Tanju Sofu

Manager, Engineering Analysis Department
- Nuclear Engineering

Tanju Sofu is the manager of the Engineering Analysis Department in Argonne's Nuclear Engineering Division. He is responsible for technical leadership and programmatic guidance of a variety of activities that include engineering simulations and safety analysis of nuclear reactor and fuel cycle facilities and systems, development of innovative nuclear reactor concepts, facility risk assessment and structural analyses, nuclear reactor plant performance analysis, and process modeling for developmental energy technologies.

Dr. Sofu also leads the Fast Reactor Safety and Licensing technical area under the U.S. Department of Energy's Advanced Reactor Concepts (ARC) program. He is the co-chair of Organisation for Economic Co-operation and Development/Nuclear Energy Agency's Generation-IV International Forum (GIF) Sodium Fast Reactor (SFR) Safety Design Criteria Task Force and U.S. representative to the GIF SFR Safety and Operations Project Management Board.

Dr. Sofu joined Argonne in 1992 as a post-doctoral appointee. During his tenure at Argonne, he has contributed to a number of nuclear and non-nuclear projects mostly focusing on development of simulation models for engineering systems analyses involving multi-dimensional, multi-scale, multi-physics phenomena. His technical contributions include a wide range of large-scale computational physics and fluid dynamics simulations on high-performance computing platforms for design optimizations, model validations, and safety analyses.

