Organization / Localization: CEA Country: France Facility Description: Vertical cylindrical vessel of 100 m3 volume; internal structures. Test Identification: HM1 Series SA-Related Topics / Phenomena:Containment atmosphere mixing/He/air and He/Air/Steam Stratification mixing by horizontal diffuse buoyant jet.
Jet/plume interacting with flow obstruction Measured Parameters: Pressure, temperature, local He concentration Modelling: Governing equations: U-RANS, total energy equation, transport equation
for helium mass fraction.
Turbulence model: k-epsilon model
including buoyancy effects. Simulation Code: Open FOAM Experimental Research Program: OECD/NEA HYMERES Project
References: [1] S. Abe, E. Studer, M. Ishigaki, Y. Sibamoto, & T. Yonomoto. Stratification breakup by a diffuse buoyant jet: The MISTRA HM1-1 and 1-1bis experiments and their CFD analysis. Nuclear Engineering and Design, 331, 162–175 (2018). https://doi.org/10.1016/j.nucengdes.2018.01.050 IP/Copyright Situation: CEA
References: [1] OECD/NEA (SARNET). Resolving Complex Safety Relevant Issues Related to Hydrogen Release in Nuclear Power Plant Containments During a Postulated Severe Accident. 2018, OECD Publishing / SARNET report. IP/Copyright Situation: CEA
References: [1] OECD/NEA (SARNET). Resolving Complex Safety Relevant Issues Related to Hydrogen Release in Nuclear Power Plant Containments During a Postulated Severe Accident. 2018, OECD Publishing / SARNET report. IP/Copyright Situation: CEA
Organization / Localization: CEA Country: France Facility Description: Vertical cylindrical vessel of 100 m3 volume; internal structures. Test Identification: IMPIGS SA-Related Topics / Phenomena:Containment atmosphere mixing/He/Air/Steam Stratification mixing by diffuse steam jet from below Measured Parameters: Pressure, temperature, local He concentration Experimental Research Program: OECD/NEA SETH-2 Project
References: [1] NEA (2012), OECD/SETH-2 Project PANDA and MISTRA Experiments Final Summary Report: Investigation of Key Issues for the Simulation of Thermal-hydraulic Conditions in Water Reactor Containment, OECD Publishing, Paris
[2] D. Paladino, G. Mignot, R. Kapulla, R. Zboray, M. Andreani, I. Tkatschenko, E. Studer, and J. Brinster, ""OECD/SETH-2 Project: PANDA and MISTRA Experiments Addressing Key Safety Issues for Water Reactor Containment,"" in Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), Paper 106, Pisa, Italy, May 12–17, 2013 IP/Copyright Situation: CEA
Organization / Localization: CEA Country: France Facility Description: Vertical cylindrical vessel of 100 m3 volume; internal structures. Test Identification: INITIALA and INITIALS SA-Related Topics / Phenomena:Containment atmosphere mixing/He/Air/Steam Containment mixing by diffusion Measured Parameters: Pressure, temperature, local He concentration Modelling: Governing equations: Navier-Stokes equations, and scalar transport equation for the helium
mass fraction
Turbulence model: k-epsilon including buoyancy effects Simulation Code: CFX Experimental Research Program: OECD/NEA SETH-2 Project
References: [1] NEA (2012), OECD/SETH-2 Project PANDA and MISTRA Experiments Final Summary Report: Investigation of Key Issues for the Simulation of Thermal-hydraulic Conditions in Water Reactor Containment, OECD Publishing, Paris
[2] J. R. Hoyes, M. J. Ivings. CFD modelling of hydrogen stratification in enclosures: Model validation and application to PAR performance. Nuclear Engineering and Design, 310, 142–153 (2016). https://doi.org/10.1016/j.nucengdes.2016.08.036 IP/Copyright Situation: CEA
Organization / Localization: CEA Country: France Facility Description: Vertical cylindrical vessel of 100 m3 volume; empty space. Test Identification: ISP-47 SA-Related Topics / Phenomena:Jet release of steam/hydrogen, Entrainment by Jet/Plume, Thermal stratification, Gas stratification, Wall condensation, Natural circulation, Turbulent diffusion, Pressurisation Measured Parameters: Gas pressure, gas temperature, gas concentration,
velocity profile, condensation mass flow rates, wall temperature Modelling: State equation: real gas, or perfect gas
Condensation model: Max of Uchida and Gido Koeste correlation, Surface film model, Chilton-Colburn, Stefan's Law, Homogeneous equilibirum model, Nussel Theory + deterioration factor, among others.
