Applicability of two-phase CFD to nuclear reactor thermalhydraulics and elaboration of Best Practice Guidelines
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Conference Proceeding
Critical flow prediction by system codes – Recent analyses made within the FONESYS network
Lanfredini, M., Bestion, D., D'Auria, F., Aksan, N., Fillion, P., Gaillard, P., Heo, J., Karppinen, I., Kim, K.D., Kurki, J., Liu, L., Shen, A., Vacher, J.-L., Wang, D.
Published in Nuclear engineering and design (01.09.2020)
Published in Nuclear engineering and design (01.09.2020)
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Hyperbolicity and numerics in SYS-TH codes: The FONESYS point of view
Ahn, S.H., Aksan, N., Austregesilo, H., Bestion, D., Chung, B.D., Coscarelli, E., D'Auria, F., Emonot, P., Gandrille, J.L., Sauvage, J.Y., Hanninen, M., Horvatović, I., Kim, K.D., Kovtonyuk, A., Lutsanych, S., Petruzzi, A.
Published in Nuclear engineering and design (01.10.2017)
Published in Nuclear engineering and design (01.10.2017)
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FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics
Ahn, S.H., Aksan, N., Austregesilo, H., Bestion, D., Chung, B.D., D’Auria, F., Emonot, P., Gandrille, J.L., Hanninen, M., Horvatović, I., Kim, K.D., Kovtonyuk, A., Petruzzi, A.
Published in Nuclear engineering and design (01.01.2015)
Published in Nuclear engineering and design (01.01.2015)
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Modelling and computation of cavitation and boiling bubbly flows with the NEPTUNE_CFD code
Mimouni, S., Boucker, M., Laviéville, J., Guelfi, A., Bestion, D.
Published in Nuclear engineering and design (01.03.2008)
Published in Nuclear engineering and design (01.03.2008)
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An Overview of the Pressurized Thermal Shock Issue in the Context of the NURESIM Project
Lucas, D., Bestion, D., Bodèle, E., Coste, P., Scheuerer, M., D'Auria, F., Mazzini, D., Smith, B., Tiselj, I., Martin, A., Lakehal, D., Seynhaeve, J.-M., Kyrki-Rajamäki, R., Ilvonen, M., Macek, J.
Published in Science and technology of nuclear installations (01.01.2009)
Published in Science and technology of nuclear installations (01.01.2009)
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Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA)
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.
Published in Nuclear engineering and design (01.02.2005)
Published in Nuclear engineering and design (01.02.2005)
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Journal Article
Conference Proceeding
A Three-Dimensional Two-Fluid Modeling of Stratified Flow with Condensation for Pressurized Thermal Shock Investigations
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Journal Article
Conference Proceeding
Validation of NEPTUNE_CFD Module with Data of a Plunging Water Jet Entering a Free Surface
Galassi, M. C., Bestion, D., Morel, C., Pouvreau, J., D'Auria, F.
Published in Nuclear technology (01.07.2009)
Published in Nuclear technology (01.07.2009)
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Journal Article
Review of Available Data for Validation of Nuresim Two-Phase CFD Software Applied to CHF Investigations
Krepper, E., Lucas, D., Moretti, Fabio, Galassi, Maria Cristina, Macek, J., Vyskocil, L., Končar, Boštjan, Hazi, G., Bestion, Dominique, Ničeno, B., Andreani, M., Smith, B. L., Anglart, H., Caraghiaur, D., Péturaud, P.
Published in NURESIM (01.01.2009)
Published in NURESIM (01.01.2009)
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Journal Article
OECD/NEA/CSNI state-of-the-art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (The S-SOAR)
Mascari, F., D'Auria, F., Bestion, D., Lien, P., Nakamura, H., Austregesilo, H., Moon, S.K., Reventos, F., Umminger, K., Reyes, J.N., Rohatgi, U.S.
Published in Nuclear engineering and design (01.01.2024)
Published in Nuclear engineering and design (01.01.2024)
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Journal Article
TPTF horizontal flow prediction by SYS-TH codes – Recent analyses made within the FONESYS network
Lanfredini, M., Bestion, D., D'Auria, F., Aydemir, N., Carnevali, S., Fillion, P., Gaillard, P., Jeong, J.J., Junk, M., Karppinen, I., Kim, K.D., Kurki, J., Lee, J.H., Schoeffel, P., Sha, H., Skorek, T., Vacher, J.L., Waddington, G.
Published in Nuclear engineering and design (01.02.2023)
Published in Nuclear engineering and design (01.02.2023)
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