Dr Marco Colombo
School of Mechanical, Aerospace and Civil Engineering
Lecturer in Fluid Mechanics
Full contact details
School of Mechanical, Aerospace and Civil Engineering
D243
Sir Frederick Mappin Building
Mappin Street
Sheffield
S1 3JD
- Profile
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I am a Lecturer in Fluid Mechanics in the Department of Mechanical Engineering having joined at the end of 2021. I received a Bachelor of Science in Energy Engineering and a Master of Science in Nuclear Engineering from Politecnico di Milano, in Italy, where I also completed my PhD in 2013. Before joining the University of Sheffield, I was a postdoctoral researcher at the University of Leeds from 2013.
My research addresses mainly the development of computational models of the thermo-fluid dynamics of multiphase flows, with a specific focus on computational fluid dynamics and boiling flows. I am interested in nuclear thermal hydraulics and the prediction of boiling heat transfer, passive cooling and two-phase thermal hydraulic instabilities in reactor systems, and the fluid dynamics of bubbly flows in multiple devices. I currently hold an EPSRC Fellowship focused on the challenge of modelling multiple flow regimes and transition in gas-liquid flows.
- Research interests
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Multiphase gas-liquid flows
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Nuclear thermal hydraulics
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Boiling heat transfer
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Computational fluid dynamics
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Bubbly flows
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- Publications
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Journal articles
- Predicting mass transfer in liquid–liquid extraction columns. Processes, 10(5).
- Prediction of horizontal gas–liquid segregated flow regimes with an all flow regime multifluid model. Processes, 10(5).
- Study of nuclear reactor external vessel passive cooling using computational fluid dynamics. Nuclear Engineering and Design, 378.
- A generalized multiphase modelling approach for multiscale flows. Journal of Computational Physics, 436.
- Benchmarking of computational fluid dynamic models for bubbly flows. Nuclear Engineering and Design, 375.
- Development of a CFD – LES model for the dynamic analysis of the DYNASTY natural circulation loop. Chemical Engineering Science, 237.
- Computational modeling of microbubble coalescence and breakup using large eddy simulation and Lagrangian tracking. AIChE Journal, 66(11).
- Simulation of microbubble dynamics in turbulent channel flows. Flow, Turbulence and Combustion, 105(4), 1303-1324.
- Multi-fluid computational fluid dynamic predictions of turbulent bubbly flows using an elliptic-blending Reynolds stress turbulence closure. Frontiers in Energy Research, 8.
- Assessment of semi-mechanistic bubble departure diameter modelling for the CFD simulation of boiling flows. Nuclear Engineering and Design, 344, 15-27.
- Large eddy simulation of microbubble dispersion and flow field modulation in vertical channel flows. AIChE Journal, 65(4), 1325-1339.
- Influence of multiphase turbulence modelling on interfacial momentum transfer in two-fluid Eulerian-Eulerian CFD models of bubbly flows. Chemical Engineering Science, 195, 968-984.
- Large eddy simulation of microbubble transport in a turbulent horizontal channel flow. International Journal of Multiphase Flow, 94, 80-93.
- Accuracy of Eulerian–Eulerian, two-fluid CFD boiling models of subcooled boiling flows. International Journal of Heat and Mass Transfer, 103, 28-44.
- RANS simulation of bubble coalescence and break-up in bubbly two-phase flows. Chemical Engineering Science, 146, 207-225.
- Multiphase turbulence in bubbly flows: RANS simulations. International Journal of Multiphase Flow, 77, 222-243.
- CFD study of an air–water flow inside helically coiled pipes. Progress in Nuclear Energy, 85, 462-472.
- A scheme of correlation for frictional pressure drop in steam–water two-phase flow in helicoidal tubes. Chemical Engineering Science, 123, 460-473.
- Prediction of bubble departure in forced convection boiling: A mechanistic model. International Journal of Heat and Mass Transfer, 85, 135-146.
- Experimental and numerical study of the laminar flow in helically coiled pipes. Progress in Nuclear Energy, 76, 206-215.
- Experimental and theoretical studies on density wave instabilities in helically coiled tubes. International Journal of Heat and Mass Transfer, 68, 343-356.
- Time-domain linear and non-linear studies on density wave oscillations. Chemical Engineering Science, 81, 118-139.
