Nuclear Engineering and Design

Journal: Nuclear Engineering and Design

Abbreviation

Nucl. eng. des.

Publisher

North-Holland

ISSN

0029-5493
1872-759X

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Publications1 - 10 of 14

Development of thermal fatigue damage in 1CrMoV rotor steel
Holdsworth, S. R.; Mazza, Edoardo; Binda, L.; et al. (2007)
Nuclear Engineering and Design
Investigations on mixing phenomena in single-phase flow in a T-junction geometry
Walker, C.; Simiano, M.; Zboray, R.; et al. (2009)
Nuclear Engineering and Design
Experiments at the mixing test facility ROCOM for benchmarking of CFD codes
Kliem, S.; Sühnel, T.; Rohde, U.; et al. (2008)
Nuclear Engineering and Design
Evolution of interfacial area concentration in a vertical air–water flow measured by wire-mesh sensors
Prasser, Horst-Michael (2007)
Nuclear Engineering and Design
Experimental and numerical studies of void fraction distribution in rectangular bubble columns
Krepper, Eckhard; Vanga, Brahma Nanda Reddy; Zaruba, Alexander; et al. (2007)
Nuclear Engineering and Design
Computational study of conjugate heat transfer in T-junctions
Kuhn, Simon; Braillard, Olivier; Niceno, Bojan; et al. (2010)
Nuclear Engineering and Design
CFD modelling of polydispersed bubbly two-phase flow around an obstacle
Krepper, Eckhard; Beyer, Matthias; Frank, Thomas; et al. (2009)
Nuclear Engineering and Design
Steam bubble condensation in sub-cooled water in case of co-current vertical pipe flow
Lucas, Dirk; Prasser, Horst-Michael (2007)
Nuclear Engineering and Design
Gas–liquid flow around an obstacle in a vertical pipe
Frank, Thomas; Prasser, Horst-Michael; Beyer, Mathias; et al. (2008)
Nuclear Engineering and Design
Comparison between wire-mesh sensors and conductive needle-probes for measurements of two-phase flow parameters
Manera, Annalisa; Ozar, Basar; Paranjape, Sidharth; et al. (2009)
Nuclear Engineering and Design
Measurements of two-phase flow parameters such as void-fraction, bubble velocities, and interfacial area density have been performed in an upwards air–water flow at atmospheric pressure by means of a four-tip needle-probe and a wire-mesh sensor. For the first time, a direct comparison between the two measuring techniques has been carried out. Both techniques are based on the measurement of the fluid conductivity. For void-fraction and velocity measurements, similarity exists between the two methodologies for signal analysis. A significantly different approach is followed, instead, for the estimation of the interfacial area concentration: while the evaluation based on the needle-probe signal is carried out by using projections of the gas–liquid interface velocity, the evaluation based on the wire-mesh signals consist in a full reconstruction of the bubbles interfaces. The comparison between the two techniques shows a good agreement.

Publications1 - 10 of 14

Journal: Nuclear Engineering and Design

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