Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Philippe Fillion"'
Autor:
Matteo Bucci, Philippe Fillion
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2012 (2012)
This paper discusses the results of a computational activity devoted to the prediction of two-phase flows in subchannels and in rod bundles. The capabilities of the FLICA-OVAP code have been tested against an extensive experimental database made avai
Externí odkaz:
https://doaj.org/article/2d2d00f1855642e9be52b11c850c8d7a
Autor:
Jinzhao Zhang, Guillaume Damblin, Francesc Reventos, Mathieu Couplet, Jean Baccou, Nils Sandberg, Bertrand Iooss, Philippe Fillion, Takeshi Takeda, Alessandro Petruzzi, T. Skorek, Deog-Yeon Oh, Rafael Mendizábal
Publikováno v:
Nuclear Science and Engineering
Nuclear Science and Engineering, 2020, 194, pp.721-736. ⟨10.1080/00295639.2020.1759310⟩
Nuclear Science and Engineering, Academic Press, 2020, 194, pp.721-736. ⟨10.1080/00295639.2020.1759310⟩
Nuclear Science and Engineering, 2020, 194, pp.721-736. ⟨10.1080/00295639.2020.1759310⟩
Nuclear Science and Engineering, Academic Press, 2020, 194, pp.721-736. ⟨10.1080/00295639.2020.1759310⟩
International audience; Uncertainty analysis (UA) is a key element in nuclear power plant (NPP) deterministic safety analysis using best-estimate thermal hydraulic codes and best estimate plus uncertainty (BEPU) methodologies. If forward uncertainty
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::019d4c82dcc9c210783d300b1f077489
https://hal.science/hal-03149294
https://hal.science/hal-03149294
Autor:
P. Gaillard, N. Aksan, D. Bestion, M. Lanfredini, Joona Kurki, Jaeseok Heo, Philippe Fillion, A. Shen, Ismo Karppinen, D. Wang, J. L. Vacher, F. D'Auria, Kwang-Rag Kim, L. Liu
Publikováno v:
Lanfredini, M, Bestion, D, D'Auria, F, Aksan, N, Fillion, P, Gaillard, P, Heo, J, Karppinen, I, Kim, K D, Kurki, J, Liu, L, Shen, A, Vacher, J L & Wang, D 2020, ' Critical flow prediction by system codes – Recent analyses made within the FONESYS network ', Nuclear Engineering and Design, vol. 366, 110731 . https://doi.org/10.1016/j.nucengdes.2020.110731
A benchmark activity on Two-Phase Critical Flow (TPCF) prediction was conducted in the framework of the Forum & Network of System Thermal-Hydraulics Nuclear Reactor Thermal-Hydraulics (FONESYS). FONESYS is a network among code developers who share th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::98c4782aad03a36190c36a1d358f1e5f
http://hdl.handle.net/11568/1064167
http://hdl.handle.net/11568/1064167
Autor:
Takeshi Takeda, Jinzhao Zhang, Francesc Reventos, Alessandro Petruzzi, Deog-Yeon Oh, Rafael Mendizábal, T. Skorek, Jean Baccou, Guillaume Damblin, Mathieu Couplet, Philippe Fillion, Bertrand Iooss
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2019, 354, ⟨10.1016/j.nucengdes.2019.110173⟩
Nuclear Engineering and Design, 2019, 354, ⟨10.1016/j.nucengdes.2019.110173⟩
Nuclear Engineering and Design, Elsevier, 2019, 354, ⟨10.1016/j.nucengdes.2019.110173⟩
Nuclear Engineering and Design, 2019, 354, ⟨10.1016/j.nucengdes.2019.110173⟩
International audience; Taking into account uncertainties is a key issue in nuclear power plant safety analysis using best estimate plus uncertainty methodologies. It involves two main types of treatment depending on the variables of interest: input
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2f24ea6ee5bef54a8769fc75ffc1e7d1
https://hal.archives-ouvertes.fr/hal-02530001/document
https://hal.archives-ouvertes.fr/hal-02530001/document
Publikováno v:
Nuclear Engineering and Design. 241:4348-4358
FLICA-OVAP is a new platform dedicated to core thermal–hydraulic studies, funded by the Thermal–hydraulics Simulation project of CEA. It includes both subchannel scale and CFD scale capabilities. To provide a relevant response to different core c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6a13a7ec08dc870b2f5e3c275260cba1
https://doi.org/10.1016/j.nucengdes.2011.04.048
https://doi.org/10.1016/j.nucengdes.2011.04.048
Autor:
Pascal Boudier, Eric Hervieu, Jean-Marc Hérard, Pierre Péturaud, D. Bestion, Philippe Fillion, Antoine Guelfi, Marc Grandotto, M. Boucker
Publikováno v:
Nuclear Science and Engineering
Nuclear Science and Engineering, 2007, 156 (3), pp.281-324
Nuclear Science and Engineering, Academic Press, 2007, 156 (3), pp.281-324
Nuclear Science and Engineering, 2007, 156 (3), pp.281-324
Nuclear Science and Engineering, Academic Press, 2007, 156 (3), pp.281-324
The NEPTUNE project constitutes the thermal-hydraulic part of the long-term Electricite de France and Commissariat a l’Energie Atomique joint research and development program for the next generatio...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::67ed6ecc2cbae421b62256fb68cec242
https://doi.org/10.13182/nse05-98
https://doi.org/10.13182/nse05-98