CURRICULUM VITAE THOMAS J. DOWNAR

1. EDUCATION 1984 1975 1974

Ph.D. M.S. B.S.

Massachusetts Institute of Technology. Discipline: Nuclear Engineering Massachusetts Institute of Technology. Discipline: Nuclear Engineering United States Military Academy, West Point

2. PROFESSIONAL EXPERIENCE 2008-Present

Professor and Chair of the Graduate Program, Department of Nuclear Engineering and Radiological Sciences, University of Michigan

2007 1998-2006 2003-2006 2002-2006 1990-1998 1984-90 1984 1979

Professor, Department of Nuclear Engineering, UC Berkeley Professor, School of Nuclear Engineering, Purdue University Co-Director, Computer Research Institute, Purdue University Director, Computational Science and Engineering Program, Purdue Associate Professor, School of Nuclear Engineering, Purdue University Assistant Professor, School of Nuclear Engineering, Purdue University Instructor, Department of Nuclear Engineering, MIT Assistant Professor of Physics, U.S. Military Academy, West Point, NY

3. AWARDS AND HONORS IN TEACHING & RESEARCH 2002 1995, 96 1989, 90, 92 1980-84 1980 1974

Fellow, American Nuclear Society (ANS) Best Paper Award, ANS Annual Meeting, Reactor Physics Division Best Teacher Award, School of Nuclear Engineering, Purdue Hertz Fellow, MIT Best Teacher Award, U.S. Military Academy, West Point, NY Distinguished Graduate (U.S. Military Academy)

4. PROFESSIONAL ORGANIZATIONS Chairman, Reactor Physics Division, American Nuclear Society, 1996 Nominating Committee, American Nuclear Society, 2005

RESEARCH, SCHOLARSHIP

DOWNAR - 2 1. Publications a. Archival Journals 1. “Reverse Depletion Method for PWR Core Reload Design," T.J. Downar and Y.J. Kim, Nucl. Tech., Vol. 73, 42-54, April 1986. 2. "Explicit Burnable Poison Modelling in PWR Core Reload Design Optimization," T.J. Downar and J.A. Stillman, Nucl. Sci. Eng., Vol. 94, 241-250, Nov. 1986. 3. "Accelerated Fuel Depreciation as an Economic Incentive for Low Leakage Fuel Management," T.J. Downar, Annals Nuc Eng, Vol. 13, 545-548, Oct. 1986. 4. "Moderator Feedback Effects in Two-Dimensional Nodal Methods for Pressurized Water Reactor Analysis," T.J. Downar, Nucl. Tech, Vol. 76, 303-307, Feb. 1987. 5. "Optimization of Core Reload Design for Low-Leakage Fuel Management in Pressurized Water Reactors," Y.J. Kim, T.J. Downar, and A. Sesonske, Vol. 96, Nuc. Sci. Eng., 85-101, June 1987. 6. "Reactivity Space Analysis of PWR Core Depletion," T.J. Downar, Annals Nuc Eng, Vol. 14, 135-144, May 1987. 7. "A Vectorized Source Algorithm for the LWR Coarse Mesh Nodal Code SIMULATE-E," C. Wemple, I. Dilber, and T.J. Downar, Nuc. Sci. Eng., Vol. 99, 36-41, May 1988. 8. "Generalized Perturbation Theory for Constant Power Core Depletion," W.S. Yang and T.J. Downar, Nucl. Sci. Eng., Vol. 99, 353-366, Aug. 1988. 9. "Optimal Space-Time Fuel Distribution in a One-Dimensional Numerical Core Model," H.R. Hwang and T.J. Downar, Annals Nucl Eng, Vol. 15, No. 5, 219-234, 1988. 10. "Depletion Perturbation Theory for the Constrained Equilibrium Cycle," W.S. Yang and T.J. Downar, Nucl. Sci. Eng., Vol. 102, No. 4, 365-380, 1989. 11. "The Optimum Fuel and Power Distribution for a PWR Burnup Cycle", J.A. Stillman, Y.A. Chao, and T.J. Downar, Nucl. Sci. Eng., Vol. 103, No. 4, 321-333, 1989. 12. "A Linear Time-Dependent Flux Approximation for Nuclide Depletion Based on a Perturbation Method", T.J. Downar and W.S. Yang, Annals Nucl. Energy, Vol. 17, No. 1, 3742, 1990. 13. "Uncertainty in the Burnup Reactivity Swing of Fast Reactors," T.J. Downar and H. Khalil, Nucl. Sci. Eng., Vol. 109, 278-296, Nov. 1991. 14. "Depletion Perturbation Theory for Burnup-Dependent Microscopic Cross Sections," T.J. Downar, Annals Nucl. Eng., Vol. 19, 27-37, Jan. 1992. 15. "Sensitivity Theory for the Closed Nuclear Fuel Cycle," H. Choi and T.J. Downar, Nucl. Sci. Eng., Vol. 111, 205-213, June 1992.

