Philippe Fillion

Identifiants chercheurs

IdHAL :

philippe-fillion

ORCID :

0000-0002-8581-4593

Publications

Article dans une revue (11)

Modeling of droplet entrainment in horizontal pipes at low pressure for system thermal-hydraulics codes Philippe Fillion,Sofia Carnevali,Adrien Rodriguez Nuclear Engineering and Design, 2025, 442, pp.114265. ⟨10.1016/j.nucengdes.2025.114265⟩ Article dans une revue cea-05293633v1
Benchmark DEBORA: Assessment of MCFD compared to high-pressure boiling pipe flow measurements G. Bois,P. Fillion,F. François,A. Burlot,A. Ben Hadj Aliet al. International Journal of Multiphase Flow, 2024, 179, pp.104920. ⟨10.1016/j.ijmultiphaseflow.2024.104920⟩ Article dans une revue cea-04695258v1
A systematic approach for the adequacy analysis of a set of experimental databases: application in the framework of the ATRIUM activity Jean Baccou,Tony Glantz,Alberto Ghione,Lucia Sargentini,Philippe Fillionet al. Nuclear Engineering and Design, 2024, 421, pp.113035. ⟨10.1016/j.nucengdes.2024.113035⟩ Article dans une revue cea-04491875v1
Modeling single-phase transverse flows in a PWR rod bundle at low Reynolds number Qinjun Fu,Andre Bergeron,Philippe Fillion,Yohan Davit,Michel Quintard Nuclear Engineering and Design, 2024, 416, pp.112752. ⟨10.1016/j.nucengdes.2023.112752⟩ Article dans une revue cea-04370869v1
Assessment of stratification and entrainment models in CATHARE 3 code during FONESYS activities Sofia Carnevali,Philippe Fillion Nuclear Engineering and Design, 2024, 430, pp.113700. ⟨10.1016/j.nucengdes.2024.113700⟩ Article dans une revue cea-04803344v1
TPTF horizontal flow prediction by SYS-TH codes – Recent analyses made within the FONESYS network M. Lanfredini,D. Bestion,F. d'Auria,N. Aydemir,S. Carnevaliet al. Nuclear Engineering and Design, 2023, 402, pp.112106. ⟨10.1016/j.nucengdes.2022.112106⟩ Article dans une revue cea-04452324v1
SAPIUM: a generic framework for a practical and transparent quantification of thermal hydraulic code model input uncertainty Jean Baccou,Jinzhao Zhang,Philippe Fillion,Guillaume Damblin,Alessandro Petruzziet al. Nuclear Science and Engineering, 2020, 194, pp.721-736. ⟨10.1080/00295639.2020.1759310⟩ Article dans une revue hal-03149294v1
Critical flow prediction by system codes – Recent analyses made within the FONESYS network M. Lanfredini,D. Bestion,F. d'Auria,N. Aksan,P. Fillionet al. Nuclear Engineering and Design, 2020, 366, pp.110731. ⟨10.1016/j.nucengdes.2020.110731⟩ Article dans une revue cea-04384302v1
Development of good practice guidance for quantification of thermal-hydraulic code model input uncertainty J. Baccou,J. Zhang,P. Fillion,G. Damblin,A. Petruzziet al. Nuclear Engineering and Design, 2019, 354, ⟨10.1016/j.nucengdes.2019.110173⟩ Article dans une revue hal-02530001v1
Analysis of the NUPEC PSBT Tests with FLICA-OVAP Matteo Bucci,Philippe Fillion Science and Technology of Nuclear Installations, 2012, 2012, pp.1-18. ⟨10.1155/2012/436142⟩ Article dans une revue cea-04911398v1
NEPTUNE: a new software platform for advanced nuclear thermal hydraulics Antoine Guelfi,Dominique Bestion,Marc Boucker,Pascal Boudier,Philippe Fillionet al. Nuclear Science and Engineering, 2007, 156 (3), pp.281-324. ⟨10.13182/NSE05-98⟩ Article dans une revue hal-01580126v1

Communication dans un congrès (32)

