Zobrazeno 1 - 10
of 153
pro vyhledávání: '"F. Leprêtre"'
Akademický článek
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Autor:
J. Allard, A. Amadon, G. Aubert, J. Belorgey, C. Berriaud, C. Bonnelye, R. Boudoin, N. Boulant, T. Boussuge, F. Boumezbeur, P. Brédy, P. Dietz, G. Dilasser, Y. Drouen, O. Dubois, S. Faict-Bastin, I. Gonzalez Insua, V. Gras, Q. Guihard, P. Guiho, J-C. Guillard, V. Jannot, F-P. Juster, F. Koeber, B. Koestel, D. Le Bihan, R. Leboeuf, C. Lerman, F. Leprêtre, A. Lotodé, F. Nunio, L. Quettier, H. Landes, H. Lannou, A. Massire, F. Mauconduit, F. Molinié, H. Neyrial, C. Péron, L. Renou, A. Roger, P. Rouffiat, W. Ruth, T. Schild, P. Sieber, M. Santin, M. Schroeder, L. Scola, A. Sinanna, V. Stepanov, M. Szmigiel, O. Tellier, R. Touzery, P. Védrine, A. Vignaud, C. Walter, K. Wicklow
Synopsis: The Iseult project started in 2001 and is a collaborative effort involving CEA and the University of Freiburg in academics, Guerbet, Siemens Healthineers and Bruker Biospin as industrial partners. One central aspect of the project has been
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::493829aa30976ab967a6c6029a572743
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2021, pp.152807. ⟨10.1016/j.jnucmat.2021.152807⟩
Journal of Nuclear Materials, Elsevier, 2021, pp.152807. ⟨10.1016/j.jnucmat.2021.152807⟩
International audience; The evolution of radiation damage in steels is a major issue for the safe operation of nuclear power plants. Mn and Ni contribution to the formation and evolution of microstructural features remains a controversial issue. The
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ed3f535348a2e3216ce3e34c75cf375c
https://hal-normandie-univ.archives-ouvertes.fr/hal-03127358
https://hal-normandie-univ.archives-ouvertes.fr/hal-03127358
Autor:
F. Leprêtre, M. Bricout, Renaud C. Belin, Aurélien Debelle, Gaëlle Gutierrez, Yves Pipon, Frédérico Garrido, C. Onofri
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2020, 531, pp.151967. ⟨10.1016/j.jnucmat.2019.151967⟩
Journal of Nuclear Materials, 2020, 531, pp.151967. ⟨10.1016/j.jnucmat.2019.151967⟩
Journal of Nuclear Materials, Elsevier, 2020, 531, pp.151967. ⟨10.1016/j.jnucmat.2019.151967⟩
Journal of Nuclear Materials, 2020, 531, pp.151967. ⟨10.1016/j.jnucmat.2019.151967⟩
A coupling between the nuclear and electronic energy losses occur in the nuclear fuel (UO2) during in-reactor operations. However, the underlying mechanisms involved are still to be investigated. In this work, synergistic effects of nuclear and elect
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c04fa1aeb768f15edb3bdd50bf642e79
https://hal-cea.archives-ouvertes.fr/cea-02459763
https://hal-cea.archives-ouvertes.fr/cea-02459763
Autor:
Marco Beghi, Kumar Sridharan, L. Van Brutzel, Alain Chartier, F. Leprêtre, Lucile Beck, F. García Ferré, A. Mairov, F. Di Fonzo, Yves Serruys, M. Vanazzi
Publikováno v:
Acta Materialia
Acta Materialia, 2018, 143, pp. 156. ⟨10.1016/j.actamat.2017.10.011⟩
Acta Materialia, 2018, 143, pp. 156. ⟨10.1016/j.actamat.2017.10.011⟩
International audience; Oxide nanoceramics combine the enhanced radiation tolerance of nanocrystalline materials with the chemical inertness of oxides, and are promising materials for highly corrosive and intense radiation environments. In this work,
Autor:
F. Leprêtre, Victor Garric, Patricia Donnadieu, Kimberly Colas, Véronique Cloute-Cazalaa, Bénédicte Kapusta, Marie Loyer-Prost
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2021, 557, pp.153273. ⟨10.1016/j.jnucmat.2021.153273⟩
Journal of Nuclear Materials, 2021, 557, pp.153273. ⟨10.1016/j.jnucmat.2021.153273⟩
Journal of Nuclear Materials, Elsevier, 2021, 557, pp.153273. ⟨10.1016/j.jnucmat.2021.153273⟩
Journal of Nuclear Materials, 2021, 557, pp.153273. ⟨10.1016/j.jnucmat.2021.153273⟩
International audience; Swelling of metals under irradiation is largely studied in the nuclear industry for its impact on the safe and efficient operation of reactors. However, the case of aluminum alloys remains poorly documented as they are exclusi
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
Autor:
F. Leprêtre, Yves Serruys, Alexis Deschamps, Camille Flament, J. Ribis, J. Garnier, Patricia Donnadieu
Publikováno v:
Philosophical Magazine
Philosophical Magazine, 2016, 96 (24), pp.2504-2517. ⟨10.1080/14786435.2016.1205230⟩
Philosophical Magazine, Taylor & Francis, 2016, 96 (24), pp.2504-2517. ⟨10.1080/14786435.2016.1205230⟩
Philosophical Magazine, 2016, 96 (24), pp.2504-2517. ⟨10.1080/14786435.2016.1205230⟩
Philosophical Magazine, Taylor & Francis, 2016, 96 (24), pp.2504-2517. ⟨10.1080/14786435.2016.1205230⟩
International audience; In irradiated material, cavities result from the condensation of vacancies induced by collision cascades. The study of their formation is a relevant topic since a high density of cavities may alter significantly the material p
Autor:
R. Verlet, J. Huguet-Garcia, Lionel Thomé, Sandrine Miro, Lucile Beck, M. Tupin, D. Gosset, Jean-Marc Costantini, Yves Serruys, Patrick Trocellier, M. Belleil, F. Leprêtre, E. Bordas
Publikováno v:
Journal of Raman Spectroscopy. 47:476-485
Raman spectroscopy is an efficient technique for studying the evolution of microstructure of materials under irradiation. For that purpose, a Raman spectrometer has been recently installed at the JANNUS-Saclay platform. In this paper, we describe the
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2018, 504, pp.289-299. ⟨10.1016/j.jnucmat.2018.01.029⟩
Journal of Nuclear Materials, 2018, 504, pp.289-299. ⟨10.1016/j.jnucmat.2018.01.029⟩
Journal of Nuclear Materials, Elsevier, 2018, 504, pp.289-299. ⟨10.1016/j.jnucmat.2018.01.029⟩
Journal of Nuclear Materials, 2018, 504, pp.289-299. ⟨10.1016/j.jnucmat.2018.01.029⟩
International audience; Chromium-coated zirconium alloys are being studied as Enhanced Accident Tolerant Fuel Cladding for Light Water Reactors (LWRs). Those materials are especially studied to improve the oxidation resistance of LWRs current fuel cl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::550ba30647520d5dd191589256e906b1
https://hal-cea.archives-ouvertes.fr/cea-02428719/file/1-s2.0-S0022311517313338-main.pdf
https://hal-cea.archives-ouvertes.fr/cea-02428719/file/1-s2.0-S0022311517313338-main.pdf