DOWNAR - 3 16. "Numerical Divergence Effects of Equivalence Theory in the Nodal Expansion Method," M. Zika and T. Downar, Nucl. Sci. Eng., Vol. 115, 219-232, Nov. 1993. 17. "Depletion Perturbation Theory within the Framework of an Advanced Nodal Method," T. Downar, Nucl. Sci. Eng., Vol. 115, 334-340, Nov. 1993. 18. “Optimization of PWR Shuffling by Simulated Annealing with Heuristics,” J. Stevans, K. Smith, K. Rempe, and T. Downar, Nucl. Sci. Eng., Vol. 121, 67-88, Sep. 1995. 19. “Harmonic Perturbation Theory for the Analysis of Boiling Water Reactor Regional Instabilities, Annals of Nuclear Energy, Vol. 22, 339-351, June 1995. 20. “An Augmented Source Method for the Application of Nodal Equivalence Theory,” C. Hah and T. Downar, Nucl. Sci. Eng., Vol. 121, 405-415, Nov. 1995. 21. “Incomplete Domain Decomposition Preconditioning for Coarse Mesh Neutron Diffusion Problems,” H. Joo and T. Downar, Nucl. Sci. Eng., Vol. 123, 403-414, July 1996. 22. “Parallel and Serial Applications of the RETRAN-03 Power Plant Simulation Code Using Domain Decomposition and Krylov Subspace Methods,” T. Downar, J.Y. Wu, J. Steill, R. Janardhan, Nuclear Technology, Vol. 117, 133-150, Feb. 1997. 23. “Mapping the Preconditioned Conjugate Gradient Algorithm for Neutron Diffusion Applications onto SIMD, MIMD, and Mixed-Mode Parallel Computers,” J. So, R. Janardhan, T. Downar, and H.J. Siegel, International Journal of Parallel Programming, Vol. 26, No. 1, 183-207, 1998. 24. “A Nested FGMRES Method for Parallel Calculation of Nuclear Reactor Transients,” R. Janardhan and T. Downar, J. of Scientific Computing, Vol. 13, No. 1, 65-93, 1998. 25. “Stabilization Techniques for the Nonlinear Analytic Nodal Method,” H. Joo, G. Jiang, and T. Downar, Nuclear Science and Engr., Vol. 130, No. 1, Sept. 1998.



26. “Importance of the D Term in Frequency Resolved Optical Diffusion Imaging,” J. Ye, R. Millane, K. Webb, and T. Downar, Optics Letters, Vol. 23, No. 18, Sept. 1998. 27. “Analysis of the Reactivity During a PWR Main Stream Line Break Transient,” G. Gose, T. Downar, K. Ott, Nuclear Technology, Vol. 124, No. 3, Dec. 1998. 28. “A Liquid Metal Reactor for Burning Minor Actinides of Spent Light Water Reactor Fuel I: Neutronics Design Study,” Choi, H. and Downar, T., Nuclear Science and Eng., Vol. 133, No. 1, p. 1-22, September 1999. 29. “A Liquid Metal Reactor for Burning Minor Actinides of Spent Light Water Reactor Fuel II: Nuclear Data Uncertainty Analysis,” Choi, H. and Downar, T., Nuclear Science and Eng., Vol. 133, No. 1, p. 23-39, September 1999. 30. “A Krylov Subspace Method for Solution of the Two Fluid Hydrodynamics Equations in VIPRE-02,” Downar, T. and Joo, H., Annals of Nuclear Energy, December, 2000.

