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Jacopo Buongiorno

Jacopo Buongiorno

TEPCO Professor and Associate Department Head, Nuclear Science and Engineering
Director, Center for Advanced Nuclear Energy Systems (CANES)

Consortium for Advanced Simulation of Light Water Reactors (CASL)
The Offshore Floating Nuclear Plant (OFNP) concept
Reactor Thermal-Hydraulics Laboratory Overview slideshow


Jacopo Buongiorno is the TEPCO Professor and Associate Department Head of Nuclear Science and Engineering at the Massachusetts Institute of Technology (MIT), where he teaches a variety of undergraduate and graduate courses in thermo-fluids engineering and nuclear reactor engineering. Buongiorno has published over 70 journal articles in the areas of reactor safety and design, two-phase flow and heat transfer, and nanofluid technology. For his research work and his teaching at MIT he won several awards, including, recently, the Ruth and Joel Spira Award (MIT, 2015), and the Landis Young Member Engineering Achievement Award (American Nuclear Society, 2011). He is the Director of the Center for Advanced Energy Systems (CANES), which is one of eight Low-Carbon-Energy Centers (LCEC) of the MIT Energy initiative (MITEI), as well as the Director of the MIT study on the Future of Nuclear Energy in a Carbon-Constrained World. Buongiorno is a consultant for the nuclear industry in the area of reactor thermal-hydraulics, and a member of the Accrediting Board of the National Academy of Nuclear Training. He is also a member of the Naval Studies Board (National Academies of Sciences, Engineering, and Medicine), the American Nuclear Society (including service on its Special Committee on Fukushima in 2011–2012), the American Society of Mechanical Engineers, and a participant in the Defense Science Study Group (2014–2015).


  • Ruth and Joel Spira Award for Distinguished Teaching, School of Engineering, 2006, 2011 and 2015.
  • MacVicar Faculty Fellow for exemplary and sustained contributions to the teaching and education of undergraduates at MIT, March 2014
  • Best Paper Award at the 9th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9) in Kaohsiung, Taiwan on September 9-13, 2012 (G. DeWitt, T. McKrell, J. Buongiorno, L.W. Hu and R. J. Park, "Experimental Study of Critical Heat Flux with Alumina-water Nanofluids in Downward-Facing Channels for In-Vessel Retention Applications”, Paper N9P0148).
  • Landis Young Member Engineering Achievement Award, American Nuclear Society, 2011.
  • ASME Heat Transfer Division Best Paper, 2008.
  • Best Paper Award at the 1st ASME Micro/Nanoscale Heat Transfer International Conference, Tainan, Taiwan, January 6-9, 2008.
  • Junior Bose Award for Excellence in Teaching, School of Engineering, 2007.
  • Mark Mills Award for best U.S. PhD Thesis in Nuclear Engineering, American Nuclear Society, 2001


Research Interests

Multi-phase flow and heat transfer; advanced reactor design; reactor thermal-hydraulics and safety. My current research is focused in four areas.

The offshore floating nuclear power plant

We are developing an offshore floating nuclear power plant concept that achieves unprecedented levels of safety. It does so through innovative design features that ensure indefinite cooling of the nuclear fuel (thus reducing the likelihood of accidents with fuel damage and radionuclide release), and eliminate the need for land evacuation, should such an accident actually occur. Both features are responsive to the new safety imperatives of a post-Fukushima world. This is a plant that can be entirely built (and decommissioned) as a floating rig in a shipyard, floated to the operating site (within 8–15 km of the coast), anchored in relatively deep water (i.e., ~100 m), and connected to the grid via an underwater transmission line. The economic potential is high, owing to efficient shipyard construction and decommissioning, and elimination of concrete structures from the plant design.
VIDEO: The Offshore Floating Nuclear Plant (OFNP) concept

Fundamentals of Boiling

Cutting edge experimental techniques are used to study the physics of two-phase flow and heat transfer phenomena, in particular nucleate boiling, Critical Heat Flux (CHF) and quenching heat transfer. The group has optimized the use of synchronized infra-red thermography, high-speed video and Particle Image Velocimetry (PIV) to obtain detailed data for temperature distribution on the boiling surface, bubble departure diameter and frequency, growth and wait times, nucleation site density, near-wall void fraction, etc.. These data can be used to inform and validate models of boiling heat transfer, CHF and quenching, including multi-phase Computational Fluid Dynamics (CFD), and specifically Interface Tracking Methods (ITM). With such methods the geometry of the vapor-liquid interface is not assumed (e.g., bullet-shaped bubbles), but actually calculated from ‘first principles’.

Surface effects on boiling heat transfer

It is well known that boiling and quenching heat transfer depends strongly on the morphology and composition of the solid surface through which the heat transfer occurs. The relevant surface features are roughness, wettability (hydrophilicity), porosity, presence of cavities, size and shape of cavities, and thermo-physical properties of the surface material. My work has been exploring the separate effects of surface roughness, wettability and porosity on both Critical Heat Flux (CHF) and quenching heat transfer (Leidenfrost point temperature). This is made possible by the use of surfaces with engineered features (e.g. posts, coatings, nanoparticle layers) at the micro- and nano-scale, which enabled varying the surface roughness, wettability and porosity precisely and independently from each other. In fabricating the test surfaces, I work with Profs. Michael Rubner and Robert Cohen in DMSE and ChemE, respectively.

