Zobrazeno 1 - 10
of 42
pro vyhledávání: '"Jean-Christophe Brachet"'
Autor:
Jeremy Bischoff, Christine Delafoy, Christine Vauglin, Pierre Barberis, Cédric Roubeyrie, Delphine Perche, Dominique Duthoo, Frédéric Schuster, Jean-Christophe Brachet, Elmar W. Schweitzer, Kiran Nimishakavi
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 2, Pp 223-228 (2018)
AREVA NP (Courbevoie, Paris, France) is actively developing several enhanced accident-tolerant fuels cladding concepts ranging from near-term evolutionary (Cr-coated zirconium alloy cladding) to long-term revolutionary (SiC/SiC composite cladding) so
Externí odkaz:
https://doaj.org/article/e5fc343c6b114e4086a6df9ec054548c
Autor:
Joël Ribis, Alexia Wu, Raphaëlle Guillou, Jean-Christophe Brachet, Cédric Baumier, Aurélie Gentils, Marie Loyer-Prost
Publikováno v:
Materials; Volume 15; Issue 6; Pages: 2322
Materials
Materials, 2022, 15 (6), pp.2322. ⟨10.3390/ma15062322⟩
Materials
Materials, 2022, 15 (6), pp.2322. ⟨10.3390/ma15062322⟩
International audience; To improve the safety of nuclear power plants, a Cr protective layer is deposited on zirconium alloys to enhance oxidation resistance of the nuclear fuel cladding during both in-service and hypothetical accidental transients a
Autor:
Quentin Barres, Isabelle Turque, Gilles André, Jean-Christophe Brachet, Caroline Toffolon-Masclet, Raphaëlle Guillou, Jérôme Crépin, Matthieu Le Saux, Thai Le Hong, Jean-Marc Joubert
Publikováno v:
Acta Materialia
Acta Materialia, Elsevier, 2020, 199, pp.453-468. ⟨10.1016/j.actamat.2020.08.061⟩
Acta Materialia, Elsevier, 2020, 199, pp.453-468. ⟨10.1016/j.actamat.2020.08.061⟩
International audience; In hypothetical accidental conditions, zirconium-based nuclear fuel claddings can absorb high hydrogen contents (up to several thousand wppm) and be exposed to high temperatures (βZr phase temperature range) before being cool
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⟩
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
https://hal-ensta-bretagne.archives-ouvertes.fr/hal-03327638
Autor:
Jean-Christophe Brachet, Antoine Ambard, M. Le Saux, Raphaël Chosson, Stéphane Urvoy, Elodie Rouesne, Valérie Vandenberghe
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2019, 518, pp.386-399. ⟨10.1016/j.jnucmat.2019.03.023⟩
Journal of Nuclear Materials, Elsevier, 2019, 518, pp.386-399. ⟨10.1016/j.jnucmat.2019.03.023⟩
International audience; The effect of a pre-existing oxide layer formed at low temperature on the subsequent oxidation in steam at high temperature was studied for Zircaloy-4 and M5 Framatome alloys. Various pre-oxidation conditions (air at 550 °C,
Autor:
Jean-Christophe Brachet, Francis Maury, Stéphane Urvoy, Frédéric Ott, Elodie Rouesne, M. Dumerval, G. Nony, Frédéric Schuster, Alexandre Michau, M. Le Saux
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2021, 550, pp.152953. ⟨10.1016/j.jnucmat.2021.152953⟩
Journal of Nuclear Materials, 2021, 550, pp.152953. ⟨10.1016/j.jnucmat.2021.152953⟩
Journal of Nuclear Materials, Elsevier, 2021, 550, pp.152953. ⟨10.1016/j.jnucmat.2021.152953⟩
Journal of Nuclear Materials, 2021, 550, pp.152953. ⟨10.1016/j.jnucmat.2021.152953⟩
International audience; Zirconium-based claddings with an outer chromium coating resistant to corrosion are studied and devel- oped as an evolutionary Enhanced Accident Tolerant Fuel (E-ATF) concept for light water reactors. How- ever, in hypothetica
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e46d08dcd66e0872acb55550169a2647
https://hal-ensta-bretagne.archives-ouvertes.fr/hal-03212406/document
https://hal-ensta-bretagne.archives-ouvertes.fr/hal-03212406/document
Autor:
J. Bischoff, Jean-Christophe Brachet, Philippe Bossis, T. Vandenberghe, Edouard Pouillier, G. Nony, T. Guilbert, Hervé Palancher, M. Le Saux, Raphaël Chosson, A. Lequien, Stéphane Urvoy, C. Miton
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2020, 533, pp.152106-1-152106-16. ⟨10.1016/j.jnucmat.2020.152106⟩
Journal of Nuclear Materials, 2020, 533, pp.152106-1-152106-16. ⟨10.1016/j.jnucmat.2020.152106⟩
Journal of Nuclear Materials, Elsevier, 2020, 533, pp.152106-1-152106-16. ⟨10.1016/j.jnucmat.2020.152106⟩
Journal of Nuclear Materials, 2020, 533, pp.152106-1-152106-16. ⟨10.1016/j.jnucmat.2020.152106⟩
International audience; Cr-coated M5(Framatome) cladding materials are studied and developed within the CEA-Framatome-EDF French nuclear fuel joint program as Enhanced Accident Tolerant Fuel claddings for Light Water Reactors. The objective of this p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c1d6034589f30c013d03d6b517dda5e4
https://hal.archives-ouvertes.fr/hal-02639341
https://hal.archives-ouvertes.fr/hal-02639341
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⟩
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
https://hal.science/hal-02520055
Autor:
Bono, Matthew, Tuan-Hiep Pham, Courcelle, Arnaud, Mallet, Caroline, Sibille, Yannick, Wu, Alexia, Rouesne, Elodie, Jean-Christophe Brachet, Bischoff, Jeremy, Pouillier, Edouard
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5167e9c8e8b27b88e7c61992e906b451