Výsledky vyhledávání - "Matthieu Le Saux"

Combined effects of temperature and of high hydrogen and oxygen contents on the mechanical behavior of a zirconium alloy upon cooling from the βZr phase temperature range

Autor: Matthieu Le Saux, Jérôme Crépin, Thai Le Hong, Jean-Christophe Brachet

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2021, 554, pp.153069. ⟨10.1016/j.jnucmat.2021.153069⟩
Journal of Nuclear Materials, 2021, 554 (554), pp.153069. ⟨10.1016/j.jnucmat.2021.153069⟩

International audience; During hypothetical loss-of-coolant accidents (LOCA), zirconium-based nuclear fuel claddings can be exposed to high temperatures in the beta(Zr) phase domain and absorb substantial amounts of hydrogen (up to about 3000 weight

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f803e408272dd0a62a8c9b8d223955d1
https://hal-ensta-bretagne.archives-ouvertes.fr/hal-03327638

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High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process

Autor: Matthieu Le Saux, Elodie Rouesne, J. Ribis, Guillaume Nony, Stéphane Urvoy, Nihed Chaabane, Amandine David, Jean-Christophe Brachet, T. Guilbert, Edouard Pouillier, Julien Augereau, J. Bischoff, Hervé Palancher, Caroline Toffolon-Masclet

Publikováno v: Corrosion Science
Corrosion Science, 2020, ⟨10.1016/j.corsci.2020.108537⟩

International audience; The oxidation of chromium-coated zirconium-based alloys is studied under steam at temperatures ranging from 800 °C up to 1500 °C and for oxidation times ranging from a few minutes up to a few hours. For oxidation temperature

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f705e79efeb69cabe60eb67f182a0ccc
https://hal.science/hal-02520055

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Mechanical behavior of a chromium coating on a zirconium alloy substrate at room temperature

Autor: Jean-Philippe Bonthonneau, Arnaud Courcelle, Duc Vinh Nguyen, Elodie Rouesne, Raphaëlle Guillou, Lionel Gélébart, Stéphane Urvoy, Jean-Christophe Brachet, Matthieu Le Saux

Publikováno v: Journal of Nuclear Materials. 558:153332

The mechanical behavior of a 15 µm-thick chromium coating deposited on a zirconium alloy substrate using a particular physical vapor deposition process is studied at room temperature using several experimental techniques at different scales: biaxial

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::aa351057cbc0fd525eb2cbd05d3c39d9
https://doi.org/10.1016/j.jnucmat.2021.153332

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A model to describe the cyclic anisotropic mechanical behavior of short fiber-reinforced thermoplastics

Autor: Yann Marco, Sylvain Moyne, Matthieu Le Saux, Libor Navrátil, Jérôme Olhagaray, Vincent Le Saux, Louis Leveuf, Sylvain Leclercq

Publikováno v: 24e Congrès Français de Mécanique
24e Congrès Français de Mécanique, Aug 2019, Brest, France
Mechanics of Time-Dependent Materials
Mechanics of Time-Dependent Materials, 2020, ⟨10.1007/s11043-020-09445-1⟩

International audience; Due to the injection molding process, short fiber-reinforced thermoplastic composites show a complex fiber orientation distribution and, as a consequence, an overall anisotropic mechanical behavior. The monotonic and cyclic me

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::cb7837b4a1b21fcd6f4deac95b5b91dc
https://hal-ensta-bretagne.archives-ouvertes.fr/hal-02493873/document

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Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors

Autor: Valérie Vandenberghe, Gihan Velisa, Stéphane Urvoy, Fernando Lomello, Marc Tupin, Alain Billard, Elodie Rouesne, Frédéric Schuster, T. Guilbert, Marion Le Flem, Jean-Christophe Brachet, Cédric Ducros, Isabel Idarraga-Trujillo, Christian Phalippou, Caroline Toffolon-Masclet, Frédéric Sanchette, Matthieu Le Saux

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2019, 517, pp.268-285. ⟨10.1016/j.jnucmat.2019.02.018⟩
Journal of Nuclear Materials, 2019, 517, pp.268-285. ⟨10.1016/j.jnucmat.2019.02.018⟩

International audience; Coatings with thicknesses between a few microns and similar to 10 mu m deposited on a Zircaloy-4 substrate have been studied with the objective to provide a significant reduction in the oxidation-induced embrittlement of the n

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::895349c3a5884f058307858b8ffcfd7b
https://hal-ensta-bretagne.archives-ouvertes.fr/hal-02090215/document

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Breakaway oxidation of zirconium alloys exposed to steam around 1000 °C

Autor: Valérie Vandenberghe, Matthieu Le Saux, Antoine Ambard, Raphaël Chosson, Jean-Christophe Brachet

Publikováno v: Corrosion Science
Corrosion Science, 2020, 176 (108936), pp.1-21. ⟨10.1016/j.corsci.2020.108936⟩
Corrosion Science, Elsevier, 2020, 176 (108936), pp.1-21. ⟨10.1016/j.corsci.2020.108936⟩

International audience; The breakaway oxidation of Zircaloy-4 and M5Framatome alloys oxidized in flowing steam around 1000 °C wasstudied. The influences of oxidation temperature between 950 and 1050 °C, one-side versus two-side oxidationand chemica

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::575f8991a2b31b9f16623059a6118504
https://doi.org/10.1016/j.corsci.2020.108936

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Study of secondary hydriding at high temperature in zirconium based nuclear fuel cladding tubes by coupling information from neutron radiography/tomography, electron probe micro analysis, micro elastic recoil detection analysis and laser induced breakdown spectroscopy microprobe

Autor: Caroline Raepsaet, Jean-Christophe Brachet, Jean-Luc Lacour, Frédéric Ott, Elodie Rouesne, Valérie Vandenberghe, Guy Bayon, Jean-Luc Béchade, Didier Hamon, Matthieu Le Saux, Stéphane Urvoy, Caroline Toffolon-Masclet

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, 2017, 488, pp.267-286. ⟨10.1016/j.jnucmat.2017.03.009⟩
Journal of Nuclear Materials, Elsevier, 2017, 488, pp.267-286. 〈http://www.sciencedirect.com/science/article/pii/S0022311516308960〉. 〈10.1016/j.jnucmat.2017.03.009〉
Journal of Nuclear Materials, Elsevier, 2017, 488, ⟨10.1016/j.jnucmat.2017.03.009⟩
Journal of Nuclear Materials, Elsevier, 2017, 488, pp.267-286. ⟨10.1016/j.jnucmat.2017.03.009⟩

International audience; This paper gives an overview of a multi-scale experimental study of the secondary hydriding phenomena that can occur in nuclear fuel cladding materials exposed to steam at high temperature (HT) after having burst (loss-of-cool

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::24ca8cbff68204ff1bf8ee7fd75995a3
https://cea.hal.science/cea-01488896

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