Modeling single-phase transverse flows in a PWR rod bundle at low Reynolds number

Autor: Fu, Qinjun, Bergeron, André, Fillion, Philippe, Davit, Yohan, Quintard, Michel

Publikováno v: In Nuclear Engineering and Design January 2024 416

Assessment of stratification and entrainment models in CATHARE 3 code against TPTF-H and Mantilla experiments

Autor: Carnevali, Sofia, Fillion, Philippe

Publikováno v: NURETH-19-The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
NURETH-19-The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Mar 2022, Bruxelles (Conference virtuelle), Belgium

International audience; This paper presents the assessment of CATHARE 3 code against tests performed in the horizontal TPTF (Two Phase Tests Facility) and Mantilla facilities. This activity falls within the framework of a benchmark conducted by the F

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=od______3515::36c8bf979df2cc29cf47289cff49d237
https://cea.hal.science/cea-03985842/document

CATHARE-3 V2.1: The new industrial version of the CATHARE code

Autor: Préa, Raphaël, Fillion, Philippe, Matteo, Laura, Mauger, Gédéon, Mekkas, Anouar

Publikováno v: ATH'20-Advances in Thermal Hydraulics 2020
ATH'20-Advances in Thermal Hydraulics 2020, Oct 2020, Palaiseau, France. https://www.ans.org/pubs/proceedings/article-49142/

International audience; CATHARE-3 is the new version of the French thermal-hydraulic code for the safety analysis of nuclear reactors; its development has begun in 2006 as part of the NEPTUNE project launched by the CEA, EDF, AREVA-NP and IRSN in 200

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=od______3515::84bfbfff91ce31b38950b33ff4174034
https://cea.hal.science/cea-04087378/document

Analysis of flow in rod bundles with velocity and temperature radial dissymmetry using CATHARE-3

Autor: Fu, Qinjun, Bestion, Dominique, Fillion, Philippe, Davit, Yohan, Quintard, Michel

Publikováno v: ICAPP 2019-International Congress on Advances in Nuclear Power Plants
ICAPP 2019-International Congress on Advances in Nuclear Power Plants, May 2019, Juan-les-Pins, France. pp.1-8
ICAPP 2019 International Congress on Advances in Nuclear Power Plants
ICAPP 2019 International Congress on Advances in Nuclear Power Plants, May 2019, Juan-Les-Pins, France

International audience; CATHARE is a 2-fluid thermal-hydraulic system code, capable of simulating phenomena occurring in the primary and secondary circuits of a PWR (Pressurized Water Reactor) under a wide variety of accidental situations. The latest

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::7076502414ca07fbf8da962e5d75932d
https://oatao.univ-toulouse.fr/23982/

Analysis of the NUPEC PSBT Tests with FLICA-OVAP.

Autor: Bucci, Matteo¹, Fillion, Philippe¹ philippe.fillion@cea.fr

Publikováno v: Science & Technology of Nuclear Installations. 2012, p1-18. 18p.