Journal of nuclear materials (01-09-2012)
    “…Oxide Dispersion Strengthened (ODS) ferritic–martensitic steels are considered for nuclear applications as structural components for fusion or fission…”
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    Journal Article Conference Proceeding
  12. 12

    Study of the thermal stability of nanoparticle distributions in an oxide dispersion strengthened (ODS) ferritic alloys by Zhong, S.Y., Ribis, J., Klosek, V., de Carlan, Y., Lochet, N., Ji, V., Mathon, M.H.

    Published in Journal of nuclear materials (01-09-2012)
    “…Oxide dispersion strengthened (ODS) ferritic alloys have a vast applicability due to their excellent mechanical resistance at high temperature. The precipitate…”
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    Journal Article Conference Proceeding
  13. 13

    Relaxation path of metastable nanoclusters in oxide dispersion strengthened materials by Ribis, J., Thual, M.A., Guilbert, T., de Carlan, Y., Legris, A.

    Published in Journal of nuclear materials (01-02-2017)
    “…ODS steels are a promising class of structural materials for sodium cooled fast reactor application. The ultra-high density of the strengthening nanoclusters…”
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    Journal Article
  14. 14

    Characterization of ion irradiated microstructure and cavity swelling evolution up to high doses in austenitic stainless steels representative of PWR internals by Malaplate, J., Michaut, B., Renault-Laborne, A., Jourdan, T., Dalle, F., Ribis, J., Radiguet, B., Sefta, F., Décamps, B.

    Published in Journal of nuclear materials (15-04-2019)
    “…Ion irradiations have been performed at 450 °C on 304 and 304L austenitic stainless steels representative of PWR internals structure up to high doses (close to…”
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    Journal Article
  15. 15

    Relaxation path of nanoparticles in an oxygen-enriched ferritic oxide-dispersion-strengthened alloy by Thual, M.A., Ribis, J., Baudin, T., Klosek, V., de Carlan, Y., Mathon, M.H.

    Published in Scripta materialia (15-07-2017)
    “…Excellent mechanical properties of oxide-dispersion-strengthened (ODS) alloys arise from a high density of Y-Ti nano-oxides finely dispersed in the matrix…”
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    Journal Article
  16. 16

    Radiation-sustained nanocluster metastability in oxide dispersion strengthened materials by Ribis, J., Bordas, E., Trocellier, P., Serruys, Y., de Carlan, Y., Legris, A.

    “…ODS materials constitute a new promising class of structural materials for advanced fission and fusion energy application. These Fe–Cr based ferritic steels…”
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    Journal Article
  17. 17

    Influence of the low interfacial density energy on the coarsening resistivity of the nano-oxide particles in Ti-added ODS material by Ribis, J., Lescoat, M.-L., Zhong, S.Y., Mathon, M.-H., de Carlan, Y.

    Published in Journal of nuclear materials (01-11-2013)
    “…The ODS materials are composed of very fine (Y,Ti,O) nano-particles. During annealing at 1573K, the nano-clusters evolve into a fully cubical shape…”
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    Journal Article
  18. 18

    High resolution Transmission Electron Microscopy characterization of a milled oxide dispersion strengthened steel powder by Loyer-Prost, M., Merot, J.-S., Ribis, J., Le Bouar, Y., Chaffron, L., Legendre, F.

    Published in Journal of nuclear materials (01-10-2016)
    “…Oxide Dispersion Strengthened (ODS) steels are promising materials for generation IV fuel claddings as their dense nano-oxide dispersion provides good creep…”
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    Journal Article
  19. 19

    Influence of nano-particle coherency degree on the coarsening resistivity of the nano-oxide particles of Fe–14Cr–1W ODS alloys by Zhong, S Y, Ribis, J, Lochet, N, de Carlan, Y, Klosek, V, Mathon, M H

    Published in Journal of nuclear materials (01-12-2014)
    “…High chrome oxide dispersion strengthened (ODS) ferritic alloys exhibit a high mechanical resistance at high temperature as well as high resistance to…”
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    Journal Article
  20. 20

    The effect of Ti/Y ratio on the recrystallisation behaviour of Fe–14%Cr oxide dispersion-strengthened alloys by Zhong, S.Y., Ribis, J., Baudin, T., Lochet, N., de Carlan, Y., Klosek, V., Mathon, M.H.

    Published in Journal of nuclear materials (01-09-2014)
    “…Oxide dispersion-strengthened (ODS) alloys have an extraordinarily high recrystallisation temperature that is highly sensitive to the particle size and the…”
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    Journal Article