The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results
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H.-M. Prasser
Abstract
A new multipurpose thermalhydraulic test facility TOPFLOW (TwO Phase FLOW) was built and put into operation at Forschungszentrum Rossendorf in 2002 and 2003. Since then, it has been mainly used for the investigation of generic and applied steady state and transient two phase flow phenomena and the development and validation of models of Computational Fluid Dynamic (CFD) codes in the frame of the German CFD initiative. The advantage of TOPFLOW consists in the combination of a large scale of the test channels with a wide operational range both of the flow velocities as well as of the system pressures and temperatures plus finally the availability of a special instrumentation that is capable in high spatial and temporal resolving two phase flow phenomena, for example the wire-mesh sensors.
Kurzfassung
Eine neue Mehrzweck-Thermohydraulikversuchsanlage TOPFLOW wurde in den Jahren 2002 und 2003 im Forschungszentrum Rossendorf errichtet und in Betrieb genommen. Seitdem wird sie hauptsächlich zur Untersuchung stationärer und transienter Phänomene in Zweiphasenströmungen und zur Entwicklung und Validierung der in Computational Fluid Dynamic (CFD) Codes enthaltenen Modellen im Rahmen der deutschen CFD Initiative genutzt. Die großmaßstäblichen Testsektionen, der breite Parameterbereich bei den einstellbaren Strömungsgeschwindigkeiten, Drücken und Temperaturen und schließlich die Verwendung von räumlich und zeitlich hochauflösender Spezialmesstechnik zur Erfassung der Phänomene in Zweiphasenströmungen, beispielsweise Gittersensoren, sind die Vorzüge von TOPFLOW.
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© 2006, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results
- Uncertainty in cross-section calculations for reactions induced by neutrons with energy above 0.1 MeV
- Determination of the exposure build-up factor in a slab using the LTSN method
- Lumped parameters analysis of the IAEA research reactor benchmark problem
- Assessment of the look-up table using the tubular and bundle CHF data and modification of the bundle correction factor
- A finite element model for static strength analysis of CANDU fuel bundle
- Effect of packing fraction variations on the multiplication factor in pebble-bed nuclear reactors
- Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects
- Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant
- Analyses of severe accident scenarios in RBMK-1500