Turbulence model: k-epsilon, Mixing length scale model Simulation Code: GOTHIC
ASTEC
CFX
COCOSYS
CONTAIN
DEFINE
FUMO
CFX
GASFLOW
KUPOL
MELCOR
TONUS Experimental Research Program: OECD/NEA International Standard Problem No 47
References: [1] NEA (2007), International Standard Problem: ISP-47 on Containment Thermal Hydraulics – Final Report, OECD Publishing, Paris
[2] E. Studer, J. P. Magnaud, F. Dabbene, and I. Tkatschenko, „International standard problem on containment thermal–hydraulics ISP47“, Nucl. Eng. Des., Bd. 237, Nr. 5, S. 536–551, März 2007, doi: 10.1016/j.nucengdes.2006.08.008. IP/Copyright Situation: CEA
Organization / Localization: CEA Country: France Facility Description: Vertical cylindrical vessel of 100 m3 volume; internal structures. Test Identification: LOWMA SA-Related Topics / Phenomena:Containment atmosphere mixing/He/Air Stratification mixing by air jet from below Measured Parameters: Pressure, temperature, local He concentration Simulation Code: CAST3M
CFX Experimental Research Program: OECD/NEA SETH-2 Project
References: [1] NEA (2012), OECD/SETH-2 Project PANDA and MISTRA Experiments Final Summary Report: Investigation of Key Issues for the Simulation of Thermal-hydraulic Conditions in Water Reactor Containment, OECD Publishing, Paris
[2] E. Studer, J. Brinster, I. Tkatschenko, G. Mignot, D. Paladino, and M. Andreani, ‘Interaction of a light gas stratified layer with an air jet coming from below: Large scale experiments and scaling issues’, Nuclear Engineering and Design, vol. 253, pp. 406–412, 2012.
[3] J. R. Hoyes, M. J. Ivings. CFD modelling of hydrogen stratification in enclosures: Model validation and application to PAR performance. Nuclear Engineering and Design, 310, 142–153 (2016). https://doi.org/10.1016/j.nucengdes.2016.08.036
[4] L. Ishay, G. Ziskind, A. Rashkovan, U. Bieder, and J. Brinster, ‘Simulation of LOWMA-3 MISTRA experiment’, in Proceedings of CFD4NRS conference, 2014. IP/Copyright Situation: CEA
Organization / Localization: CEA Country: France Facility Description: Vertical cylindrical vessel of 100 m3 volume; internal structures. Test Identification: LOWMS SA-Related Topics / Phenomena:Containment atmosphere mixing/He/Air/Steam Stratification mixing by steam jet from below Measured Parameters: Pressure, temperature, local He concentration Experimental Research Program: OECD/NEA SETH-2 Project
References: [1] NEA (2012), OECD/SETH-2 Project PANDA and MISTRA Experiments Final Summary Report: Investigation of Key Issues for the Simulation of Thermal-hydraulic Conditions in Water Reactor Containment, OECD Publishing, Paris
[2] D. Paladino, G. Mignot, R. Kapulla, R. Zboray, M. Andreani, I. Tkatschenko, E. Studer, and J. Brinster, ""OECD/SETH-2 Project: PANDA and MISTRA Experiments Addressing Key Safety Issues for Water Reactor Containment,"" in Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), Paper 106, Pisa, Italy, May 12–17, 2013 IP/Copyright Situation: CEA
