NSE - Nuclear Science & Engineering at MIT


Koroush Shirvan

Koroush Shirvan

Assistant Professor



Koroush Shirvan joined the faculty in the Department of Nuclear Science and Engineering in July, 2017. Previously, he was a principal research scientist at Center for Advanced Nuclear Energy Systems (CANES). He specializes in development and analysis of innovative nuclear reactor technology. He is currently focused on development of advanced nuclear fuels focused on improving the economics and safety of current and next generation power plants. His approach combines multiple scales, physics and disciplines to realize innovative solutions in the highly regulated nuclear energy sector. He is the executive director of the accident tolerant fuel integrated research project (ATF IRP) and MIT education program lead for Consortium for Advanced Simulation of Light water reactors (CASL). He is also the Co-Director of Nuclear Reactor Technology course for utility executives.


Ph.D. Nuclear Science and Engineering, 2012
Massachusetts Institute of Technology, Cambridge, Massachusetts

Masters of Science in Nuclear Science and Engineering, 2010
Massachusetts Institute of Technology, Cambridge, Massachusetts

Bachelor of Science in Nuclear Engineering, 2008
University of Florida, Gainesville, Florida

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Development of Accident Tolerant Fuels

The work focuses on development of computational tools to simulate near term Accident Tolerant Fuel (ATF) options. All of ATF concepts involve some changes to the conventional fuel that is made of UO2 pellets and Zircaloy cladding. Any type of change to the current fuel system is more costly from the point of view of manufacturing and initial regulatory burden. Thus a multi-disciplinary approach is taken in realizing feasible technology solutions. Current concepts under investigation includes: Coated Zircaloy Cladding (Zr/Cr), Metal Composite Cladding (Zr/Mo/Cr), Ceramic Composite Cladding (SiC), Coated Ceramic Composite Cladding (SiC/Cr), High Density Fuels (UN) and Direct Manufactured Fuels. The research focuses on development of mechanistic thermal-hydraulics and structural mechanics models using high fidelity modeling and simulation, augmented with informed experimental testing

Reactor Design and Safety Analysis

Research work primarily includes multi-physics development and analysis of neutronics, thermal hydraulics/CFD and fuel performance phenomena to be applied to innovative nuclear reactor design and systems.


Recent Publications

  1. Shirvan K., Ballinger R,, Buongiorno J., Forsberg C., Kazimi M., Todreas N., “Technology Selection for Offshore Underwater Small Modular Reactors,” Journal of Nuclear Engineering and Technology (Available Online), June, 2016.
  2. Shirvan K., Kazimi M., “Superheated Water Small Modular Underwater Reactor Concept,” Journal of Nuclear Engineering and Technology (Available Online), June, 2016.
  3. Shirvan K., “Numerical Investigation of the Boiling Crisis for Helical Cruciform-Shaped Rods at High Pressures,” Journal of Multiphase Flow vol. 83, pp. 51-61, July, 2016.
  4. Shirvan K., Forrest E., “Design of an Organic Simplified Nuclear Reactor,” Journal of Nuclear Engineering and Technology, Accepted, February, 2016.
  5. Shirvan K., Kazimi M., “Is a PWR SMR or a BWR SMR the Better Choice for the Future?,” Transactions of the American Nuclear Society, Washington D.C, 2013.
  6. Shirvan K., Kazimi M., “BWR-HD: An Optimized BWR for High Power Density,” Journal of Nuclear Technology, Dec, 2013.
  7. Shirvan K., Hejzlar P., and Kazimi M.S., “The Design of A Compact Integral Medium Size PWR,” Nuclear Engineering and Design vol. 243, pp. 393-403, Feb 2012.


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