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Michael P. Short

Michael Short

Assistant Professor of Nuclear Science and Engineering

Short Lab
H.H. Uhlig Corrosion Laboratory



  • B.S., Nuclear Science and Engineering, MIT, 2005
  • B.S., Materials Science and Engineering, MIT, 2005
  • M.S., Materials Science and Engineering, MIT, 2010
  • Ph.D., Nuclear Science and Engineering, MIT, 2010


  • Earll S. Murman Award for Excellence in Undergraduate Advising, MIT, 2016
  • Ruth and Joel Spira Award for Excellence in Mentoring and Advising, MIT 2016
  • Best Poster — 1st annual MIT NSE Research Expo, MIT, Cambridge, MA, 2010
  • Best Nuclear Energy Presentation — 2nd Tokyo Tech MERCES Forum, Okinawa, Japan, 2009
  • Best Graduate Paper — Bodycote 2009 Paper Prize Competition, Köln, Germany

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Multiphysics, Multiscale Modeling of Corrosion Deposits (CRUD) in PWRs

Soluble and particulate species present in the coolant of light water nuclear reactors can deposit on the surfaces of fuel rods, due to a phenomenon known as sub-cooled boiling. These deposits, known as 'CRUD' (a technical term), can lead to three major problems in reactors: an axial power shift, accelerated corrosion of the fuel cladding, and increased worker dose. The power shift can lead to a mandatory derating of the plant. A new model, MAMBA-BDM, is being developed to study how CRUD forms using a multiphysics, multiscale, fully coupled approach, where no approximations or 'fudge factors' are used to understand how CRUD forms from first-principles.

Imparting Deposition Resistance to High Heat Flux Surfaces

The deposition of corrosion products (see CRUD above) is a serious problem in areas that require high heat transfer and fluid flow to keep cool. These include reactor fuel rods, steam generators, and compact heat exchanger designs like printed circuit heat exchangers (PCHEs). Synergistic atomistic simulations, multiphysics models, and experiments are being proposed to find ways to impart deposition resistance to these surfaces. It is believed that the electronic structure of the surface is the key, and techniques such as plasma ion implantation, gas ion nitriding, and electro-implantation are being studied to stop deposition products from forming altogether.

Composite Alloys for Increasing Fuel Performance of Next-Generation Reactors

The era when a single alloy or material can solve all the problems related to strength, ductility, corrosion resistance, and radiation resistance in some extreme environments is ending. New reactor concepts push the outlet temperatures, the material dose, and the lifetimes of reactor materials to extremes beyond the reach of single alloys. A composite approach is therefore necessary, to combine the best properties of each constituent material without degrading the system as a whole or at its interfaces. Steel composites have been developed at MIT to achieve both high strength and corrosion resistance in liquid lead-bismuth up to 715C, and similar efforts are underway for liquid sodium.


Provisional Patent Application #61/600,128: “Method for Improving Deposition (CRUD) Resistance of Nuclear Fuel Cladding and Components” (filed 2012)


Selected Publications

Short, M. P., Gaston, D., Jin, M., Shao, L., Garner, F. A. "Modeling injected interstitial effects on void swelling in self-ion irradiation experiments." J. Nucl. Mater. 471(1):200-208 (2016). Link to paper

Jin, M., Short, M. P. "Multiphysics Modeling of Two-Phase Film Boiling within Porous Corrosion Deposits." J. Comp. Phys. (In Press) (2016). Link to paper

Carlson, M., Yau, K., Simpson, R., Short, M. P. "Conceptual Design of a Pick-and-Place 3D Nanoprinter for Materials Synthesis." 3DP+ 2(3):123-130 (2015). Link to paper

Short, M. P., Yip, S. "Materials Aging at the Mesoscale: Kinetics of Thermal, Stress, Radiation Activations." COSSMS 19(4):245-252 (2015). Link to paper

Short, M. P., Dennett, C., Ferry, S., Yang, Y., Mishra, V., Eliason, J. K., Vega-Flick, A., Maznev, A. A., Nelson, K. A. "Applications of Transient Grating Spectroscopy to Radiation Materials Science." JOM 67(8):1840-1848 (2015). Link to paper

Emelyanova, O. V., Dzhumaev, P. S., Yakushin, V. L., Kalin, B. A., Ganchenkova, M. G., Khein, A. T., Leontyeva-Smirnova, M. V., Valiev, R. Z., Enikeev, N. A., Shao, L., Aydogan, E., Short, M. P., Garner, F. A. "Surface modification of low activation ferritic–martensitic steel EK-181 (Rusfer) by high temperature pulsed plasma flows." Nucl. Instrum. Meth. B 365(A):218-221 (2015). Link to paper

Li, Y., Yang, Y., Short, M. P., Ding, Z., Zeng, Z., Li, J. "IM3D: A parallel Monte Carlo code for efficient simulations of primary radiation displacements and damage in 3D geometry." Sci. Rep. 5:18130 (2015). Link to paper

Gaston, D., Permann, C., Peterson, J. W., Slaughter, A. E., Andrš, D., Wang, Y., Short, M. P., Perez, D. M., Tonks, M. R., Ortensi, J., Zou, L., Martineau, R. C. "Physics-based multiscale coupling for full core nuclear reactor simulation." Ann. Nucl. Ener. 84:45-54 (2015). Link to paper

Nelson, A. T., White, J. T., Andersson, D., Aguiar, J. A., McClellan, K. J., Byler, D. B., Short, M. P., Stanek, C. "Thermal Expansion, Heat Capacity, and Thermal Conductivity of Nickel Ferrite (NiFe2O4)." J. Am. Ceram. Soc. 97(5):1559-1565 (2014). Link to paper

Short, M. P., Gaston, D., Stanek, C., Yip, S. "A perspective on coupled multiscale simulation and validation in nuclear materials." MRS-B 39(1):71-77 (2014). Link to paper


22.033/22.33 Nuclear Systems Design Project
22.74 Radiation Damage & Effects in Nuclear Materials


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