Passive systems like natural circulation (NC) loops can offer reliable and cost efficient alternatives to common active systems for decay heat removal in nuclear power plants. During the transition between stable single and stable two phase flows, instabilities e. g. flashing and geysering may occur in the riser due to low system pressure and saturation temperature conditions. These instabilities may cause severe stress to the system components. This paper presented some results of the study on the decay heat removal system based on natural circulation, performed on the open loop NC test facility GENEVA, built at TU Dresden in 2013. 16 probes were used to determine void fraction along the riser on nine different levels in high time and spatial resolution, and stability maps was created for riser with inner diameters of 20 mm and 38 mm and up to 85 kW evaporator power.
Skip Nav Destination
2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4590-5
PROCEEDINGS PAPER
Generic Experimental Investigations of Thermohydraulic Instabilities With Void Fraction Measurement at Natural Circulation Test Facility Geneva
Tim Cloppenborg,
Tim Cloppenborg
Technische Universität Dresden, Dresden, Germany
Search for other works by this author on:
Christoph Schuster,
Christoph Schuster
Technische Universität Dresden, Dresden, Germany
Search for other works by this author on:
Antonio Hurtado
Antonio Hurtado
Technische Universität Dresden, Dresden, Germany
Search for other works by this author on:
Tim Cloppenborg
Technische Universität Dresden, Dresden, Germany
Christoph Schuster
Technische Universität Dresden, Dresden, Germany
Antonio Hurtado
Technische Universität Dresden, Dresden, Germany
Paper No:
ICONE22-30380, V02AT09A049; 8 pages
Published Online:
November 17, 2014
Citation
Cloppenborg, T, Schuster, C, & Hurtado, A. "Generic Experimental Investigations of Thermohydraulic Instabilities With Void Fraction Measurement at Natural Circulation Test Facility Geneva." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 2A: Thermal Hydraulics. Prague, Czech Republic. July 7–11, 2014. V02AT09A049. ASME. https://doi.org/10.1115/ICONE22-30380
Download citation file:
7
Views
Related Proceedings Papers
Related Articles
Study of Thermodynamic Effect on the Mechanism of Flashing Flow Under Pressurized Hot Water by a Homogeneous Model
J. Fluids Eng (January,2022)
Computational Fluid Dynamics Modeling of Two-Phase Flow in an Adiabatic Capillary Tube
J. Thermal Sci. Eng. Appl (March,2015)
Heat Transfer Effects of a Longitudinal Vortex Embedded in a Turbulent Boundary Layer
J. Heat Transfer (February,1987)
Related Chapters
Completing the Picture
Air Engines: The History, Science, and Reality of the Perfect Engine
Experimental Characterization of a Cavitating Orifice
Proceedings of the 10th International Symposium on Cavitation (CAV2018)
Production Riser Life Extension – A Class Perspective
Ageing and Life Extension of Offshore Facilities