DOWNAR - 4 31. “Thorium Fuel Performance in Advanced Light Water Reactors," T. K. Kim and T. Downar, Nuclear Technology, April, 2002. 32. “Neutronics Design and Analysis of a 200 MWe Simplified Boiling Water Reactor,” D. Tinkler and T. Downar, Nuclear Technology, Vol. 142, No. 3, April, 2003. 33. "A Hybrid Nodal Diffusion/SP3 Method Using One-Node Coarse-Mesh Finite Difference Formulation.” Nuclear Science and Engineering, Vol. 146, No.2, February, 2004. 34. “Analysis of the OECD/NRC Peach Bottom Turbine Trip Transient Benchmark with the Coupled Neutronics and Thermal-hydraulics Code TRAC-M/PARCS,” Deokjung Lee, Thomas J. Downar, Anthony Ulses, Bedirhan Akdeniz, Kostadin N. Ivanov, Nucl. Sci. Eng., Vol. 148, No.2, October, 2004.

35. “Convergence Analysis of the Nonlinear Coarse Mesh Finite Difference Method for Onedimensional Fixed Source Neutron Diffusion Problem,” Deokjung Lee, Thomas J. Downar, and Yonghee Kim, Nucl. Sci. Eng., Vol. 147, No.2, June, 2004. 36. “A Nodal and Finite Difference Hybrid Method for Pin-by-pin Heterogeneous Threedimensional LWR Diffusion Calculations,” Deokjung Lee, Thomas J. Downar, and Yonghee Kim, Nucl. Sci. Eng., Vol. 146, No. 3, March, 2004. 37. “Steam Line Break and Station Blackout Transients for Proliferation Resistant Hexagonal Tight Lattice Boiling Water Reactor,” U. Rohatgi, J. Jo, B. Chung, H. Takahashi, T. Downar, Nuclear Technology, Vol. 145, No. 1, , January, 2004. 38. “Consistent Comparison of the Codes RELAP5/PARCS and TRAC-M/PARCS for the OECD MSLB Coupled Code Benchmark,” T. Kozlowski, R. Miller, T. Downar, H. Joo, D. Barber Nuclear Technology, Vol. 146, No. 1, April, 2004. 39. “Use of Thorium in Light Water Reactors,” M. Todosow, A. Galperin, T. Downar, M. Kazimi, S. Herring, Nuclear Technology, Vol. 151, No. 2, August, 2005. 40. “Iterative Two and One Dimesional Methods for Three-Dimensional Neutron Diffusion Calculations,” H. Lee, D. Lee, T. Downar, Nuclear Science and Engineering, Vol. 151, No.l, September, 2005. 41. “Continuous Energy Multi-Dimensional SN Transport Problem Dependent Resonance SelfShielding Calculations,” Z.Zhong, T. Downar, M. Williams, M. DeHart, Nuclear Science and Engineering, Vol. 152, No. 4, April, 2006. 42. “Zirconium Matrix Cermet for a Uranium-Thorium Oxide Fuel in a SBWR”, S. McDeavitt, T. Downar, A. Solomon, Nuclear Technology, December, 2005. 43. “The Numerical Nuclear Reactor – A High Fidelity, Integrated Neutronic, Thermal-Hydraulic, and Thermo-Mechanical Code”, D. P. Weber, T. Sofu, W. S. Yang, K. S. Kim, T. H. Chun, T. Downar, J. Thomas, H. G. Joo, C. H. Kim, Nuclear Science and Engineering, January, 2006.

