Philippe Fillion

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Publications

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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
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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
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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
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Benchmark DEBORA: Assessment of MCFD compared to high-pressure boiling pipe flow measurements

G. Bois , P. Fillion , F. François , A. Burlot , A. Ben Hadj Ali et 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 Fillion et al.

Nuclear Engineering and Design, 2024, 421, pp.113035. ⟨10.1016/j.nucengdes.2024.113035⟩

Article dans une revue cea-04491875v1

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. Carnevali et al.

Nuclear Engineering and Design, 2023, 402, pp.112106. ⟨10.1016/j.nucengdes.2022.112106⟩

Article dans une revue cea-04452324v1
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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 Petruzzi et 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. Fillion et al.

Nuclear Engineering and Design, 2020, 366, pp.110731. ⟨10.1016/j.nucengdes.2020.110731⟩

Article dans une revue cea-04384302v1
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Development of good practice guidance for quantification of thermal-hydraulic code model input uncertainty

J. Baccou , J. Zhang , P. Fillion , G. Damblin , A. Petruzzi et 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
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NEPTUNE: a new software platform for advanced nuclear thermal hydraulics

Antoine Guelfi , Dominique Bestion , Marc Boucker , Pascal Boudier , Philippe Fillion et al.

Nuclear Science and Engineering, 2007, 156 (3), pp.281-324. ⟨10.13182/NSE05-98⟩

Article dans une revue hal-01580126v1
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Experimental qualification of a PIV and two-dye LIF temperature field measurement system with the "filling box" 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
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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
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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
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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
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Application of SAPIUM guidelines to Input Uncertainty Quantification: the ATRIUM project

Alberto Ghione , Lucia Sargentini , Guillaume Damblin , Philippe Fillion , Jean Baccou et 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
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METERO-V and PRIUS experimental programs: complementary separate effects tests for core mixing validation

Philippe Fillion , Seok Kim , Clément Melin , Gilles Bernard-Michel , Benjamin Cariteau et 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

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 Kim et al.

NURETH-20, Aug 2023, Washington, D.C., United States. pp.1502-1515, ⟨10.13182/NURETH20-40676⟩

Communication dans un congrès cea-04390515v1
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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
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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
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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
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Qualification expérimentale d'un système de thermographie LIF-2D

Vincent Helfer , Clément Melin , Adrien Toutant , Gilles Bernard-Michel , Philippe Fillion et 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 Carnevali et 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 Carnevali et 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 Carnevali et 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
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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
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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
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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
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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 Mimouni et al.

Advances in Thermal Hydraulics 2020, Oct 2020, Palaiseau, France. pp.1105-1116

Communication dans un congrès cea-04221795v1
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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
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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 Parrinello et al.

ICAPP 2019 – International Congress on Advances in Nuclear Power Plants, May 2019, Juan-les-pins, France

Communication dans un congrès cea-04221858v1
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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
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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
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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 Petruzzi et 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
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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
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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
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SAPIUM a systematic approach for input uncertainty quantification

J. Baccou , D. Bestion , M. Couplet , G. Damblin , P. Fillion et al.

BEPU-2018, May 2018, Lucca, Italy

Communication dans un congrès cea-02338977v1
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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
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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
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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