The DOI matches its Crossref record; 8 of the 8 references it cites were found in a registry or an index.
Validation of CFD models for mono- and polydisperse air–water two-phase flows in pipes
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“Some of the deficiencies present in the formulations proposed by Antal and Tomiyama have been improved by Frank et al. [264], who proposed a generalized wall lubrication force coefficient that does not consider the pipe diameter as a geometry length scale.”
From Modeling and Simulation of Photobioreactors with Computational Fluid Dynamics—A Comprehensive Review (2022) · cites this paper as [264]
Citations
Cites
Theoretical model for drop and bubble breakup in turbulent dispersions
Luo, H., & Svendsen, H. F. (1996) · AIChE Journal · doi:10.1002/aic.690420505 · Cited by 1,250
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Prince, M. J., & Blanch, H. W. (1990) · AIChE Journal · doi:10.1002/aic.690361004 · Cited by 1,238
Analysis of phase distribution in fully developed laminar bubbly two-phase flow
Antal, S. P., Lahey, R. T., & Flaherty, J. E. (1991) · International Journal of Multiphase Flow · doi:10.1016/0301-9322(91)90029-3 · Cited by 878
Struggle with computational bubble dynamics
(1998) · Multiphase Science and Technology · doi:10.1615/multscientechn.v10.i4.40 · Cited by 663
Development of co-current air–water flow in a vertical pipe
Lucas, D., Krepper, E., & Prasser, H.-M. (2005) · International Journal of Multiphase Flow · doi:10.1016/j.ijmultiphaseflow.2005.07.004 · Cited by 194
Self-citationEvolution of the structure of a gas–liquid two-phase flow in a large vertical pipe
Prasser, H.-M., Beyer, M., Carl, H., Gregor, S., Lucas, D., Pietruske, H., Schütz, P., & Weiß, F.-P. (2007) · Nuclear Engineering and Design · doi:10.1016/j.nucengdes.2007.02.018 · Cited by 132
Self-citationCFD Best Practice Guidelines for CFD Code Validation for Reactor- Safety Applications
Menter, F. R., Hemström, B., Mühlbauer, P., Scheuerer, M., Smith, B., & Willemsen, S. (2002) · Cited by 122
A simplified method proposal for practical determination of aperiodic two-phase flow instability
Lorenzini, E. C. (1981) · International Journal of Multiphase Flow · doi:10.1016/0301-9322(81)90035-5 · Cited by 63
Flagged first, then by citations
Research works printed but not linked: 4
- Frank, Th., October 2003. Bubble flow in vertical pipes—investigation of the testcase VDL-01/1 (FZR-074) for the validation of CFD. ANSYS CFX Germany. Technical Report No. TR-03-09, pp. 34.
- Frank, Th., January 2006. Abschlußbericht zum Forschungsvorhaben 150 1271 “Entwicklung von CFD-Software zur Simulation mehrdimensionaler Strömungen im Reaktorkühlsystem”. Technical Report TR-06-01, ANSYS Germany, Otterfing, pp. 72.
- Prasser, H.-M., Lucas, D., Krepper, E., Baldauf, D., Böttger, A., Rohde, U., et al., June 2003. Strömungskarten und Modelle für transiente Zweiphasenströmungen. Forschungszentrum Rossendorf, Germany. Report No. FZR-379, pp. 183.
- Tomiyama, A., 2002. Single bubbles in stagnant liquids and in linear shear flows. Workshop on Measurement Technology (MTWS5), FZ Rossendorf, Dresden, Germany, pp. 3–19.
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Metadata
- Authors
- Frank, T., Zwart, P. J., Krepper, E., Prasser, H.-M., & Lucas, D.
- Affiliations
- Ansys (Germany) (DE)
- Ansys (Canada) (CA)
- Helmholtz-Zentrum Dresden-Rossendorf (DE)
- ETH Zurich (CH)
- Corresponding author
- Frank, Th.
- ORCID
- Venue
- Nuclear Engineering and Design
- Publisher
- Elsevier BV
- Published
- 2008-03
- Volume
- 238
- Issue
- 3
- Pages
- 647-659
- ISSN
- 0029-5493 (ISSN-L)
- OpenAlex
- W2046276638
- Cited by
- 237
- References
- 8
- Citations by year
- 2026: 13 · 2025: 11 · 2024: 10 · 2023: 16 · 2022: 16 · 2021: 15 · 2020: 20 · 2019: 15 · 2018: 21 · 2017: 20 · 2016: 15 · 2015: 12 · 2014: 12 · 2013: 9 · 2012: 9
- FWCI
- 10.68
- Type
- journal article
- Language
- en
- Open access
- closed
- Locations
- Nuclear Engineering and Design (publishedVersion)
- Topics
- Physical Sciences › Energy › Nuclear Energy and Engineering › Nuclear Engineering Thermal-Hydraulics
- Physical Sciences › Engineering › Computational Mechanics › Fluid Dynamics and Heat Transfer
- Physical Sciences › Chemical Engineering › Fluid Flow and Transfer Processes › Particle Dynamics in Fluid Flows
- Keywords
- multiphase flow simulation, air-water flow, Eulerian multiphase model, interphase momentum transfer, bubble size distribution, model validation, nuclear reactor safety, pipe flow
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