DOWNAR - 5 44. Fourier Convergence Analysis of 2-D/1-D Coupling Methods for the 3-Dimensional Neutron Diffusion Eigenvalue Problem, H. Lee, J. Noh, H. K. Joo, D. Lee, T. Downar, Nuclear Science and Engineering, May, 2007. 45. “Coarse Mesh Finite Difference Acceleration in the Two-Dimensional Discrete Ordinates Transport Calculation,” Z. Zhong, T. Downar, M. DeHart, K. Clarno, Y. Xu, accepted for publication, Nuclear Science and Engineering, May, 2007. 46. F. Reitsma, G. Strydom, J.B.M. de Haas, K. Ivanov, B. Tyobeka, R. Mphahlele, T.J. Downar, V. Seker, H.D. Gougar, D.F. Da Cruz, U. E. Sikik, “The PBMR steady-state and coupled kinetics core thermal-hydraulics benchmark test problems”, Nuclear Engineering and Design, 236 (2007) 657-68 47. “Parallelization in the SCALE Continuous-Energy Resonance Module GEMINEWTRN and the Transport Module NEWT,” Z. Zhong, T. Downar, M. DeHart, M. Williams, scheduled for publication in Nuclear Science and Engineering, March, 2008. 48. Y. Xu, T. Downar, R. Walls, K. Ivanov, J. Staudenmeier, J. March-Lueba, Application of TRACE/PARCS to BWR Stability Analysis,” Annals of Nuclear Energy, Volume 36, Number 3, March, 2009. 49. S. D. Clarke, S. A. Pozzi, M. Flaska, and T. J. Downar, "Monte Carlo study of photoneutron production in U-235 following perturbations in cross section data," Annals of Nucl. Energy, 369, 393-398 (2009). 50. S. Pozzi, Y. Xu, T. Zak, S. Clarke, M. Bourne, M. Flaska, T. Downar, Fast Neutron Spectrum Unfolding for Nuclear Nonproliferation and Safeguards Applications, NIMA, Volume 33, No.1, 2009. 51. S. D. Clarke, S. A. Pozzi, E. Padovani, and T. J. Downar, "Sensitivity of Photoneutron Production to Perturbations in Cross-Section Data," Nuclear Science and Engineering, 160, 3, 370-377, 2009. 52. T. Zak, S. D. Clarke, M. M. Bourne, S. A. Pozzi, Y. Xu, T. J. Downar, and P. Peerani. "Neutron spectroscopy of plutonium oxide using a matrix unfolding approach. Accepted for publication in Nucl. Instr. Meth. A. 53. Z. Gao, Y. Xu, T. Downar, “The Treatment of Resonance Interference Effects in the Subgruop Method,” Annals of Nuclear Energy, March, 2011 54. Andrew Ward, Benjamin S. Collins, Marcelo Ricardo Madariaga, Yunlin Xu and Thomas J. Downar , "Methods & Model Development for Coupled RELAP5 / PARCS Analysis of the Atucha-II Nuclear Power Plant,", STNI, CSNI Journal. Dec. 2010.

55. Mathieu Hursin, Thomas J. Downar, Brendan Kochunas, “Analysis of the Core Power Response During a PWR Rod Ejection Transient Using the PARCS Nodal Code and the DeCART MOC Code,” Nuclear Science and Engineering / Volume 170 / Number 2 February 2012 / Pages 151-167

DOWNAR - 6 56. T. Drzwiecki, Isaac M. Asher, Timothy P. Grunloh, Victor E. Petrov, Krzysztof J. Fidkowski, Annalisa Manera, and Thomas J. Downar , Parameter Sensitivity Study of Boiling and TwoPhase Flow Models in CFD, Journal of Computational Fluid Dynamics, Volume 4, Number 4, December, 2012. 57. N. Brown, V. Seker, S. Revankar, T. Downar, “An Endothermic Chemical Process Facility Coupled to a High Temperature Reactor, Part I: Proposed Accident Scenarios Within the Chemical Plant,” Nuclear Engineering and Design, Volume 246, May, 2012. 58. N. Brown, V. Seker, S. Revankar, T. Downar, “Transient Simulation of an Endothermic Chemical Process Facility Coupled to a High Temperature Reactor: Part II: Model Development and Validation,” Nuclear Engineering and Design, Volume 248, July, 2012.

