Koroush SHIRVAN Research Scientist Department of Nuclear Engineering, MIT [email protected] 24-212a, 77 Massachusetts Ave. Cambridge, Massachusetts, 02139 Cell: (352) 872-6272

EDUCATION

Sept. 2012 Ph.D. Nuclear Science and Engineering Massachusetts Institute of Technology, Cambridge, Massachusetts Major: Reactor Analysis Minor: Probabilistic Risk Assessment

Ph.D. Dissertation Title: Development of Optimized Core Design and Analysis Methods for High Power Density Boiling Water Reactors (Ph.D. Committee Chair: Professor Mujid Kazimi)

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

MS Thesis Title: Optimization of Small Integral Light Water Reactors (MS Committee Chair: Professor Mujid Kazimi)

May 2008 Bachelor of Science in Nuclear Engineering (Minor: Mathematics) University of Florida, Gainesville, Florida Graduated with Summa Cum Laude (Highest Honors)

Title of Highest Honors Project: Developed of a Methodology to Reduce Axial Offset Issues in PWRs by Coupling Core Neutronics, Thermal Hydraulics and Coolant Chemistry (Research Advisor: Professor Samim Anghaie)

May 2005 High School Diploma Graduated as Valedictorian Gainesville High School, Gainesville, Florida

February 2011 Swiss Federal Institute of Technology, Zürich (ETHZ), Zurich, Switzerland Short Course with certificate: Modeling & Computational Multi Phase Flow

WORK EXPERIENCE

Sept 2012 – Current Research Scientist/Engineer Department of Nuclear Engineering Massachusetts Institute of Technology Cambridge, Massachusetts

Graduate Research Assistant/Scientist

Research work primarily includes development of coupled Neutronics – Thermal Hydraulics and CFD Analysis Methods and their applications for structural mechanics and fuel performance and reactor core safety margin improvement, and optimization methods in current operating nuclear reactors. Specific research responsibilities include: • Development of methodology for design with coupled Neutronics-Thermal Hydraulics analysis of LWR cores. • Analysis of compact heat exchangers for next generation of nuclear reactors. • Support the assessment of the performance of SiC cladding in LWR reactors with conventional and innovative fuels such as Thorium. • Adaption of probabilistic risk assessment for performance of nuclear waste material for extended period of time. • Development of reactor system designs to perform safety analysis for both PWRs and BWRs. • Assessment of BWR stability modes in both frequency and time domains with both point kinetics and 3D neutronics. • Development of single and two-phase CFD and empirical models for nuclear fuel design geometries based on experimental data. • Development of finite volume and method of characteristic code to analyze non standard fuel geometries.

Graduate Teaching Assistant

Fall 2011: Nuclear Engineering 22.251 System Analysis of Nuclear Fuel Cycle Fall 2010: Nuclear Engineering 22.811 Sustainable Energy Summer 2011: MIT Reactor Technology Course for Nuclear Power Executives Summer 2010, 2011, 2012: MIT Nuclear Power Engineering Course for United Arab Emirates Nuclear Energy Corporation engineers. Summer 2009: MIT Nuclear Safety Course for Nuclear Industry.

May 2007 – August 2008 Core Design Intern Southern Nuclear Company Birmingham, Alabama

PWR Core Analysis, Summer 2008 • Worked extensively on PWR Pellet Clad Interaction risk assessment and created new methodologies to analyze fuel performance during power changes. Plant Vogtle Core Analysis, Summer 2007 • Ran and created many different codes for PWR core reload cycle design • Created a new core design methodology used by industry to reduce crud deposition on fuel rods

June 2006 – August 2008 Undergraduate Teaching Assistant Department of Industrial & Systems Engineering University of Florida

• CGS 2425 FORTRAN Programming (Summer 06, Spring 07, Summer 07)

COMPUTER & COMPUTATIONAL SKILLS/EXPERIENCE

• Primary Administrator of two MIT Department of Nuclear Engineering Computer Clusters along with technical support with engineering related software.

• Proficient in Fortran language and familiar with C#, C++, Xml, JAVA, Visual Basic, Maple, Matlab, GOLDSIM, GNU, MOOSE, Python.

