Computational and experimental analysis of gas/liquid two-phase flow in rod bundles with mixing-vane spacer grids

Waite, Brian M.; Prasser, Horst-Michael; Podowski, Michael Z.

doi:10.1016/j.nucengdes.2019.110499

Title: Computational and experimental analysis of gas/liquid two-phase flow in rod bundles with mixing-vane spacer grids

Journal Article · 13 January 2020 · Nuclear Engineering and Design

DOI: https://doi.org/10.1016/j.nucengdes.2019.110499 · OSTI ID:1848131

Waite, Brian M. ^[1]; Prasser, Horst-Michael ^[2]; Podowski, Michael Z. ^[3]

Rensselaer Polytechnic Inst., Troy, NY (United States). Center for Multiphase Research; Rensselaer Polytechnic Inst., Troy, NY (United States)
Eidgenoessische Technische Hochschule (ETH), Zurich (Switzerland). Lab of Nuclear Energy Systems
Rensselaer Polytechnic Inst., Troy, NY (United States). Center for Multiphase Research

The existing evidence clearly shows that the physical phenomena governing gas/liquid two-phase flows are quite complicated even in the case of smooth conduits and simple geometries. Needless to say, the development of experimental, analytical and computational methods for predicting such flows in complex geometries is an even more complicated and challenging task. A configuration of interest to a broad range of industrial applications, including nuclear reactors, deals with the flow of two-phase mixture along the channels formed between narrow arrays of multiple parallel cylindrical elements (tubes or rods). The alignment of such elements is normally accomplished by installing spacer grids placed at regular distances along the flow. The presence of spacers actually affect flow conditions, including the velocity field, pressure drop, heat transfer and, in the case of two-phase flows, phase distribution. The objective of this article is to present a comparative analysis of the results of a combined experimental, theoretical, and computational study of phase distribution around and downstream from complex-geometry spacer grids with split-vane type mixing devices. The main emphasis has been given to the analysis of the effect of proper interpretation of the experimental data on the modeling consistency. The importance of the understanding of uncertainties and limitations associated with the results of multidimensional computer simulations performed using mechanistic modeling principles based on an average bubble size is also discussed.

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Research Organization:: Univ. of Michigan, Ann Arbor, MI (United States)

Sponsoring Organization:: USDOE; USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: NE0000663

OSTI ID:: 1848131

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: C Vol. 360; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (39)