Publications and Patents

  • “Current Status of Collaboration for GIF Sodium-cooled Fast Reactor System,” D. Hahn, R. Hill, T. Sofu, C. Lee, J. Sienicki, N. Chauvin, Proceedings of 2012 GIF Symposium, ISBN 978-92-64-99199-6, OECD (2012).
  • “Safety Design Criteria for Generation-IV sodium-cooled fast reactor system,” R. Nakai and T. Sofu, Proceedings of 2012 GIF Symposium, ISBN 978-92-64-99199-6, OECD (2012).
  • “Sodium Fast Reactor Research Plan,” M. Denman, J. LaChance, T. Sofu, G. Flanagan, R. Wigeland and R. Bari, Transactions of American Nuclear Society, 2012 ANS Winter Meeting, November 11-15, 2012.
  • “Benchmark Specifications for EBR-II Shutdown Heat Removal Tests,” T. Sofu and L. L. Briggs, 2012 International Congress on the Advances in Nuclear Power Plants (ICAPP’12), Chicago, Illinois, June 24-28, 2012.
  • “Parametric Analysis of Thermal Stratification during the Monju Turbine Trip Test,” T. Sofu, 2012 International Congress on the Advances in Nuclear Power Plants (ICAPP’12), Chicago, Illinois, June 24-28, 2012.
  • “Analysis of the Phenix End-of-Life Natural Convection Test with SAS4A/SASSYS-1,” J. W. Thomas, T. H. Fanning, F. E. Dunn, T. Sofu, 2012 International Congress on the Advances in Nuclear Power Plants (ICAPP’12), Chicago, Illinois, June 24-28, 2012.
  • “GIF Sodium Fast Reactor Project R&D on Safety and Operation,” A. Vasile, T. Sofu, H. Y. Jeong, T. Sakai, 2012 International Congress on the Advances in Nuclear Power Plants (ICAPP’12), Chicago, Illinois, June 24-28, 2012.
  • “Nuclear Reactor Thermal Hydraulics,” T. Sofu, 48th Annual Technical Meeting of Society of Engineering Sciences (SES-2011), Northwestern University, Evanston, Illinois, October 12-14, 2011.
  • “Fundamentals of Nuclear Safety and Their Application in Design and Operation,” W. Deitrich and T. Sofu, 48th Annual Technical Meeting of Society of Engineering Sciences (SES-2011), Northwestern University, Evanston, Illinois, October 12-14, 2011.
  • “Sodium-cooled Fast reactor (SFR) Safety,” T. Sofu, International Seminars on Nuclear War and Planetary Emergencies – 43rd Session (Science and Culture: Nuclear Strategy and Peace Technology), R. Ragaini (editor), page 123, World Scientific Publishing Company (June 8, 2011).
  • “Analysis of Thermal Stratification in the Upper Plenum of the Monju Reactor Vessel,” T. Sofu and J. W Thomas, 14th International Topical Meeting on Nuclear Reactor Thermal-hydraulics, (NURETH-14), Toronto, Ontario, Canada, September 25-30, 2011.
  • “Safety Analysis of the Target Design with Electron Accelerator,” E. Merzari, T. Sofu, Y. Gohar, and Z. Zhong, International Topical Meeting on Nuclear Applications of Accelerators (ACCAPP-2011), Knoxville, Tennessee, April 3-7, 2011.
  • “TREAT Experiments Relational Database,” A. E. Wright, T. H. Bauer, P. H. Froehle, T. Sofu, Trans. Amer. Nucl. Soc., ANS Winter Meeting, Las Vegas, Nevada, November 7-11, 2010.
  • “Pressure-Flow Scour Prediction using Computational Fluid Dynamics with a Porous Media Formulation and a Moving-Grid Approach,” S. Lottes, T. Sofu, K. Kerenyi. J. Guo, B. Afzal, and B. Tulimilli, 2010 National Hydraulics Engineering Conference, Park City, Utah, August 31 to September 3, 2010.
  • “Combined Underhood Thermal and External Aerodynamic Analyses,” T. Sofu and L. K. Hwang, Aerodynamics of Heavy Vehicles III: Trucks, Buses and Trains, Potsdam, Germany, September 12-17, 2010.
  • “Experience with a High-Fidelity Multiphysics Computational Framework: A Case Study on LWR Fuel Reliability,” T. Sofu, Verification & Validation for Nuclear Systems Analysis Workshop – II, Myrtle Beach, South Carolina, May 24-28, 2010.
  • “Modeling of Thermal Stratification in Sodium Fast Reactor Outlet Plenums during Loss of Flow Transients,” T. H. Fanning and T. Sofu, Proc. International Conference on Fast Reactors and Related Fuel Cycles: Challenges and Opportunities (FR09), Kyoto, Japan, December 7-11, 2009.
  • “Analysis of a Hypothetical Partial Loss-of-Coolant Accident in the University of Wisconsin TRIGA-Fueled Research Reactor,” E. E. Feldman, T. Sofu, J. E. Matos, RERTR 2009 – 31st International Meeting on Reduced Enrichment for Research and Test Reactors, Beijing, China, November 1-5, 2009.
  • “Applicability of Commercial CFD Tools for Assessment of Heavy-Vehicle Aerodynamic Characteristics,” W. D. Pointer, T. Sofu, J. Chang, D. P. Weber, The Aerodynamics of Heavy Vehicles-II: Trucks, Buses, and Trains, pp349-361, F. Browand, R. McCallen, J. Ross editors, Springer (2009).
  • “Using Supercomputers to Determine Bridge Loads,” K. Kerenyi, T. Sofu, and J. Guo, Public Roads, September/October 2008, Vol. 72, No. 2, pp28-34 (2008).
  • “Analysis of the BWR Fuel Assembly Boiling Test BFBT Void Distribution Using a Two-Phase Computational Fluid Dynamics Model,” D. Pointer, A. Tentner, T. Sofu, D. Weber, S. Lo, A. Splaswski, International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), September 30 - October 4, 2007, Pittsburgh, Pennsylvania (2007).
  • “Prediction of Boiling Water Reactor Assembly Void Distributions Using a Two-Phase Computational Fluid Dynamics Model,” W. D. Pointer, A. Tentner, T. Sofu, S. Lo, A. Splawski, Proceedings of the 16th Intl. Conf. on Nuclear Engineering (ICONE-16), July 17-20, 2008, Orlando, Florida (2008).
  • “Innovative Solutions: Advanced Technologies and Equipment to Resolve Hydraulic Issues: Computational Fluid Dynamics for Bridge Hydraulics,” T. Sofu (ANL) and K. Kerenyi (FHWA), 2008 National Hydraulic Engineering Conference, Partnering for Progress in a Changing Environment, Portland, Maine, August 25 - 29, 2008.
  • “High Fidelity LWR Analysis with the Numerical Nuclear Reactor,” D. P. Weber, T. Sofu, et. al, Nuclear Science and Engineering, 155, 395-408 (2007).
  • “Multi-Physics Analysis of an Electron Target for the KIPT Subcritical Assembly,” T.Sofu, Y.Gohar, H. Belch, Z.Zhong, D. Naberezhnev, XX International Workshop on Charged Particle Accelerators (IWCPA-2007), September 9-15, 2007, Alushta, Ukraine (2007).