• Expert User of major Nuclear Engineering modeling, analysis and licensing codes including:

• Neutronics: ANC, CASMO, SIMULATE, S3K, MCNP5/X, SERPENT, SCALE, PARTISN, DRAGON, ROSA, NESTLE, PARCS, BEACON • Thermal Hydraulics: RETRAN, RELAP, TRACE, VIPRE, COBRA,, TRANSAT, FLUENT, CFX, STARCCM+ • Materials and Nuclear Fuel Performance: BOA, FRAPCON, FRAPTRAN, FALCON, LAMMPS, SOLID WORKS, ADINA, MOOSE

PROFESSIONAL ACTIVITIES

Technical Program Committee member for TopFuel Conference 2013 Peer Reviwer of FRAPCON/FRAPTRAN Fuel Performance codes 2013 American Nuclear Society 2006-Present President, American Nuclear Society (MIT Chapter) 2011-2012 Member, DOE Energy Innovation Hub, CASL 2011-2013 Member, ANS Small and Medium Sized Reactor Committee 2011-Present Co-Developers and Administrator of MIT NSE website in response to Fukushima-Daiichi Accident (more than one million hits in the first 5 days) 2011-Present Delegate and Presenter at the Global Conference on Energy (Ishigaki, Japan) 2010 MIT International Energy Conference Panel Organizer and presenter 2010-2013

HONORS & AWARDS

Elite Nuclear Engineering Fellowship (Univ. of Florida) 2006-08 Alpha Nu Sigma Nuclear Honor Society 2007-Present TAU BETA PI Honor Society 2007-Present National Society of Collegiate Scholars 2006-Present Golden Key International Honour Society 2006-Present National Scholars Honor Society 2006-Present Reinhold Rudenberg Memorial Award (MIT) 2011 Signature Fission Doctorate Seminar Selectee (MIT) 2012 Outstanding Student Service Award (computer code management) 2012

PUBLICATIONS

Peer-Reviewed Journals & Conference Proceedings Shirvan K., Hejzlar P. Shatilla Y. and Kazimi M.S., “Enhancing the Power Density of IRIS by Compact Steam Generators,” Transactions of the American Nuclear Society, Vol 100, New York, pp. 567-568, 2009.

Shirvan K. Hejzlar P., and Kazimi M.S., M.,”The Design of a Compact Vessel Integrated LWR,“ Proceedings of International Congress on Advances in Nuclear Power Plants (ICAPP ’10), San Diego.

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.

Shirvan K., and Kazimi M.S., “Limitation of Control Rod Modeling with Current BWR Methods,“ Transactions of the American Nuclear Society, Hollywood, Fl, 2011.

Shirvan K. And Kazimi M.S., ”Nuclear Design Behaviour of Helical Cruciform Fuel Rods,” Physor, 2012.

Shirvan K., Andrews A., Kazimi M.S., “Best Estimate Void Fraction and Critical Power Correlations for Tight Lattice BWR Bundles,” ICAPP 2013, Korea, 2013.

Hall, A. Xu Y., Ward A., Downar T., Shirvan K., Kazimi M., “Advanced Neutronics Methods for Analysis of the RBWR-AC,” ANS Transactions, San Diego, 2013.

Shirvan K. And M.S. Kazimi, “BWR-HD: An Optimized BWR for High Power Density,” Journal of Nuclear Technology, Dec, 2013.

Shirvan K. Kazimi M. “Safety Analysis of BWR-HD: An Optimized BWR for High Power Density,” Journal of Nuclear Technology, Dec, 2013.

Shirvan K. Kazimi M. “Stability Analysis of an Optimized BWR for High Power Density (BWR-HD),” Journal of Nuclear Technology, Dec, 2013.

Shirvan K. Baglietto E., Kazimi M. “Assessment of a baseline Two Phase CFD closure for PWR applications,” Transactions of the American Nuclear Society, Washington D.C, 2013.

Shirvan K. Baglietto E., 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.

Shirvan K. And M.S. Kazimi, “Three Dimensional Considerations in Thermal-Hydraulics of Helical Cruciform Fuel Rods for LWR Power Uprates,” Manuscript submitted to Journal of Nuclear Engineering and Design, 2013.

Shirvan K., and M.S. Kazimi M., “Two-Phase Behaviour of Flow through Helical Cruciform Fuel Rods,” Manuscript in preparation, to be submitted to Journal of Multiphase Flow, 2013.

Major Reports & Other Publications

Kazimi, M.S., P. Hejzlar, Y. Shatilla, Bo Feng, Yu-Chih Ko, E. Pilat, K. Shirvan, J. Whitman, and A. Hamed, “A High Efficiency and Environmentally Friendly Nuclear Reactor (HEER) for Electricity and Hydrogen”, MIT-ANP-TR-125, (October 2009). Shirvan K. Hezjalar P. and M.S. Kazimi, “The Design of A Compact Integral Medium Size PWR: The CIRIS, “MIT-TR-ANP-129, Massachusetts Institute of Technology, March 2010.

Shirvan K., Ramsey A., and M.S. Kazimi, “Annual Report on High Power Density BWR Design, TEPCO,” FINAL REPORT, August 2011.

Shirvan K., Kazimi M.S., “Development of Optimized Core Design and Analysis Methods for High Power Density BWRs,” CANES MIT-ANP-TR-145, Nov 2012.