Network


Latest external collaboration on country level. Dive into details by clicking on the dots.

Hotspot


Dive into the research topics where Helmar Carl is active.

Publication


Featured researches published by Helmar Carl.


Kerntechnik | 2006

The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results

Horst-Michael Prasser; Matthias Beyer; Helmar Carl; Annalisa Manera; Heiko Pietruske; Peter Schütz; F.-P. Weiß

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.


Journal of Engineering for Gas Turbines and Power-transactions of The Asme | 2009

Air/Water Counter-Current Flow Experiments in a Model of the Hot Leg of a Pressurized Water Reactor

Christophe Vallée; Deendarlianto; Matthias Beyer; Dirk Lucas; Helmar Carl

Different scenarios of small break loss of coolant accident for pressurized water reactors (PWRs) lead to the reflux-condenser mode in which steam enters the hot leg from the reactor pressure vessel (RPV) and condenses in the steam generator. A limitation of the condensate backflow toward the RPV by the steam flowing in counter current could affect the core cooling and must be prevented. The simulation of counter-current flow limitation conditions, which is dominated by 3D effects, requires the use of a computational fluid dynamics (CFD) approach. These numerical methods are not yet mature, so dedicated experimental data are needed for validation purposes. In order to investigate the two-phase flow behavior in a complex reactor-typical geometry and to supply suitable data for CFD code validation, the “hot leg model” was built at Forschungszentrum Dresden-Rossendorf (FZD). This setup is devoted to optical measurement techniques, and therefore, a flat test-section design was chosen with a width of 50 mm. The test section outlines represent the hot leg of a German Konvoi PWR at a scale of 1:3 (i.e., 250 mm channel height). The test section is mounted between two separators, one simulating the RPV and the other is connected to the steam generator inlet chamber. The hot leg model is operated under pressure equilibrium in the pressure vessel of the TOPFLOW facility of FZD. The air/water experiments presented in this article focus on the flow structure observed in the region of the riser and of the steam generator inlet chamber at room temperature and pressures up to 3 bar. The performed high-speed observations show the evolution of the stratified interface and the distribution of the two-phase mixture (droplets and bubbles). The counter-current flow limitation was quantified using the variation in the water levels measured in the separators. A confrontation with the images indicates that the initiation of flooding coincides with the reversal of the flow in the horizontal part of the hot leg. Afterward, bigger waves are generated, which develop to slugs. Furthermore, the flooding points obtained from the experiments were compared with empirical correlations available in literature. A good overall agreement was obtained, while the zero penetration was found at lower values of the gaseous Wallis parameter compared with previous work. This deviation can be attributed to the rectangular cross section of the hot leg model.


Journal of Engineering for Gas Turbines and Power-transactions of The Asme | 2012

Erratum: "Air/Water Counter-Current Flow Experiments in a Model of the Hot Leg of a Pressurized Water Reactor" (Journal of Engineering for Gas Turbines and Power, 2009, 131(2), p. 022905)

Christophe Vallée; Deendarlianto; Matthias Beyer; Dirk Lucas; Helmar Carl

An error in the implementation into the test facility of the air flow meter used during the experiments was noticed after publication of the paper. As a consequence, the raw flow rates recorded by the digital data acquisition system with this flow meter are wrong. In order to correct the measured flow rates, a calibration curve was recorded with a certified rotameter. The obtained calibration points could be correlated in order to obtain the correction function applied to the raw measuring values. This resulted in the following modifications compared to the original paper: • p. 1, last two sentences of the Abstract: A good overall agreement was obtained, especially for the zero liquid penetration, while the slope of the CCFL characteristics was lower compared to previous work. This deviation may be attributed to the rectangular cross-section of the hot leg model. • p. 3, end of Sec. 3.1: (…) the air mass flow rate was varied between 0.23 and 0.41 kg/s.


Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition | 2008

Air/Water Counter-Current Flow Experiments in a Model of the Hot Leg of a Pressurised Water Reactor

