Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: HYMERES HP1 SA-Related Topics / Phenomena:Containment atmosphere mixing/Jet-plume interaction with flow obstructions; eroding of the stratified He layer Measured Parameters: Pressure, gas and wall temperature, helium concentration Modelling: Turbulence model: k-epsilon, RNG k-epsilon, k-omega SST.
Radiative heat transfer: No radiation, Discrete Ordinate method, Monte Carlo method. Simulation Code: FLUENT
CFD-ACE+
CFX
OpenFOAM
GOTHIC Experimental Research Program: OECD/NEA HYMERES Project
References: [1] M. Andreani, A. J. Gaikwad, S. Ganju, B. Gera, S. Y. Grigoryev, L. E. Herranz, R. Huhtanen, V. Kale, A. Kanaev, R. Kapulla, S. Kelm, J. Kim, T. Nishimura, D. Paladino, S. Paranjape, B. Schramm, M. Sharabi, F. Shen, B. Wei, D. Yan, & R. Zhang. Synthesis of a CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction. Nuclear Engineering and Design, 354, 110177 (2019). https://doi.org/10.1016/j.nucengdes.2019.110177
[2] 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.
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: HYMERES HP2 SA-Related Topics / Phenomena:Containment atmosphere mixing/One heat source interacting with flow obstruction on He distribution Measured Parameters: Pressure, gas and wall temperature, helium concentration Experimental Research Program: OECD/NEA HYMERES Project
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.
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: HYMERES HP3 SA-Related Topics / Phenomena:Containment atmosphere mixing/Two heat sources interacting with obstacles, He distribution Measured Parameters: Pressure, gas and wall temperature, helium concentration Experimental Research Program: OECD/NEA HYMERES Project
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.
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: HYMERES HP4 SA-Related Topics / Phenomena:Containment atmosphere mixing/Effect of spray and cooler on PWR containment Measured Parameters: Pressure, gas and wall temperature, helium concentration Experimental Research Program: OECD/NEA HYMERES Project
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.
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: HYMERES HP5 SA-Related Topics / Phenomena:Containment atmosphere mixing/Suppression pool water thermal stratification in BWR Measured Parameters: Pressure, gas and wall temperature, helium concentration Modelling: Turbulence model: k-omega BSL with low-Re corrections, k-epsilon realizable.
Effective Heat
Source (EHS) and Effective Momentum Source (EMS), EHS/EMS model for thermal stratification and mixing phenomena. Simulation Code: FLUENT Experimental Research Program: OECD/NEA HYMERES Project
References: [1] X. Wang, D. Grishchenko, & P. Kudinov. Pre-test analysis for definition of steam injection tests through multi-hole sparger in PANDA facility. Nuclear Engineering and Design, 386, 111573 (2022). https://doi.org/10.1016/j.nucengdes.2021.111573
[2] I. Gallego-Marcos, P. Kudinov, W. Villanueva, R. Kapulla, S. Paranjape, D. Paladino, J. Laine, M. Puustinen, A. Räsänen, L. Pyy, & E. Kotro. Pool stratification and mixing induced by steam injection through spargers: CFD modelling of the PPOOLEX and PANDA experiments. Nuclear Engineering and Design, 347, 67–85 (2019). https://doi.org/10.1016/j.nucengdes.2019.03.011
[3] 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.
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: HYMERES HP6 SA-Related Topics / Phenomena:Containment atmosphere mixing/Natural circulation induced by opening hatches Measured Parameters: Pressure, gas and wall temperature, helium concentration Simulation Code: LP & CFD Experimental Research Program: OECD/NEA HYMERES Project
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.
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: HYMERES-2 H2P1 SA-Related Topics / Phenomena:Containment atmosphere mixing/Jet/plume interacting with various obstructions Measured Parameters: Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities Modelling: Turbulence model: k-epsilon model
including buoyancy effects.
Radiative heat transfer: P-1 model Simulation Code: CUPID Experimental Research Program: OECD/NEA HYMERES-2 Project
References: [1] D. Paladino, R. Kapulla, S. Paranjape, S. Suter, & M. Andreani. PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena. Nuclear Engineering and Design, 392, 111777 (2022). https://doi.org/10.1016/j.nucengdes.2022.111777
[2] J. H. Sohn, Y. J. Cho, & H. Y. Yoon. Analysis on helium stratification erosion by vertical steam jet using the CUPID code. Nuclear Engineering and Design, 388, 111643 (2022). https://doi.org/10.1016/j.nucengdes.2021.111643
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: HYMERES-2 H2P2 SA-Related Topics / Phenomena:Containment atmosphere mixing/Thermal radiation effect on gas distribution Measured Parameters: Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities Modelling: Turbulence model: URANS k-omega SST
including buoyancy effects.