Two-fluid model and hydrodynamic constitutive relations Ishii, M.; Mishima, K. Nuclear Engineering and Design, Vol. 82, Issue 2-3 https://doi.org/10.1016/0029-5493(84)90207-3	journal	October 1984
The analysis of virtual mass effects in two-phase flow Drew, D.; Cheng, L.; Lahey, R. T. International Journal of Multiphase Flow, Vol. 5, Issue 4 https://doi.org/10.1016/0301-9322(79)90023-5	journal	August 1979
Momentum and heat transfer in two-phase bubble flow—I. Theory Sato, Y.; Sadatomi, M.; Sekoguchi, K. International Journal of Multiphase Flow, Vol. 7, Issue 2 https://doi.org/10.1016/0301-9322(81)90003-3	journal	April 1981
3-D turbulence structure and phase distribution measurements in bubbly two-phase flows Wang, S. K.; Lee, S. J.; Jones, O. C. International Journal of Multiphase Flow, Vol. 13, Issue 3 https://doi.org/10.1016/0301-9322(87)90052-8	journal	May 1987
Transverse migration of single bubbles in simple shear flows Tomiyama, Akio; Tamai, Hidesada; Zun, Iztok Chemical Engineering Science, Vol. 57, Issue 11 https://doi.org/10.1016/S0009-2509(02)00085-4	journal	June 2002
A study of the performance of void fraction correlations used in the context of drift-flux two-phase flow models Coddington, Paul; Macian, Rafael Nuclear Engineering and Design, Vol. 215, Issue 3 https://doi.org/10.1016/S0029-5493(01)00503-9	journal	June 2002
CFD prediction of flow and phase distribution in fuel assemblies with spacers Anglart, H.; Nylund, O.; Kurul, N. Nuclear Engineering and Design, Vol. 177, Issue 1-3 https://doi.org/10.1016/S0029-5493(97)00195-7	journal	December 1997
Bubble size measurement using wire-mesh sensors Prasser, H. -M.; Scholz, D.; Zippe, C. Flow Measurement and Instrumentation, Vol. 12, Issue 4 https://doi.org/10.1016/S0955-5986(00)00046-7	journal	August 2001
Validation of CFD analysis for rod bundle flow test with vaned spacer grids Chen, Xi; Du, Sijia; Zhang, Yu Annals of Nuclear Energy, Vol. 109 https://doi.org/10.1016/j.anucene.2017.05.055	journal	November 2017
CFD evaluation of turbulence models for flow simulation of the fuel rod bundle with a spacer assembly Liu, C. C.; Ferng, Y. M.; Shih, C. K. Applied Thermal Engineering, Vol. 40 https://doi.org/10.1016/j.applthermaleng.2012.02.027	journal	July 2012
Comparison between wire-mesh sensor and ultra-fast X-ray tomograph for an air–water flow in a vertical pipe Prasser, H. -M.; Misawa, M.; Tiseanu, I. Flow Measurement and Instrumentation, Vol. 16, Issue 2-3 https://doi.org/10.1016/j.flowmeasinst.2005.02.003	journal	April 2005
Stereoscopic particle image velocimetry measurements of flow in a rod bundle with a spacer grid and mixing vanes at a low Reynolds number Nguyen, Thien; Hassan, Yassin International Journal of Heat and Fluid Flow, Vol. 67 https://doi.org/10.1016/j.ijheatfluidflow.2017.08.011	journal	October 2017
Space and energy-based turbulent scale-resolving simulations of flow in a 5 × 5 nuclear reactor core fuel assembly with a spacer grid Busco, Giacomo; Hassan, Yassin A. International Journal of Heat and Fluid Flow, Vol. 71 https://doi.org/10.1016/j.ijheatfluidflow.2018.04.003	journal	June 2018
Invariant analysis of the Reynolds stress tensor for a nuclear fuel assembly with spacer grid and split type vanes Busco, Giacomo; Merzari, Elia; Hassan, Yassin A. International Journal of Heat and Fluid Flow, Vol. 77 https://doi.org/10.1016/j.ijheatfluidflow.2019.04.006	journal	June 2019
Detached direct numerical simulations of turbulent two-phase bubbly channel flow Bolotnov, Igor A.; Jansen, Kenneth E.; Drew, Donald A. International Journal of Multiphase Flow, Vol. 37, Issue 6 https://doi.org/10.1016/j.ijmultiphaseflow.2011.03.002	journal	July 2011
On the role of the lateral lift force in poly-dispersed bubbly flows Lucas, D.; Tomiyama, A. International Journal of Multiphase Flow, Vol. 37, Issue 9 https://doi.org/10.1016/j.ijmultiphaseflow.2011.05.009	journal	November 2011
A study on large bubble motion and liquid film in vertical pipes and inclined narrow channels Behafarid, F.; Jansen, K. E.; Podowski, M. Z. International Journal of Multiphase Flow, Vol. 75 https://doi.org/10.1016/j.ijmultiphaseflow.2015.04.016	journal	October 2015
Phenomenological investigations on the turbulent flow structures in a rod bundle array with mixing devices Chang, Seok Kyu; Moon, Sang Ki; Baek, Won Pil Nuclear Engineering and Design, Vol. 238, Issue 3 https://doi.org/10.1016/j.nucengdes.2007.02.037	journal	March 2008
On the consistency of mechanistic multidimensional modeling of gas/liquid two-phase flows Podowski, M. Z. Nuclear Engineering and Design, Vol. 239, Issue 5 https://doi.org/10.1016/j.nucengdes.2008.10.022	journal	May 2009
Mechanistic multidimensional analysis of horizontal two-phase flows Tselishcheva, Elena A.; Antal, Steven P.; Podowski, Michael Z. Nuclear Engineering and Design, Vol. 240, Issue 2 https://doi.org/10.1016/j.nucengdes.2009.09.015	journal	February 2010
