Accéder directement au contenu

Philippe Fillion

33
Documents

Publications

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
NURETH-20, Aug 2023, Washington, D.C., United States. pp.1502-1515, ⟨10.13182/NURETH20-40676⟩
Communication dans un congrès cea-04390515v1
Image document

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
Image document

Application of SAPIUM guidelines to Input Uncertainty Quantification: the ATRIUM project

Alberto Ghione , Lucia Sargentini , Guillaume Damblin , Philippe Fillion , Jean Baccou
20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 20), American Nuclear Society, Aug 2023, Washington DC, United States
Communication dans un congrès cea-04191079v1
Image document

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
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
Image document

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
Image document

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
Image document

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

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
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
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
Image document

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
Image document

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

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
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

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
Advances in Thermal Hydraulics 2020, Oct 2020, Palaiseau, France. pp.1105-1116
Communication dans un congrès cea-04221795v1
Image document

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
Image document

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
Image document

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
ICAPP 2019 – International Congress on Advances in Nuclear Power Plants, May 2019, Juan-les-pins, France
Communication dans un congrès cea-04221858v1
Image document

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
Image document

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

Development of a systematic approach for quantification of thermal hydraulic code model input uncertainty

Jean Baccou , Jinzhao Zhang , Philippe Fillion , Guillaume Damblin , Alessandro Petruzzi
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
Image document

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
Image document

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
Image document

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
Image document

SAPIUM a systematic approach for input uncertainty quantification

J. Baccou , D. Bestion , M. Couplet , G. Damblin , P. Fillion
BEPU-2018, May 2018, Lucca, Italy
Communication dans un congrès cea-02338977v1
Image document

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
Image document

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
Image document

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

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
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
Nuclear Engineering and Design, 2023, 402, pp.112106. ⟨10.1016/j.nucengdes.2022.112106⟩
Article dans une revue cea-04452324v1

Critical flow prediction by system codes – Recent analyses made within the FONESYS network

M. Lanfredini , D. Bestion , F. d'Auria , N. Aksan , P. Fillion
Nuclear Engineering and Design, 2020, 366, pp.110731. ⟨10.1016/j.nucengdes.2020.110731⟩
Article dans une revue cea-04384302v1
Image document

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
Nuclear Science and Engineering, 2020, 194, pp.721-736. ⟨10.1080/00295639.2020.1759310⟩
Article dans une revue hal-03149294v1
Image document

Development of good practice guidance for quantification of thermal-hydraulic code model input uncertainty

J. Baccou , J. Zhang , P. Fillion , G. Damblin , A. Petruzzi
Nuclear Engineering and Design, 2019, 354, ⟨10.1016/j.nucengdes.2019.110173⟩
Article dans une revue hal-02530001v1
Image document

NEPTUNE: a new software platform for advanced nuclear thermal hydraulics

Antoine Guelfi , Dominique Bestion , Marc Boucker , Pascal Boudier , Philippe Fillion
Nuclear Science and Engineering, 2007, 156 (3), pp.281-324. ⟨10.13182/NSE05-98⟩
Article dans une revue hal-01580126v1