Non-uniform flows through a 8x34 PWR-type rod bundle: PIV and pressure drop measurements Clément Melin,Benjamin Cariteau,Philippe Fillion SWINTH 2024 - Specialist Workshop on Advanced Instrumentation and Measurement Techniques for Nuclear Reactor Thermal Hydraulics and Severe Accidents, Jun 2024, Dresde, Germany. pp.017 Communication dans un congrès cea-04750812v1
Adequacy analysis of critical flow experiments in the framework of the OECD-NEA ATRIUM project: CEA's contribution Alberto Ghione,Lucia Sargentini,Guillaume Damblin,Philippe Fillion BEPU 2024 - Best Estimate Plus Uncertainty International Conference, May 2024, Lucca, Italy. pp.BEPU2024-353 Communication dans un congrès cea-04706836v1
Experimental qualification of a PIV and two-dye LIF temperature field measurement system with the &quot;filling box&quot; experiment in liquid flow Vincent Helfer,Benjamin Cariteau,Philippe Fillion,A Toutant SWINTH 2024, Jun 2024, Dresden, Germany. pp.056 Communication dans un congrès cea-04675570v1
Validation of the system code CATHARE3 on critical flow experiments in the framework of the OECD-NEA ATRIUM project Alberto Ghione,Lucia Sargentini,Guillaume Damblin,Philippe Fillion NUTHOS-14 - The 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety, Aug 2024, Vancouver, Canada Communication dans un congrès cea-04711360v1
METERO-V and PRIUS experimental programs: complementary separate effects tests for core mixing validation Philippe Fillion,Seok Kim,Clément Melin,Gilles Bernard-Michel,Benjamin Cariteauet al. NURETH-20 - 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2023, Washington DC, United States. pp.1848-1861, ⟨10.13182/NURETH20-41365⟩ Communication dans un congrès cea-04371973v1
Application of SAPIUM guidelines to Input Uncertainty Quantification: the ATRIUM project Alberto Ghione,Lucia Sargentini,Guillaume Damblin,Philippe Fillion,Jean Baccouet al. 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 20), American Nuclear Society, Aug 2023, Washington DC, United States. pp.5734-5747, ⟨10.13182/NURETH20-40380⟩ Communication dans un congrès cea-04191079v1
Recommendations for new Experiments able to Better Characterize Flashing Flows in Nozzles for Improving Critical Flow Modelling in System Codes Dominique Bestion,Francesco d'Auria,Klaus Umminger,Philippe Fillion,Seok Kimet al. NURETH-20, Aug 2023, Washington, D.C., United States. pp.1502-1515, ⟨10.13182/NURETH20-40676⟩ Communication dans un congrès cea-04390515v1
Uniform and non-uniform flows through a PWR-type rod bundle with mixing grids at Reynolds number ranging from 800 up to 70000: pressure loss measurements Clément Melin,Gilles Bernard-Michel,Benjamin Cariteau,Philippe Fillion NURETH-20 - 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2023, Washington, D.C., United States. pp.1946-1956 Communication dans un congrès cea-04371975v1
METERO-V experimental set-up: presentation and first results. Uniform flows through a 8x34 PWR-type rod bundle with mixing grids at Reynolds number ranging from 800 to 70000: pressure loss measurements Clément Melin,Gilles Bernard-Michel,Benjamin Cariteau,Philippe Fillion ICAPP 2023 - 2023 International Congress on Advances in Nuclear Power Plants, in conjunction with 38th Korea Atomic Power Annual Conference, Apr 2023, Gyeongju, South Korea. pp.233 Communication dans un congrès cea-04464968v1
Validation of the CATHARE 3 code based on Rod Bundle Heat Transfer (RBHT) benchmark data using two-fluid and three-field models Antoine Du Cluzeau,Philippe Fillion NURETH-19 - The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, ANS; IAEA; NRG, Mar 2022, Brussels (online), Belgium Communication dans un congrès cea-04256708v1
Qualification expérimentale d'un système de thermographie LIF-2D Vincent Helfer,Clément Melin,Adrien Toutant,Gilles Bernard-Michel,Philippe Fillionet al. Congrès Francophone de Techniques Laser, Sep 2022, Leuven, Belgique Communication dans un congrès cea-04675537v1
TPTF horizontal flow prediction by SYS-TH codes - Recent analyses made within the FONESYS network M. Lanfredini,D. Bestion,F. d'Auria,N. Aydemir,Sofia Carnevaliet al. The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Mar 2022, Brussels (online), Belgium. pp.35792 Communication dans un congrès cea-04098083v1
Horizontal stratification criteria of 8 system codes and direct confrontation to TPTF and Mantilla data M. Lanfredini,D. Bestion,F. d'Auria,N. Aydemir,Sofia Carnevaliet al. The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Mar 2022, Bruxelles (Virtual), Belgium. pp.35791 Communication dans un congrès cea-04371870v1
Droplet entrainment prediction in horizontal flow by SYS-TH codes - Mantilla experiments - Recent analyses made with the FONESYS network M. Lanfredini,D. Bestion,F. d'Auria,N. Aydemir,Sofia Carnevaliet al. The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Mar 2022, Brussels (Virtual), Belgium. pp.35793 Communication dans un congrès cea-04371871v1
