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Lanfredini M, Bestion D, D'Auria F, Aydemir N, Carnevali S, Fillion P, Gaillard P, Jeong J, Junk M, Karppinen I, Kim K, Kurki J, Lee J, Schoeffel P, Sha H, Skorek T, Vacher J, Waddington G. TPTF horizontal flow prediction by SYS-TH codes – Recent analyses made within the FONESYS network. Nuclear Engineering and Design 2023. [DOI: 10.1016/j.nucengdes.2022.112106] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/24/2022]
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D’Auria F, Bestion D. Nuclear Thermal-Hydraulic Phenomena: Bases and Challenges. NUCL TECHNOL 2022. [DOI: 10.1080/00295450.2021.1997059] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
Affiliation(s)
- F. D’Auria
- University of Pisa, DESTEC, GRNSPG-UNIPI, Pisa, Italy
| | - D. Bestion
- Retired expert, formerly at CEA, 22 Avenue de l’Europe, Saint Egreve 38120, France
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Lanfredini M, Bestion D, D'Auria F, Aksan N, Fillion P, Gaillard P, Heo J, Karppinen I, Kim K, Kurki J, Liu L, Shen A, Vacher JL, Wang D. Critical flow prediction by system codes – Recent analyses made within the FONESYS network. Nuclear Engineering and Design 2020. [DOI: 10.1016/j.nucengdes.2020.110731] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Galassi MC, Bestion D, Morel C, Pouvreau J, D’Auria F. Validation of NEPTUNE_CFD Module with Data of a Plunging Water Jet Entering a Free Surface. NUCL TECHNOL 2017. [DOI: 10.13182/nt09-a8851] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
| | - D. Bestion
- DEN/DER/SSTH - Commissariat à l’Energie Atomique, Grenoble, France
| | - C. Morel
- DEN/DER/SSTH - Commissariat à l’Energie Atomique, Grenoble, France
| | - J. Pouvreau
- DEN/DER/SSTH - Commissariat à l’Energie Atomique, Grenoble, France
| | - F. D’Auria
- F. D’AURIA DIMNP - Università di Pisa, Pisa, Italy
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Yao W, Bestion D, Coste P, Boucker M. A Three-Dimensional Two-Fluid Modeling of Stratified Flow with Condensation for Pressurized Thermal Shock Investigations. NUCL TECHNOL 2017. [DOI: 10.13182/nt05-a3665] [Citation(s) in RCA: 19] [Impact Index Per Article: 2.7] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- W. Yao
- Grenoble DEN/DTP/SMTH/LMDS, 17 rue des Martyrs, 38054 Grenoble, Cédex 9, France
| | - D. Bestion
- Grenoble DEN/DTP/SMTH/LMDS, 17 rue des Martyrs, 38054 Grenoble, Cédex 9, France
| | - P. Coste
- Grenoble DEN/DTP/SMTH/LMDS, 17 rue des Martyrs, 38054 Grenoble, Cédex 9, France
| | - M. Boucker
- Département Mécanique des Fluides et Transferts Thermiques 6, Quai Watier 75400 Chatou Cedex, France
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Bestion D. System thermalhydraulics for design basis accident analysis and simulation: Status of tools and methods and direction for future R&D. Nuclear Engineering and Design 2017. [DOI: 10.1016/j.nucengdes.2016.11.010] [Citation(s) in RCA: 18] [Impact Index Per Article: 2.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Perez J, Alpy N, Juhel D, Bestion D. CATHARE 2 simulations of steady state air/water tests performed in a 1:1 scale SFR sub-assembly mock-up. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2015.03.050] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Ahn S, Aksan N, Austregesilo H, Bestion D, Chung B, D’Auria F, Emonot P, Gandrille J, Hanninen M, Horvatović I, Kim K, Kovtonyuk A, Petruzzi A. FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics. Nuclear Engineering and Design 2015. [DOI: 10.1016/j.nucengdes.2014.12.001] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Lucas D, Bestion D, Coste P, Pouvreau J, Morel C, Martin A, Boucker M, Bodèle E, Schmidtke M, Scheuerer M, Smith B, Dhotre MT, Ničeno B, Galassi MC, Mazzini D, D'Auria F, Bartosiewicz Y, Seynhaeve JM, Tiselj I, Štrubelj L, Ilvonen M, Kyrki-Rajamäki R, Tanskanen V, Puustinen M, Laine J. Main results of the European project NURESIM on the CFD-modelling of two-phase Pressurized Thermal Shock (PTS). KERNTECHNIK 2013. [DOI: 10.3139/124.110041] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
