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 assessment of advanced nuclear reactor technology. He is currently focused on accelerating innovations in nuclear fuels, reactor design and small modular reactors to improve the sustainability 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 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 Advanced Fuels

The work focuses on identification of failure modes to support development of advanced fuels including concepts under consideration by the Accident Tolerant Fuel (ATF) program. All of fuel 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 both in-pile and out-of-pile testing of fuel concepts in extreme environments. The development of mechanistic thermal-hydraulics and structural mechanics models using high fidelity modeling and simulation guides the R&D process and evaluates the value proposition of each fuel concept.

Small Modular Reactor Optimization

Small Modular Reactors (SMRs) provide a path for accelerated deployment of nuclear energy given their smaller power output. However, many leading concepts such as Nuscale are designed with low plant power density and unable to be modular deployed from the site construction point-of-view. This will likely translate to the same slow deployment process as large reactors. The research work focuses on optimizing plant layout and performance that can result in shortest construction schedule and cheapest operation cost The work also investigates and introduces innovations (such as compact heat exchangers, seismic isolation, advanced I&C) to design an SMR for the 21st century market requirements. The neutronics, thermal hydraulics/CFD, fuel performance and economics analysis are key components of this research.

Advanced Data Analytics

Opportunities in advanced data analytics are currently being explored with the growing need to do more with less data, advent of high performance computing and infiltration of machine learning for nuclear engineering applications. Current research focuses on advanced uncertainty quantification techniques for licensing application, use of physics-informed machine learning for model closures and reinforced learning for core design optimization. The research approach focuses on addressing applicability concerns of advanced data analytics from the regulatory point of view for adoption in the nuclear engineering disciplines.


Recent Publications

  1. Shirvan K., “Implications of accident tolerant fuels on thermal-hydraulic researchNuclear Engineering and Design, Vol 358, March 2020.
  2. Zhao X., Shirvan K., Salko R., “On the prediction of critical heat flux using a physics-informed machine learning-aided framework” Applied Thermal Engineering, Vol 164, 5, Available Online Oct 2019.
  3. Wu X. Shirvan K., “System code evaluation of near-term accident tolerant claddings during boiling water reactor short-term and long-term station blackout accidents,” Nuclear Engineering and Design, Available Online Oct 2019.
  4. He Y., Shirvan, K., Wu Y., Su G., “Fuel performance optimization of U3Si2-SiC design during normal, power ramp and RIA conditions,” Nuclear Engineering and Design, Vol. 353, P. 110256, 2019.
  5. Wu X., Shirvan, K., Kozlowski T., “Demonstration of the relationship between sensitivity and identifiability for inverse uncertainty quantification,” Journal of Computational Physics, Vol. 396, pp. 12-30, 2019.
  6. Hiscox B., Shirvan, K., “Reactor Physics Analysis of a New Accident Tolerant Fuel Called Fuel-in-Fibers,” Annals of Nuclear Energy, Vol. 130, P. 473-482, 2019.
  7. Deng, Y., Shirvan, K., Wu, Y., Su, G. “Utilization of 3D fuel modeling capability of BISON to derive new insights in performance of advanced PWR fuel concepts,” Journal of Nuclear Materials, Vol 516, pp. 271-288, 2019.
  8. Seshadri A., Philips B., Shirvan, K., “Towards Understanding the Effects of Irradiation on Quenching Heat Transfer,” Journal of Heat and Mass Transfer, Vol 127 pp. 1087-1095, 2018.
  9. 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.
  10. 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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