Single-phase cross-mixing measurements in a 4×4 rod bundle Ylönen, Arto; Bissels, Wilhelm-Martin; Prasser, Horst-Michael Nuclear Engineering and Design, Vol. 241, Issue 7 https://doi.org/10.1016/j.nucengdes.2011.04.014	journal	July 2011
Multidimensional analysis of fission gas transport following fuel element failure in sodium fast reactor Bolotnov, Igor A.; Antal, Steven P.; Jansen, Kenneth E. Nuclear Engineering and Design, Vol. 247 https://doi.org/10.1016/j.nucengdes.2012.02.004	journal	June 2012
Experimental benchmark data for PWR rod bundle with spacer-grids Dominguez-Ontiveros, Elvis E.; Hassan, Yassin A.; Conner, Michael E. Nuclear Engineering and Design, Vol. 253 https://doi.org/10.1016/j.nucengdes.2012.09.003	journal	December 2012
CFD simulation of turbulent flow in a rod bundle with spacer grids (MATIS-H) using STAR-CCM+ Cinosi, N.; Walker, S. P.; Bluck, M. J. Nuclear Engineering and Design, Vol. 279 https://doi.org/10.1016/j.nucengdes.2014.06.019	journal	November 2014
Interfacial force study on a single bubble in laminar and turbulent flows Feng, Jinyong; Bolotnov, Igor A. Nuclear Engineering and Design, Vol. 313 https://doi.org/10.1016/j.nucengdes.2016.12.034	journal	March 2017
Signal response of wire-mesh sensors to an idealized bubbly flow Prasser, Horst-Michael; Häfeli, Richard Nuclear Engineering and Design, Vol. 336 https://doi.org/10.1016/j.nucengdes.2017.04.016	journal	September 2018
Wire-mesh sensors: A review of methods and uncertainty in multiphase flows relative to other measurement techniques Tompkins, Casey; Prasser, Horst-Michael; Corradini, Michael Nuclear Engineering and Design, Vol. 337 https://doi.org/10.1016/j.nucengdes.2018.06.005	journal	October 2018
Is reactor multiphase thermal-hydraulics a mature field of engineering science? Podowski, Michael Z. Nuclear Engineering and Design, Vol. 345 https://doi.org/10.1016/j.nucengdes.2019.01.022	journal	April 2019
Understanding two-phase flow and boiling heat transfer: Challenges and paradoxes Podowski, Michael Z. Nuclear Engineering and Design, Vol. 354 https://doi.org/10.1016/j.nucengdes.2019.110185	journal	December 2019
Experiments on the lift and drag of spheres suspended in a Poiseuille flow Eichhorn, R.; Small, S. Journal of Fluid Mechanics, Vol. 20, Issue 3 https://doi.org/10.1017/S0022112064001380	journal	November 1964
Three-dimensional fluid mechanics of particulate two-phase flows in U-bend and helical conduits Tiwari, Prashant; Antal, Steven P.; Podowski, Michael Z. Physics of Fluids, Vol. 18, Issue 4 https://doi.org/10.1063/1.2189212	journal	April 2006
A Pressure Drop Model for Spacer Grids with and without Flow Mixing Vanes Chun, Tae-Hyun; Oh, Dong-Seok Journal of Nuclear Science and Technology, Vol. 35, Issue 7 https://doi.org/10.1080/18811248.1998.9733899	journal	July 1998
Mapping of the Lateral Flow Field in Typical Subchannels of a Support Grid With Vanes McClusky, Heather L.; Holloway, Mary V.; Conover, Timothy A. Journal of Fluids Engineering, Vol. 125, Issue 6 https://doi.org/10.1115/1.1625688	journal	November 2003
The Effect of Support Grid Design on Azimuthal Variation in Heat Transfer Coefficient for Rod Bundles Holloway, Mary V.; Conover, Timothy A.; McClusky, Heather L. Journal of Heat Transfer, Vol. 127, Issue 6 https://doi.org/10.1115/1.1863274	journal	June 2005
The Rise of Bubbles in a Vertical Shear Flow Ervin, E. A.; Tryggvason, G. Journal of Fluids Engineering, Vol. 119, Issue 2 https://doi.org/10.1115/1.2819153	journal	June 1997
Average Volumetric Concentration in Two-Phase Flow Systems Zuber, N.; Findlay, J. A. Journal of Heat Transfer, Vol. 87, Issue 4 https://doi.org/10.1115/1.3689137	journal	November 1965
CFD Validation of Void Distribution in a Rod Bundle With Spacer Goodheart, Kevin; Ylönen, Arto; De Cacqueray, Victor 2014 22nd International Conference on Nuclear Engineering, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory https://doi.org/10.1115/ICONE22-30741	conference	November 2014
Coupled DNS/RANS Simulation of Fission Gas Discharge during Loss-of-Flow Accident in Generation IV Sodium Fast Reactor Behafarid, F.; Shaver, D.; Bolotnov, I. A. Nuclear Technology, Vol. 181, Issue 1 https://doi.org/10.13182/NT13-A15755	journal	January 2013
Heat Transfer, Carryover and fall back in Nuclear Steam Generators During Transients Liao, Lih-Yih; Parlos, Alex; Griffith, Peter Proceeding of International Heat Transfer Conference 8 https://doi.org/10.1615/IHTC8.3270	conference	January 2019

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Title: Computational and experimental analysis of gas/liquid two-phase flow in rod bundles with mixing-vane spacer grids

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