The European Platform for NUclear REactor SIMulations, (NURESIM project 2005 – 2008) addressed the creation of a Common European Standard Software Platform for modelling, recording, and recovering computer data for nuclear reactors simulations. One work package of the project was dedicated to the analysis and improvement of CFD capabilities for the simulation of two-phase PTS problems. Some SB-LOCA scenarios lead to a situation in which the cold leg is partially or totally uncovered when the Emergency Core Cooling injection is activated. The resulting complex two phase flow can be divided in characteristic flow regions: the jet flow with a free surface between steam and water, the zone of jet impingement, the horizontal two-phase flow and the flow in the downcomer. Many phenomena have to be reflected in a simulation of each separate region, but also when the simulations are coupled reflecting the integral process which is required to predict the thermal loads at the RPV wall. After analyzing the experimental database available for CFD model development and validation and identifying shortcomings of the models different activities were dedicated to the simulation of single flow regions as well as the integral flow. Based on these experiences recommendations for the CFD-simulation of the two-phase PTS problem were obtained.
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Affiliation(s)
- D. Lucas
- Forschungszentrum Dresden-Rossendorf e.V. (FZD), Institute of Safety Research, P.O. Box 51 01 19, 01314 Dresden, Germany. E-mail:
| | - D. Bestion
- Commissariat à l'Énergie Atomique (CEA), Centre d'Études Nucléaires de Grenoble, 17 Rue des Martyrs, 38054 Grenoble, France
| | - P. Coste
- Commissariat à l'Énergie Atomique
| | | | | | | | | | - E. Bodèle
- Forschungszentrum Dresden-Rossendorf e.V
| | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | | - J. Laine
- Lappeenranta University of Technology
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Bestion D. Applicability of two-phase CFD to nuclear reactor thermalhydraulics and elaboration of Best Practice Guidelines. Nuclear Engineering and Design 2012. [DOI: 10.1016/j.nucengdes.2011.08.068] [Citation(s) in RCA: 48] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Bestion D. FROM THE DIRECT NUMERICAL SIMULATION TO SYSTEM CODES - PERSPECTIVE FOR THE MULTI-SCALE ANALYSIS OF LWR THERMALHYDRAULICS. Nuclear Engineering and Technology 2010. [DOI: 10.5516/net.2010.42.6.608] [Citation(s) in RCA: 13] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Mimouni S, Boucker M, Laviéville J, Guelfi A, Bestion D. Modelling and computation of cavitation and boiling bubbly flows with the NEPTUNE_CFD code. Nuclear Engineering and Design 2008. [DOI: 10.1016/j.nucengdes.2007.02.052] [Citation(s) in RCA: 51] [Impact Index Per Article: 3.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Scheuerer M, Heitsch M, Menter F, Egorov Y, Toth I, Bestion D, Pigny S, Paillere H, Martin A, Boucker M, Krepper E, Willemsen S, Muhlbauer P, Andreani M, Smith B, Karlsson R, Henriksson M, Hemstrom B, Karppinen I, Kimber G. Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA). Nuclear Engineering and Design 2005. [DOI: 10.1016/j.nucengdes.2004.08.049] [Citation(s) in RCA: 31] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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Bartak J, Bestion D, Haapalehto T. The top-down reflooding model in the CATHARE code. Nuclear Engineering and Design 1994. [DOI: 10.1016/0029-5493(94)90281-x] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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