Dr Marco Colombo
Department of Mechanical Engineering
Lecturer in Fluid Mechanics
Full contact details
Department of Mechanical Engineering
D243
Sir Frederick Mappin Building
Mappin Street
Sheffield
S1 3JD
- Profile
-
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
-
-
Multiphase gas-liquid flows
-
Nuclear thermal hydraulics
-
Boiling heat transfer
-
Computational fluid dynamics
-
Bubbly flows
-
- Publications
-
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.