SADD - Severe accident database directory

DataBase Containment - Focus area 1: Combustible gases transport (2)

Facility Name	Test Identification	Measured Parameters	Modelling	Simulation Code	Experimental Research Program	Country
PANDA	PE3	Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities	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.	FLUENT	ERCOSAM-SAMARA Project	Switzerland
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
PANDA	PE5	Fluid and wall temperatures, absolute and differential pressures, flow rates, heater power, gas concentrations and flow velocities	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.	FLUENT GASFLOW	ERCOSAM-SAMARA Project	Switzerland
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

Containment atmosphere mixing/Atmosphere stratification and SAM effect: cooler