Radiative heat transfer: P-1 model and Monte Carlo method Simulation Code: CABARET-SC1
ContainmentFOAM
FLUENT Experimental Research Program: OECD/NEA HYMERES-2 Project
References: [1] D. Paladino, R. Kapulla, S. Paranjape, S. Suter, & M. Andreani. PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena. Nuclear Engineering and Design, 392, 111777 (2022). https://doi.org/10.1016/j.nucengdes.2022.111777
[2] R. Kapulla, S. Paranjape, U. Doll, E. Kirkby, & D. Paladino. Experimental assessment of thermal radiation effects on containment atmospheres with varying steam content. Nuclear Engineering and Technology, 54(11), 4348–4358 (2022). https://doi.org/10.1016/j.net.2022.07.001
[3] V. Y. Glotov. Simulation of experiments on thermal radiation effect studying in a large-scale PANDA facility using the CABARET-SC1 code. Nuclear Engineering and Design, 419, 112967 (2024). https://doi.org/10.1016/j.nucengdes.2024.112967
[4] R. Kapulla, S. Kelm, U. Doll, X. Liu, S. Paranjape, & D. Paladino. Large-scale PANDA facility – radiation experiments and CFD calculations. Kerntechnik, 89(2), 202–217 (2024). https://doi.org/10.1515/kern-2023-0060
[5] A. Dehbi, R. Kapulla. CFD analyses of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheres. Nuclear Engineering and Design, 415, 112710 (2023). https://doi.org/10.1016/j.nucengdes.2023.112710
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: HYMERES-2 H2P3 SA-Related Topics / Phenomena:Containment atmosphere mixing/Thermal stratification in water pool with sparger Measured Parameters: Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities Modelling: Turbulence model: k-omega BSL with low-Re corrections, k-epsilon realizable.
Effective Heat
Source (EHS) and Effective Momentum Source (EMS), EHS/EMS model for thermal stratification and mixing phenomena. Simulation Code: FLUENT Experimental Research Program: OECD/NEA HYMERES-2 Project
References: [1] D. Paladino, R. Kapulla, S. Paranjape, S. Suter, & M. Andreani. PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena. Nuclear Engineering and Design, 392, 111777 (2022). https://doi.org/10.1016/j.nucengdes.2022.111777
[2] X. Wang, D. Grishchenko, & P. Kudinov. Pre-test analysis for definition of steam injection tests through multi-hole sparger in PANDA facility. Nuclear Engineering and Design, 386, 111573 (2022). https://doi.org/10.1016/j.nucengdes.2021.111573
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: HYMERES-2 H2P4 SA-Related Topics / Phenomena:Containment atmosphere mixing/BWR containment systems response with / without spray Measured Parameters: Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities Experimental Research Program: OECD/NEA HYMERES-2 Project
References: [1] D. Paladino, R. Kapulla, S. Paranjape, S. Suter, & M. Andreani. PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena. Nuclear Engineering and Design, 392, 111777 (2022). https://doi.org/10.1016/j.nucengdes.2022.111777
[2] A. Oliva, D. Paladino, S. Carnevali, S. Paranjape, D. Grishchenko, P. Kudinov, & S. Mimouni. Experimental Investigations Addressing Steam Release in the Water Pool Through a Multi-Hole Sparger and Spray Water Activation in the Gas Space. SSRN Electronic Journal (2025). https://doi.org/10.2139/ssrn.5127387
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: HYMERES-2 H2P5 SA-Related Topics / Phenomena:Containment atmosphere mixing/Spray nozzle ring Measured Parameters: Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities Simulation Code: GOTHIC Experimental Research Program: OECD/NEA HYMERES-2 Project
References: [1] D. Paladino, R. Kapulla, S. Paranjape, S. Suter, & M. Andreani. PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena. Nuclear Engineering and Design, 392, 111777 (2022). https://doi.org/10.1016/j.nucengdes.2022.111777
[2] C. Vázquez-Rodríguez, M. Andreani, G. Jiménez, R. Kapulla, S. Paranjape, J. M. Martín-Valdepeñas, & D. Paladino. Assessment of the depressurisation and mixing effects of two spray systems in the PANDA facility, Part II – Simulations using GOTHIC 8.3 (QA). Nuclear Engineering and Design, 403, 112120 (2023). https://doi.org/10.1016/j.nucengdes.2022.112120
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: HYMERES-2 H2P6 SA-Related Topics / Phenomena:Containment atmosphere mixing/Interacting pattern of coolers Measured Parameters: Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities Modelling: Turbulence model: URANS k-omega SST
including buoyancy effects.
