Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Marine Anderhuber"'
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
Autor:
Sara Perez-Martin, Laurent Laborde, Calogera Lombardo, N. Girault, Marine Anderhuber, Werner Pfrang, Christophe Peniguel, Luca Ammirabile, Konstantin Mikityuk, Stephane Mimouni
Publikováno v:
Journal of Nuclear Engineering and Radiation Science
The computational codes used in the evaluation of the ESFR-SMART reactor performance and specifically their sodium boiling models are assessed using two KNS-37 LOF experiments, i.e. L22 and L29 tests, where boiling onset and two-phase flow regime up
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:
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
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
Autor:
Antoine Gerschenfeld, Philippe Marsault, Marine Anderhuber, Dominique Kadri, Jorge Perez, Pierre Sciora, Nicolas Alpy, Romain Lavastre
Publikováno v:
Journal of Nuclear Science and Technology
Journal of Nuclear Science and Technology, 2016, 53 (5), pp.692-697. ⟨10.1080/00223131.2015.1111778⟩
Journal of Nuclear Science and Technology, Nihon Genshiryoku Gakkai, 2016, 53 (5), pp.692-697. ⟨10.1080/00223131.2015.1111778⟩
Journal of Nuclear Science and Technology, 2016, 53 (5), pp.692-697. ⟨10.1080/00223131.2015.1111778⟩
Journal of Nuclear Science and Technology, Nihon Genshiryoku Gakkai, 2016, 53 (5), pp.692-697. ⟨10.1080/00223131.2015.1111778⟩
International audience; In the framework of the research and development on GEN IV sodium fast reactors (SFRs), the phenomenology of sodium boiling during a postulated unprotected loss of flow (ULOF) transient has been investigated with the CATHARE 2
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0805f81eb53986b624fb023545c2bdc0
https://cea.hal.science/cea-02933360
https://cea.hal.science/cea-02933360