References: [1] E. Studer, D. Abdo, S. Benteboula, G. Bernard-Michel, B. Cariteau, N. Coulon, F. Dabbene, Ph. Debesse, S. Koudriakov, C. Ledier, J.-P. Magnaud, O. Norvez, J.-L. Widloecher, A. Beccantini, S. Gounand, & J. Brinster. Challenges in Containment Thermal Hydraulics. Nuclear Technology, 206(9), 1361–1373 (2020). https://doi.org/10.1080/00295450.2020.1731406
[2] A. Bentaïb, J. Vendel, H. Simon, L. Blumenfeld, I. Tkatschenko, H. Paillère. Air-steam tests in the MISTRA facility: Experimental results and validation of the lumped-parameter/CFD TONUS code. ERMSAR 2005, European Review Meeting on Severe Accident Research, Aix-en-Provence, 14-16 novembre 2005, Rapport DSR 99
[3] C. Loiseau, S. Mimouni, and E. Studer, Numerical simulation of wall condensation and spray using the MISTRA experiments, Nuclear Engineering and Design, Vol. 402, 112111 (2023). IP/Copyright Situation: CEA
Organization / Localization: CEA Country: France Facility Description: Vertical cylindrical vessel of 100 m3 volume; internal structures. Test Identification: MERCO Series SA-Related Topics / Phenomena:Containment atmosphere mixing/He/Air/Steam Stratification mixing by heaters, coolers and spray operation (SAMG) Measured Parameters: Pressure, temperature, local He concentration Modelling: Species transport model for gas mixture
Turbulence model: k–epsilon including buoyancy effects.
Condensation models: wall and bulk condensation model developed at IBRAE RAN, Russia. Simulation Code: FLUENT
CFX Experimental Research Program: EU-ERCOSAM Project
References: [1] F. Dabbene, E. Studer, J. P. Magnaud, F. Merli, I. Tkatschenko, & N. Fedorova. ‘Experimental Activities on Stratification and Mixing of a Gas Mixture under the Conditions of a Severe Accident with Intervention of Mitigating Measures Performed in the ERCOSAM-SAMARA Project’, in International Congress on Advances in Nuclear Power Plants (ICAPP 15), Nice, France, May 3–6, 2015.
[2] A. S. Filippov, S. Y. Grigoryev, O. V. Tarasov, & T. A. Iudina. “CFD Simulation of PANDA and MISTRA Cooler Tests of ERCOSAM-SAMARA Project.” Proceedings of the 2014 22nd International Conference on Nuclear Engineering, Vol. 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, Prague, Czech Republic, July 7–11, 2014. V004T10A021. ASME. https://doi.org/10.1115/ICONE22-30557
[3] S. Kelm, J. Lehmkuhl, W. Jahn, & H.-J. Allelein. A comparative assessment of different experiments on buoyancy driven mixing processes by means of CFD. Annals of Nuclear Energy, 93, 50–57 (2016). https://doi.org/10.1016/j.anucene.2015.12.032 IP/Copyright Situation: CEA
Organization / Localization: CEA Country: France Facility Description: Vertical cylindrical vessel of 100 m3 volume; internal structures. Test Identification: NATHCO SA-Related Topics / Phenomena:Containment atmosphere mixing/He/Air/Steam Stratification mixing by natural convection flow Measured Parameters: Pressure, temperature, local He concentration Modelling: Governing equations: U-RANS, total energy equation, transport equation
for helium mass fraction.
Turbulence model: k–omega SST model
including buoyancy effects.