- RELAP5/MOD3.3 study on density wave instabilities in single channel and two parallel channels. Progress in Nuclear Energy, 56, 15-23.
- Transfer function modelling of the Lead-cooled Fast Reactor (LFR) dynamics. Progress in Nuclear Energy, 52(8), 715-729.
Chapters
- CFD model development for two-phase flows, Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment (pp. 239-335). Elsevier
- Microbubbles coalescence during transport in vertical channel flows, Computer Aided Chemical Engineering (pp. 79-84). Elsevier
- Application of CFD modelling to external nuclear reactor vessel cooling, Computer Aided Chemical Engineering (pp. 1027-1032). Elsevier
- Large Eddy Simulation of Microbubble Transport in Vertical Channel Flows, Computer Aided Chemical Engineering (pp. 73-78). Elsevier
- CFD Simulation of Boiling Flows for Nuclear Reactor Thermal Hydraulic Applications, Computer Aided Chemical Engineering (pp. 445-450). Elsevier
- Multiscale Simulation of Bubbly Flows, Computer Aided Chemical Engineering (pp. 625-630). Elsevier
Conference proceedings papers
- View this article in WRRO Preliminary results of the experimental campaign conducted on the dynasty natural circulation loop.. 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19), 6 March 2022 - 11 March 2022.
- Turbulent heat transfer in nanoparticulate multiphase channel flows with a high prandtl number molten salt fluid. 6th International Conference on Particle-Based Methods. Fundamentals and Applications, PARTICLES 2019 (pp 691-701)
- Benchmarking of CFD modelling closures for two-phase turbulent bubbly flows. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 (pp 1569-1582)
- CFD prediction of natural convection during external reactor vessel cooling. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 (pp 5449-5462)
- Coupled calculations of bubble departure diameter and frequency from mechanistic principles for nucleate boiling applications. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 (pp 288-299)
- Microbubble coalescence and breakup in turbulent vertical channel flows. Proceeding of THMT-18. Turbulence Heat and Mass Transfer 9 Proceedings of the Ninth International Symposium On Turbulence Heat and Mass Transfer, 10 July 2018 - 13 July 2018.
- Assessment of semi-mechanistic bubble departure diameter modelling for the CFD simulation of boiling flows. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Vol. 2017-September
- CFD Simulation of boiling flows with an eulerian-eulerian two-fluid model. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Vol. 2017-September
- CFD study of two-phase flow in a helical tube. Transactions of the American Nuclear Society, Vol. 117 (pp 1768-1771)
- CFD simulation of single- and two-phase natural convection in the context of external reactor vessel cooling. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Vol. 2017-September
- Modelling of bubbly two-phase flows using a population balance approach. Proceeding of THMT-15. Proceedings of the Eighth International Symposium On Turbulence Heat and Mass Transfer, 15 September 2015 - 18 September 2015.
- Multiphase RANS simulation of turbulent bubbly flows. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, Vol. 4 (pp 2644-2657)
- Experimental characterization of pressure drops and channel instabilities in helical coil SG tubes. International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012, Vol. 4 (pp 2286-2295)
- Assessment of Different Turbulence Models in Helically Coiled Pipes Through Comparison With Experimental Data. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 30 July 2012 - 3 August 2012.
- Preliminary feasibility study of a water space reactor with an innovative reactivity control system. International Conference on the Physics of Reactors 2010, PHYSOR 2010, Vol. 2 (pp 1566-1576)
- Large eddy simulation for the modelling of the dynamic behaviour of the DYNASTY natural circulation loop.. 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19), 6 March 2022 - 11 March 2022.
- Hydrodynamics and mass transfer in multiscale multiphase flows: a novel CFD modelling approach.. 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19), 6 March 2022 - 11 March 2022.
- A Generalized Multifluid Modelling Approach (GEMMA): application to multiple flow regime phenomena in nuclear reactor thermal hydraulics.. 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19), 6 March 2022 - 11 March 2022.
- A novel generalized multiphase modelling approach for the simulation of multiphase flows: model development and validation. ETMM 13 Conference Proceedings. Rhodes, Greece, 15 September 2021 - 17 September 2021.
- A novel generalized multiphase modelling approach for the simulation of multiphase flows: application to intensified liquid-liquid extraction. ETMM 13 Conference Proceedings. Rhodes, Greece, 15 September 2021 - 17 September 2021.