Cited by 237Nuclear Engineering Thermal-HydraulicsFluid Dynamics and Heat TransferParticle Dynamics in Fluid Flows

Validation of CFD models for mono- and polydisperse air–water two-phase flows in pipes

Frank, Th., Zwart, P.J., Krepper, E., Prasser, H.-M., Lucas, D.·2008·Nuclear Engineering and Design

Integrity signals

Registry

Crossref · 10.1016/j.nucengdes.2007.02.056

Cites

8 of 8 references verified0 citation errors · 0 not checkable

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Claims other papers make about this one

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  • Frank et al. [264] proposed a generalized wall lubrication force coefficient that does not consider the pipe diameter as a geometry length scale.

    “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.”

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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.
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 › Engineering › Aerospace Engineering › Nuclear Engineering Thermal-Hydraulics
  • Physical Sciences › Engineering › Computational Mechanics › Fluid Dynamics and Heat Transfer
  • Physical Sciences › Engineering › Ocean Engineering › 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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