Christophe Vallée; Deendarlianto; Matthias Beyer; Dirk Lucas; Helmar Carl

Different scenarios of small break Loss of Coolant Accident (LOCA) for pressurised water reactors (PWR) lead to the reflux-condenser mode in which steam enters the hot leg from the reactor pressure vessel (RPV) and condenses in the steam generator. A part of the condensate flows back towards the RPV in counter current to the steam. During the reflux-condenser mode, a counter-current flow limitation (CCFL) must be prevented because this would limit the core cooling. The simulation of CCFL conditions, which is dominated by 3D effects, requires the use of a computational fluid dynamics (CFD) approach. These methods are not yet mature and have to be validated before they can be applied to nuclear reactor safety. Therefore, dedicated experimental data is needed with high resolution in space and time. In order to investigate the two-phase flow behaviour in a complex reactor-typical geometry and to supply suitable data for CFD code validation, the “hot leg model” was built at Forschungszentrum Dresden-Rossendorf (FZD). This setup is devoted to optical measurement techniques, therefore, a flat test-section design was chosen with a width of 50 mm. The test-section outlines represent the hot leg of a German Konvoi PWR at a scale of 1:3, which corresponds to a channel height of 250 mm in the straight part of the hot leg. The test-section is mounted between two separators, one simulating the reactor pressure vessel and the other is connected to the steam generator inlet chamber. This allows to perform co-current as well as counter-current flow experiments. Moreover, the hot leg model is built in the pressure vessel of the TOPFLOW facility of FZD, which is used to perform high-pressure experiments under pressure equilibrium with the inside atmosphere of the vessel. Therefore, the test section can be designed with thin materials and equipped with big size windows like in the hot leg model. The presented air/water experiments focus on the flow structure observed in the region of the riser and of the steam generator inlet chamber at room temperature and pressures up to 3 bars. The performed high-speed observations show the evolution of the stratified interface and the distribution of the two-phase mixture (droplet and bubbles). Counter-current flow limitation, or the onset of flooding, was found by analysing the water levels measured in the separators. A confrontation with the images indicates that the initiation of flooding coincides with the reversal of the flow in the horizontal part of the hot leg due to high air velocities. Afterwards, bigger waves are generated, which develop to slugs. Furthermore, the CCFL data was compared with similar experiments and empirical correlations available in the literature. The agreement of the CCFL curve is good and indicate that the data is relevant for CFD validation purposes. The zero penetration was found at lower values of the Wallis parameter than in most of the previous work, which can be attributed to the rectangular geometry of the hot leg model.Copyright


Nuclear Engineering and Design | 2007

Evolution of the structure of a gas–liquid two-phase flow in a large vertical pipe

Horst-Michael Prasser; Matthias Beyer; Helmar Carl; Sabine Gregor; Dirk Lucas; Heiko Pietruske; Peter Schütz; Frank-Peter Weiss


Nuclear Engineering and Design | 2008

Erratum to “Experimental study on the air/water counter-current flow limitation in a model of the hot leg of a pressurized water reactor”

Deendarlianto; Christophe Vallée; Dirk Lucas; Matthias Beyer; Heiko Pietruske; Helmar Carl


Nuclear Engineering and Design | 2010

Experimental CFD grade data for stratified two-phase flows

Christophe Vallée; Dirk Lucas; Matthias Beyer; Heiko Pietruske; Peter Schütz; Helmar Carl


Nuclear Engineering and Design | 2008

Gas–liquid flow around an obstacle in a vertical pipe

Horst-Michael Prasser; Matthias Beyer; Thomas Frank; Suleiman Al Issa; Helmar Carl; Heiko Pietruske; Peter Schütz


Nuclear Engineering and Design | 2012

Counter-current flow limitation in a model of the hot leg of a PWR-Comparison between air/water and steam/water experiments

Christophe Vallée; Tobias Seidel; Dirk Lucas; Matthias Beyer; Horst-Michael Prasser; Heiko Pietruske; Peter Schütz; Helmar Carl


Archive | 2010

Betriebshandbuch für die Mehrzweck-Thermohydraulikversuchsanlage TOPFLOW

Peter Schütz; Heiko Pietruske; Stefan Lenk; Matthias Beyer; Helmar Carl

Collaboration


Dive into the Helmar Carl's collaboration.

Top Co-Authors

Avatar

Matthias Beyer

Helmholtz-Zentrum Dresden-Rossendorf

View shared research outputs
Top Co-Authors

Avatar

Heiko Pietruske

Helmholtz-Zentrum Dresden-Rossendorf

View shared research outputs
Top Co-Authors

Avatar

Peter Schütz

Helmholtz-Zentrum Dresden-Rossendorf

View shared research outputs
Top Co-Authors

Avatar

Dirk Lucas

Helmholtz-Zentrum Dresden-Rossendorf

View shared research outputs
Top Co-Authors

Avatar

Christophe Vallée

Helmholtz-Zentrum Dresden-Rossendorf

View shared research outputs
Top Co-Authors

Avatar
Top Co-Authors

Avatar

Frank-Peter Weiss

Helmholtz-Zentrum Dresden-Rossendorf

View shared research outputs
Top Co-Authors

Avatar
Top Co-Authors

Avatar

Tobias Seidel

Helmholtz-Zentrum Dresden-Rossendorf

View shared research outputs
Researchain Logo
Decentralizing Knowledge