Assistant Professor of Nuclear Science and Engineering
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.
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.
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)
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