Philippe Fillion
13
Documents
Publications
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Application of SAPIUM guidelines to Input Uncertainty Quantification: the ATRIUM project20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 20), American Nuclear Society, Aug 2023, Washington DC, United States
Conference papers
cea-04191079v1
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Assessment of stratification and entrainment models in CATHARE 3 code against TPTF-H and Mantilla experimentsNURETH-19 - The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Mar 2022, Bruxelles (Conference virtuelle), Belgium
Conference papers
cea-03985842v1
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TPTF horizontal flow prediction by SYS-TH codes - Recent analyses made within the FONESYS networkThe 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Mar 2022, Brussels (online), Belgium. pp.35792
Conference papers
cea-04098083v1
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CATHARE-3 V2.1: The new industrial version of the CATHARE codeATH'20 - Advances in Thermal Hydraulics 2020, Oct 2020, Palaiseau, France. https://www.ans.org/pubs/proceedings/article-49142/
Conference papers
cea-04087378v1
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Analysis of flow in rod bundles with velocity and temperature radial dissymmetry using CATHARE-3ICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan-les-Pins, France. pp.1-8
Conference papers
hal-02380403v1
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Assessing the accuracy of energy turbulent diffusion dispersion correlation in a porous two-fluid model dedicated to PWR core simulations14emes Journees d'etudes des Milieux Poreux - JEMP 2018, Oct 2018, Nantes, France
Conference papers
cea-02339457v1
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Improved PWR LOCA simulations through refined core 3D simulations - An advanced 3D modelling and the associated METERO validation programNUTHOS-12 - 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety, Oct 2018, Qingdao, China
Conference papers
cea-04084545v1
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SAPIUM a systematic approach for input uncertainty quantificationBEPU-2018, May 2018, Lucca, Italy
Conference papers
cea-02338977v1
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3d core thermalhydraulic phenomena in pwr sblocas and iblocasNURETH-17, Sep 2017, Xian, China
Conference papers
hal-02433889v1
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Prediction of annular flows in vertical pipes with new correlations for the CATHARE-3 three-field model17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Sep 2017, Xi'An, China
Conference papers
cea-02434037v1
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SAPIUM: a generic framework for a practical and transparent quantification of thermal hydraulic code model input uncertaintyNuclear Science and Engineering, 2020, 194, pp.721-736. ⟨10.1080/00295639.2020.1759310⟩
Journal articles
hal-03149294v1
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Development of good practice guidance for quantification of thermal-hydraulic code model input uncertaintyNuclear Engineering and Design, 2019, 354, ⟨10.1016/j.nucengdes.2019.110173⟩
Journal articles
hal-02530001v1
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NEPTUNE: a new software platform for advanced nuclear thermal hydraulicsNuclear Science and Engineering, 2007, 156 (3), pp.281-324
Journal articles
hal-01580126v1
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