Radiative heat transfer: Monte Carlo, 200.000 photon histories Simulation Code: CFX
OpenFOAM Experimental Research Program: OECD/NEA SETH-2 Project
References: [1] NEA (2012), OECD/SETH-2 Project PANDA and MISTRA Experiments Final Summary Report: Investigation of Key Issues for the Simulation of Thermal-hydraulic Conditions in Water Reactor Containment, OECD Publishing, Paris
[2] S. Kelm, J. Lehmkuhl, W. Jahn, & H.-J. Allelein. A comparative assessment of different experiments on buoyancy driven mixing processes by means of CFD. Annals of Nuclear Energy, 93, 50–57 (2016). https://doi.org/10.1016/j.anucene.2015.12.032
[3] D.Abdo, J.Brinster, M.Cazanou, R.Tomassian, I.Tkatschenko, J.-L.Widloecher, OECD SETH II Project, Report for MISTRA NATHCO (27-10-2009 and 10-02-2010) Test, Tech.Rep., DEN/DANS/DM2S/SFME/LEEF /RT/10006/A, CEA, Saclay, France, 2010.
[4] M. Debevc, I. Kljenak. Simulation of Natural Convection Experiment Performed in MISTRA Containment Experimental Facility. In: Proceedings of the 22nd International Conference on Nuclear Engineering (ICONE-22), Prague, Czech Republic, 2014. IP/Copyright Situation: CEA
Organization / Localization: CEA Country: France Facility Description: Vertical cylindrical vessel of 100 m3 volume; internal structures. Test Identification: SPRAY SA-Related Topics / Phenomena:Containment atmosphere mixing/He/Air/Steam Stratification mixing by spray operation Measured Parameters: Pressure, temperature, local He concentration Simulation Code: COCOSYS
NEPTUNE CFD Experimental Research Program: OECD/NEA SETH-2 Project
References: [1] NEA (2012), OECD/SETH-2 Project PANDA and MISTRA Experiments Final Summary Report: Investigation of Key Issues for the Simulation of Thermal-hydraulic Conditions in Water Reactor Containment, OECD Publishing, Paris
[2] D. Paladino, G. Mignot, R. Kapulla, R. Zboray, M. Andreani, I. Tkatschenko, E. Studer, and J. Brinster, ""OECD/SETH-2 Project: PANDA and MISTRA Experiments Addressing Key Safety Issues for Water Reactor Containment,"" in Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), Paper 106, Pisa, Italy, May 12–17, 2013
[3] M. Povilaitis, & E. Urbonavičius. Simulation of MASPn Experiments in MISTRA Test Facility with COCOSYS Code. Science and Technology of Nuclear Installations, 2008, Article ID 896406 (2008). https://doi.org/10.1155/2008/896406
[4] C. Loiseau, S. Mimouni, and E. Studer, Numerical simulation of wall condensation and spray using the MISTRA experiments, Nuclear Engineering and Design, Vol. 402, 112111 (2023). IP/Copyright Situation: CEA
Organization / Localization: CEA Facility Description: Vertical cylindrical vessel of 100 m3 volume; internal structures. Test Identification: MM0, MM1 SA-Related Topics / Phenomena:Capability of a natural convection flow, induced by Passive Autocatalytic Recombiners (PAR) operation, to remobilize an accumulation of light gas trapped below Measured Parameters: Pressure, temperature, local He concentration Modelling: PAR operation: REKO-Direkt model (2-D mechanistic model) Simulation Code: CFX/REKO-DIREKT
CAST3M/TONUS Experimental Research Program: MITHYGENE project funded by the French Research Agency ANR and industrial partners (EDF, AREVA and Air Liquide)
References: [1] E. Studer, J. Alengry, D. Abdo, F. Dabbene, S. Kelm, J. Baggemann, E.-A. Reinecke, & H.-J. Allelein. Hydrogen mobilization by Passive Autocatalytic Recombiners. In: 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11), Gyeongju, South Korea, October 9–13, 2016.
Implemented as part of the Seaknot EU funded project (HORIZON-EURATOM-2021-NRT-01 under Grant Agreement No. 101060327) - WP2.6 UNIPI (2024-2026)