Radiative heat transfer: P-1 model and Monte Carlo method Simulation Code: FLUENT Experimental Research Program: OECD/NEA HYMERES-2 Project
References: [1] D. Paladino, R. Kapulla, S. Paranjape, S. Suter, & M. Andreani. PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena. Nuclear Engineering and Design, 392, 111777 (2022). https://doi.org/10.1016/j.nucengdes.2022.111777
[2] A. Dehbi, R. Kapulla. CFD simulations of helium layer erosion in one PANDA vessel following cooler activation. Nuclear Engineering and Design, 422, 113154 (2024). https://doi.org/10.1016/j.nucengdes.2024.113154
[3] D. Paladino, R. Kapulla, S. Paranjape, S. Suter, C. Hug, M.-S. Chae, & M. Andreani. PANDA experimental database and further needs for containment analyses. Nuclear Engineering and Design, 404, 112173 (2023). https://doi.org/10.1016/j.nucengdes.2023.112173
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: PE1 SA-Related Topics / Phenomena:Containment atmosphere mixing/Atmosphere stratification and SAM effect: hollow cone spray Measured Parameters: Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities Modelling: State equation: ideal gas model.
Turbulence model: k-epsilon model
including buoyancy effects.
Radiative heat transfer: Discrete ordinate model. Simulation Code: FLUENT Experimental Research Program: ERCOSAM-SAMARA Project
References: [1] A. Filippov, S. Grigoryev, N. Drobyshevsky, A. Kiselev, A. Shyukin, T. Yudina, CMFD simulation of ERCOSAM PANDA spray tests PE1 and PE2, Nuclear Engineering and Design, Volume 299, 2016, Pages 81-94, ISSN 0029-5493, https://doi.org/10.1016/j.nucengdes.2015.10.013
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: PE2 SA-Related Topics / Phenomena:Containment atmosphere mixing/Atmosphere stratification and SAM effect: full cone spray Measured Parameters: Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities Modelling: State equation: ideal gas model.
Turbulence model: k-epsilon model
including buoyancy effects.
Condensation models: wall and bulk condensation model developed at IBRAE RAN, Russia.
Radiative heat transfer: Discrete ordinate model. Simulation Code: FLUENT Experimental Research Program: ERCOSAM-SAMARA Project
References: [1] A. Filippov, S. Grigoryev, N. Drobyshevsky, A. Kiselev, A. Shyukin, T. Yudina, CMFD simulation of ERCOSAM PANDA spray tests PE1 and PE2, Nuclear Engineering and Design, Volume 299, 2016, Pages 81-94, ISSN 0029-5493, https://doi.org/10.1016/j.nucengdes.2015.10.013
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: PE3 SA-Related Topics / Phenomena:Containment atmosphere mixing/Atmosphere stratification and SAM effect: cooler Measured Parameters: Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities 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 Experimental Research Program: ERCOSAM-SAMARA Project
References: [1] 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
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: PE4 SA-Related Topics / Phenomena:Containment atmosphere mixing/Atmosphere stratification and SAM effect: heater Measured Parameters: Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities Simulation Code: LP & CFD Experimental Research Program: ERCOSAM-SAMARA Project
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: PE5 SA-Related Topics / Phenomena:Containment atmosphere mixing/Atmosphere stratification and SAM effect: cooler Measured Parameters: Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities 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
GASFLOW Experimental Research Program: ERCOSAM-SAMARA Project
References: [1] 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
[2] Y. Li, P. Chen, & M. Zhou. Numerical simulation of containment thermal-hydraulics behavior for small modular reactor during Station Black Out severe accident. Nuclear Engineering and Design, 427, 113415 (2024). https://doi.org/10.1016/j.nucengdes.2024.113415
Organization / Localization: PSI Country: Switzerland Facility Description: One or two connected vessels of 90 m3. Test Identification: Test 1-25 SA-Related Topics / Phenomena:Gas mixing and distribution in LWR containments Measured Parameters: Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities Modelling: Turbulence model: k-epsilon, k-k1-omega, transitional SST. It
includes buoyancy effects. Simulation Code: FLUENT
GASFLOW
GOTHIC
CFX Experimental Research Program: OECD/SETH 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. Guo, J. Cai, H. Zhang, H. Yin, & X. Yang. Study of the distribution of steam plumes in the PANDA facility using CFD code. Nuclear Engineering and Design, 289, 81–91 (2015). https://doi.org/10.1016/j.nucengdes.2015.04.016
[3] D. Paladino, R. Kapulla, S. Paranjape, S. Suter, C. Hug, M.-S. Chae, & M. Andreani. PANDA experimental database and further needs for containment analyses. Nuclear Engineering and Design, 404, 112173 (2023). https://doi.org/10.1016/j.nucengdes.2023.11217
[4] M. Andreani, D. Paladino, T. George. Simulation of basic gas mixing tests with condensation in the PANDA facility using the GOTHIC code. Nuclear Engineering and Design, 240(6), 1528–1547 (2010). https://doi.org/10.1016/j.nucengdes.2010.02.021
[5] D. Paladino, M. Andreani, R. Zboray, & J. Dreier. Toward a CFD-grade database addressing LWR containment phenomena. Nuclear Engineering and Design, 253, 331–342 (2012). https://doi.org/10.1016/j.nucengdes.2011.08.064
Implemented as part of the Seaknot EU funded project (HORIZON-EURATOM-2021-NRT-01 under Grant Agreement No. 101060327) - WP2.6 UNIPI (2024-2026)