Search Results - "Ribis, J"
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Interfacial strained structure and orientation relationships of the nanosized oxide particles deduced from elasticity-driven morphology in oxide dispersion strengthened materials
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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Structural and chemical matrix evolution following neutron irradiation in a MA957 oxide dispersion strengthened material
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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3
Nano-cluster stability following neutron irradiation in MA957 oxide dispersion strengthened material
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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Shape, orientation relationships and interface structure of beta-Nb nano-particles in neutron irradiated zirconium alloy
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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5
Interface roughening in irradiated oxide dispersion strengthened steels
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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6
HRTEM and chemical study of an ion-irradiated chromium/zircaloy-4 interface
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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Radiation-induced Ostwald ripening in oxide dispersion strengthened ferritic steels irradiated at high ion dose
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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8
Atomic-scale interface structure of a Cr-coated Zircaloy-4 material
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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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
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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10
Influence of plastic deformation on the precipitation sequence in an AA6061 alloy
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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In situ TEM study of the stability of nano-oxides in ODS steels under ion-irradiation
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 -
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Study of the thermal stability of nanoparticle distributions in an oxide dispersion strengthened (ODS) ferritic alloys
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
Relaxation path of metastable nanoclusters in oxide dispersion strengthened materials
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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14
Characterization of ion irradiated microstructure and cavity swelling evolution up to high doses in austenitic stainless steels representative of PWR internals
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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15
Relaxation path of nanoparticles in an oxygen-enriched ferritic oxide-dispersion-strengthened alloy
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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16
Radiation-sustained nanocluster metastability in oxide dispersion strengthened materials
Published in Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms (15-12-2015)“…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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Influence of the low interfacial density energy on the coarsening resistivity of the nano-oxide particles in Ti-added ODS material
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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18
High resolution Transmission Electron Microscopy characterization of a milled oxide dispersion strengthened steel powder
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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Influence of nano-particle coherency degree on the coarsening resistivity of the nano-oxide particles of Fe–14Cr–1W ODS alloys
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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The effect of Ti/Y ratio on the recrystallisation behaviour of Fe–14%Cr oxide dispersion-strengthened alloys
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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