Nanofluids for Nuclear Applications

By seeding the nuclear reactor coolant with nanoparticles it is possible to enhance the rate at which energy is removed from the nuclear fuel under normal and accident conditions, thus improving the reactor’s economic and safety performance. The resulting particle-fluid system is called a ‘nanofluid’. We study the synthesis and behavior of nanofluids, including fundamentals of heat transfer, boiling phenomena and specifically the enhancement mechanisms for Critical Heat Flux (CHF) and quenching acceleration, which are relevant to the reactor application.


“In-situ treatment of metallic surfaces”, Provisional patent, Serial Number 61/153,411. United States Patent and TM Office. Filing date 18 February 2009. L. W. Hu, J. Buongiorno, B. Truong, H. Feldman

“Concentrated solar power system”, International Publication No. WO 2011/035232 March 24, 2011. US patent No. 9273883, Published March 1 , 2016 A. Slocum, J. Buongiorno, C. Forsberg, D. Codd, A. Paxson

“Hydrophobic Porous Coatings for Creation of Stable Vapor Films to Reduce Drag”, U.S. Application No.: 61/706401, Filing Date: September 27, 2012, M.I.T. Case No. 15825K, MIT Docket No.: 15825.113297, R. Cohen, M. Rubner, J. Buongiorno, H. O'Hanley, T. McKrell

“Nanoparticle Thin-Film Coatings for Enhancement of Boiling Heat Transfer”, U.S. Patent No. 8,701,927, April 2014. M. Rubner, J. Buongiorno, L.W. Hu, E. Forrest, E. Williamson, R. Cohen

“Surface Textures and Methods for Enhancing and Controlling Critical Heat Flux in Boiling on Surfaces”, U.S. Application No.: 62/187335, Filing Date: July 1, 2015, N. Dhillon, J. Buongiorno, K. Varanasi


Recent Publications

  1. G. Su, M. Bucci, J. Buongiorno, T. J. McKrell, “Transient boiling of water under exponentially escalating heat inputs.”, Int. J. Heat Mass Transfer, 96, 667-698, 2016.
  2. J. Buongiorno, J. Jurewicz, M. Golay, N. Todreas, “The Offshore Floating Nuclear Plant (OFNP) Concept”, Nuclear Technology,, 2016.
  3. N. Dhillon, J. Buongiorno, K. Varanasi, “Critical Heat Flux Maxima during Boiling Crisis on Textured Surfaces”, Nature Communications, DOI: 10.1038/ncomms924, 2015.
  4. E. Forrest, L. W. Hu, J. Buongiorno, T. McKrell,, “Convective Heat Transfer in a High Aspect Ratio Mini-Channel Heated on One Side”, ASME J. Heat Transfer, Vol. 138 / 021704, 2016.
  5. J. Yurko, J. Buongiorno, R. Youngblood, “Demonstration of Emulator-based Bayesian Calibration of Safety Analysis Codes: Theory and Formulation”, Science and Technology of Nuclear Installations, Vol. 2015, Article ID 839249, 17 pages, 2015.
  6. D. Langewisch, J. Buongiorno, “Prediction of Film Thickness, Bubble Velocity, and Pressure Drop for Capillary Slug Flow using a CFD-Generated Database”, Int. J. Heat Fluid Flow, 54, 250–257, 2015.
  7. D. Chatzikyriakou, J. Buongiorno, D. Caviezel, D. Lakehal, “DNS and LES of Turbulent Flow in a Closed Channel Featuring a Pattern of Hemispherical Roughness Elements”, Int. J. Heat Fluid Flow, 53, 29–43, 2015.
  8. E. A. Bates, A. Salazar, M. J. Driscoll, E. Baglietto, J. Buongiorno, “Plug Design for Deep Borehole Disposal of High-Level Nuclear Waste”, Nuclear Technology, 188(3), 280–291, 2014.
  9. J. Buongiorno, D. G. Cahill, C. H. Hidrovo, S. Moghaddam, A. J. Schmidt, L. Shi, “Micro- and Nanoscale Measurement Methods for Phase Change Heat Transfer on Planar and Structured Surfaces”, Nanoscale and Microscale Thermophysical Engineering, 18(3), 270–287, 2014.
  10. R. Azizian, E. Doroodchi, T. McKrell, J. Buongiorno, L.W. Hu, B. Moghtaderi, “Effect of Magnetic Field on Laminar Convective Heat Transfer of Magnetite Nanofluids”, Int. J. Heat Mass Transfer, 68, 94–109, 2014.
  11. J. Buongiorno, “Can Corrosion and CRUD actually Improve Safety Margins in LWRs?”, Annals of Nuclear Energy, Vol. 63, Pages 9–21, January 2014.

all publications (pdf)


22.06 Engineering of Nuclear Systems
2.005 Thermal-Fluids Engineering I
22.312 Engineering of Nuclear Reactors
22.313J Thermal Hydraulics in Power Technology


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Jacopo Buongiorno at IHS CERAWeek, 2016

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