SAPIUM - Follow-up activities, perspectives for future development Philippe Fillion,Lucia Sargentini,Alberto Ghione,Guillaume Damblin NURETH-19 - 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Mar 2022, Bruxelles, Belgium Communication dans un congrès cea-04417233v1
Assessment of stratification and entrainment models in CATHARE 3 code against TPTF-H and Mantilla experiments Sofia Carnevali,Philippe Fillion NURETH-19 - The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Mar 2022, Bruxelles (Conference virtuelle), Belgium Communication dans un congrès cea-03985842v1
SAPIUM - Selection of adequate test database for IUQ Philippe Fillion 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Mar 2022, Brussels (virtual), Belgium Communication dans un congrès cea-04440551v1
Some progresses in system code modelling validation and application including 3D modelling Dominique Bestion,Philippe Fillion,Raphaël Préa ATH'2020 - Advances in Thermal Hydraulics 2020, Oct 2020, Palaiseau, France. pp.661-674 Communication dans un congrès cea-04220353v1
Some Progress Made in Multiscale Analysis, Multiscale Simulation and Multi-Scale Validation in Reactor Thermalhydraulics Dominique Bestion,Philippe Fillion,Christophe Rabe,Raphaël Préa,Stéphane Mimouniet al. Advances in Thermal Hydraulics 2020, Oct 2020, Palaiseau, France. pp.1105-1116 Communication dans un congrès cea-04221795v1
CATHARE-3 V2.1: The new industrial version of the CATHARE code Raphaël Préa,Philippe Fillion,Laura Matteo,Gédéon Mauger,Anouar Mekkas ATH'20 - Advances in Thermal Hydraulics 2020, Oct 2020, Palaiseau, France. https://www.ans.org/pubs/proceedings/article-49142/ Communication dans un congrès cea-04087378v1
Development of the CATHARE 3 three-field model for simulations in large diameter horizontal pipes Philippe Fillion NURETH 2019 - 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2019, Portland, United States. pp.6271-6282 Communication dans un congrès cea-04382534v1
3-D SYS-TH: an OECD/NEA activity on multi-dimensional capabilities of thermalhydraulic system codes Christophe Herer,Dominique Bestion,Philippe Fillion,Raphaël Préa,Valeria Parrinelloet al. ICAPP 2019 – International Congress on Advances in Nuclear Power Plants, May 2019, Juan-les-pins, France Communication dans un congrès cea-04221858v1
A mechanistic flashing model for critical flowrate prediction using CATHARE 3 system code Maxime Vernassiere,Philippe Fillion,Dominique Bestion ICAPP 2019 - 2019 International Congress on Advances in Nuclear Power Plants, May 2019, Juan-les-pins, France Communication dans un congrès cea-04217103v1
Analysis of flow in rod bundles with velocity and temperature radial dissymmetry using CATHARE-3 Qinjun Fu,Dominique Bestion,Philippe Fillion,Yohan Davit,Michel Quintard ICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan-les-Pins, France. pp.1-8 Communication dans un congrès hal-02380403v1
Revisiting the PIRT and scaling analysis within the frame of 3D system code modelling Dominique Bestion,Philippe Fillion 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2019, Portland (OR), United States. pp.4109-4122 Communication dans un congrès hal-04380272v1
Development of a systematic approach for quantification of thermal hydraulic code model input uncertainty Jean Baccou,Jinzhao Zhang,Philippe Fillion,Guillaume Damblin,Alessandro Petruzziet al. NURETH2019 - 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2019, Portland (OR), United States. pp.3054-3067 Communication dans un congrès cea-04378696v1
SAPIUM a systematic approach for input uncertainty quantification J. Baccou,D. Bestion,M. Couplet,G. Damblin,P. Fillionet al. BEPU-2018, May 2018, Lucca, Italy Communication dans un congrès cea-02338977v1
Assessing the accuracy of energy turbulent diffusion dispersion correlation in a porous two-fluid model dedicated to PWR core simulations Qinjun Fu,D. Bestion,P. Fillion,Michel Quintard,Yohan Davit 14emes Journees d'etudes des Milieux Poreux - JEMP 2018, Oct 2018, Nantes, France Communication dans un congrès cea-02339457v1
Improved PWR LOCA simulations through refined core 3D simulations - An advanced 3D modelling and the associated METERO validation program Dominique Bestion,Philippe Fillion,Raphaël Préa,Gilles Bernard-Michel NUTHOS-12 - 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety, Oct 2018, Qingdao, China Communication dans un congrès cea-04084545v1
Prediction of annular flows in vertical pipes with new correlations for the CATHARE-3 three-field model M. Spirzewski,P. Fillion,M. Valette 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Sep 2017, Xi'An, China Communication dans un congrès cea-02434037v1
3d core thermalhydraulic phenomena in pwr sblocas and iblocas D. Bestion,M. Valette,P. Fillion,P. Gaillard NURETH-17, Sep 2017, Xian, China Communication dans un congrès hal-02433889v1
Assessment of correlations for low pressure subcooled boiling flows studies using the drift flux model of FLICA codes Philippe Fillion,Patricia Salvatore NURETH-15 - The 15th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, May 2013, Pise, Italy Communication dans un congrès cea-05128940v1