Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Antoine, Gerschenfeld"'
Autor:
Sara Perez-Martin, Christophe Peniguel, Antoine Gerschenfeld, Laurent Laborde, Stephane Mimouni, Konstantin Mikityuk, Haileyesus Tsige-Tamirat, Werner Pfrang, Marine Anderhuber
Publikováno v:
Journal of Nuclear Engineering and Radiation Science
Journal of Nuclear Engineering and Radiation Science, 2021, 8 (1), ⟨10.1115/1.4051066⟩
Journal of Nuclear Engineering and Radiation Science, 2021, 8 (1), ⟨10.1115/1.4051066⟩
International audience; The Euratom Horizon-2020 project European sodium fast reactor safety measures assessment and research tools (ESFR-SMART) aims to enhance the safety and performance of the European sodium-cooled fast reactor (ESFR) considering
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7526df0b6b7ba25624e7b9628f778b2e
Autor:
Amandine Marrel, Simon Li, Antoine Gerschenfeld, Marine Anderhuber, Sophie Bajard, Baptiste Grosjean, Yannick Gorsse, Nathalie Marie, Michel Marquès, Gédéon Mauger, Chotaire Geffray, Annick Tosello, Jorge Perez, Laura Matteo
Publikováno v:
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2021, 7, pp.3. ⟨10.1051/epjn/2021002⟩
EPJ Nuclear Sciences & Technologies, Vol 7, p 3 (2021)
EPJ N-Nuclear Sciences & Technologies, 2021, 7, pp.3. ⟨10.1051/epjn/2021002⟩
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2021, 7, pp.3. ⟨10.1051/epjn/2021002⟩
EPJ Nuclear Sciences & Technologies, Vol 7, p 3 (2021)
EPJ N-Nuclear Sciences & Technologies, 2021, 7, pp.3. ⟨10.1051/epjn/2021002⟩
International audience; Within the framework of the French 4th-generation Sodium-cooled Fast Reactor safety assessment, methodology on VVUQ (Verification, Validation, Uncertainty Quantification) is conducted to demonstrate that the CEA's thermal-hydr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::53205590d57b8657935fd18b4cda0e8c
https://hal.archives-ouvertes.fr/hal-03133360/file/epjn200008.pdf
https://hal.archives-ouvertes.fr/hal-03133360/file/epjn200008.pdf
Autor:
F. Álvarez-Velarde, Konstantin Mikityuk, Pablo Romojaro, Janos Bodi, Antoine Gerschenfeld, Joel Guidez, U. Diaz-Chiron
Publikováno v:
EPJ Web of Conferences, Vol 247, p 01002 (2021)
Even before Fukushima accident occurred, the safety authorities have required that new power plant designs must take into account beyond design-basis accidents including possible core meltdown. Among the mitigation strategies, the corium retention mu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4efa6c27ba8a4860efcce58caad6be27
https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_01002.pdf
https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_01002.pdf
Autor:
Am. Baudron, Marine Anderhuber, A. Canas Junquera, Yannick Gorsse, G. Campioni, K. Ammar, N. Alpy, Antoine Gerschenfeld, P. Sciora, V. Pascal, C. Patricot
Publikováno v:
EPJ Web of Conferences, Vol 247, p 07001 (2021)
Sodium cooled fast neutron reactors (SFR) are one of the selected reactor concepts in the framework of the Generation IV International Forum. In this concept, unprotected loss of cooling flow transients (ULOF), for which the non-triggering of backup
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4d49bdd4e7609bc17b3aaf6c6ddd6d51
https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_07001.pdf
https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_07001.pdf
Publikováno v:
14th WCCM-ECCOMAS Congress.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b51b8fd006a6e6d49bcc0932edfe10d5
https://doi.org/10.23967/wccm-eccomas.2020.232
https://doi.org/10.23967/wccm-eccomas.2020.232
Autor:
Marine Anderhuber, N. Alpy, Marc Medale, Antoine Gerschenfeld, E. Bissen, J. Perez-Manes, C. Latge
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, 2020, 365, pp.110728. ⟨10.1016/j.nucengdes.2020.110728⟩
Nuclear Engineering and Design, Elsevier, 2020, 365, pp.110728. ⟨10.1016/j.nucengdes.2020.110728⟩
Nuclear Engineering and Design, 2020, 365, pp.110728. ⟨10.1016/j.nucengdes.2020.110728⟩
Nuclear Engineering and Design, Elsevier, 2020, 365, pp.110728. ⟨10.1016/j.nucengdes.2020.110728⟩
International audience; The paper proposes an overview of an R&D program for Gen4 Sodium Fast Reactors that was launched in 2012 at CEA to investigate Na boiling dynamics under an Unprotected Loss of Flow scenario. Part of the program motivation was
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2e6a0c807c0b589ace9c6e00c96942b9
https://amu.hal.science/hal-03188986/document
https://amu.hal.science/hal-03188986/document
Publikováno v:
EPJ Web of Conferences, Vol 247, p 07013 (2021)
Due to the high confinement of the closed fuel assemblies in Sodium-cooled Fast Reactors (SFR), the liquid sodium filling the space between these assemblies may vaporize in case of an important mechanical excitation (cavitation process). That phenome
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7e4ddd3324f27dbcf1e72c27dd87ad7b
https://doi.org/10.1051/epjconf/202124707013
https://doi.org/10.1051/epjconf/202124707013
Publikováno v:
Outils de calcul scientifique : applications industrielles et perspectives.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a18b34e66d397c5c1a1d03f98c55c9ef
https://doi.org/10.1051/jtsfen/2018out05a
https://doi.org/10.1051/jtsfen/2018out05a