59. , Mathieu Hursin, Thomas J. Downar, Robert Montgomery, “Impact of improved neutronic methodology on the cladding response during a PWR reactivity initiated accident,” Nuclear Engineering and DesignVolume 262, September 2013, Pages 180-188 60. Artem Yankov, Benjamin Collins, Markus Klein, Matthew A. Jessee, Thomas Downar, Winfried Zwermann, Kiril Velkov, Andreas Pautz, “A Two-Step Approach to Uncertainty Quantification of Core Simulators", Science and Technology of Nuclear Installations, Volume 2012, January, 2013 61. Raymond C. Wang, Yunlin Xu, Nathanael Hudson, Thomas J. Downar, “Validation of the U.S. NRC Coupled Code System TRITON/TRACE/PARCS Using the Special Power Excursion Reactor Test III,” Nuclear Technology, Volume 183 / Number 3 / 2013 / Pages 504-514. 62. M. Hursin, B. Collins, Y. Xu, and T. Downar “The Development and Implementation of a OneDimensional Sn Method in the 2D-1D Integral Transport Solution,” , Nuclear Science and Engineering, Volume 176 / Number 2 / 2013 / Pages 186-200 63. Tomasz Kozlowski, Aaron Wysocki , Ivan Gajev, Yunlin Xu, Thomas Downar “Analysis of the OECD/NRC Oskarshamn-2 BWR Stability Benchmark,” Annals of Nuclear Energy, Volume 67, May, 2013, pages 4-12 64. A. Wysocki, J. March-Leuba, A. Manera, T. Downar , “TRACE/PARCS analysis of out-ofphase power oscillations with a rotating line of symmetry,”, Annals of Nuclear Energy, Volume 67, May 2014, Pages 59-69

b. Book Chapters 1. "Light Water Reactor Fuel Cycle Optimization: Theory Versus Practice," T.J. Downar and Alexander Sesonske, Advances in Nuclear Science and Technology, Plenum Press, Vol. 20, 71126, 1988.

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c. Conference Proceedings 1. “Optimal Burnable Poison Utilization in PWR Core Reload Design”, T. J. Downar (Purdue University), Proceedings of the Topical Meeting on Advances in Fuel Management, March 2 – 5, 1986, Pinehurst, North Carolina 2. “A Microcomputer Program for Coupled Cycle Burnup Calculation”, M. J. Driscoll (M.I.T.), T. J. Downar (Purdue University), E. L. Taylor (M.I.T.), Proceedings of the Topical Meeting on Advances in Fuel Management, March 2 – 5, 1986, Pinehurst, North Carolina 3. “A University Course In Nuclear Fuel Management”, T. J. Downar (Purdue University), M. J. Driscoll (M.I.T.), Proceedings of the Topical Meeting on Advances in Fuel Management, March 2 – 5, 1986, Pinehurst, North Carolina 4. ”Depletion perturbation theory of iterative linear time dependent flux approximations”, Yang, W.S. , Downar, T.J. (Purdue Uni.), Proceedings of the 1988 International Reactor Physics Conference, September 1988, Jackson Hole, Wyoming. 5. ”A linear time-dependent flux approximation for forward and adjoint nuclide depletion based on a perturbation method”, Yang, W.S. , Downar, T.J. (Purdue Uni.), Proceedings of the 1988 International Reactor Physics Conference, September 1988, Jackson Hole, Wyoming. 6. “The optimum fuel and power distribution for a PWR burnup cycle”, Stillman, J.A., Chao, Y.A.; Downar, T.J. (Purdue Uni.), Proceedings of the 1988 International Reactor Physics Conference, September 1988, Jackson Hole, Wyoming. 7. A linear time-dependent flux approximation for forward and adjoint nuclide depletion based on a perturbation method”, Yang, W.S. , Downar, T.J. (Purdue Uni.), Proceedings of the 1988 International Reactor Physics Conference, September 1988, Jackson Hole, Wyoming. 8. “The optimum fuel and power distribution for a PWR burnup cycle”, Stillman, J.A., Chao, Y.A.; Downar, T.J. (Purdue Uni.), Proceedings of the 1988 International Reactor Physics Conference, September 1988, Jackson Hole, Wyoming. 9. “Sensitivity Theory for the Equilibrium Burnup Cycle”, T. J. Downar, W.S. Yang, J. Stevens (Purdue University), Physor-90, International Conference on the Physics of Reactors: Operation, Design and Computation, April 23-27, 1990, Marseille, France 10. “A computer Code to Generate Depletion Sensitivity”, Thomas J. Downar (Purdue University), Advances in Mathematics, Computations and Reactor Physics, International Topical Meeting, April 28 – May 2, 1991, Pittsburgh, PA. 11. “The neutronics analysis of a liquid metal reactor for burning minor actinides”, Choi, H. Downar, T. J. (Purdue Uni.), Proceedings of International Conference on Design and Safety of Advanced Nuclear Power Plants, October 25-29, 1992, Tokyo, Japan

DOWNAR - 8 12. “A Three-Dimensional Nodal Neutron Kinetics Capability For RELAP5”, J. L. Judd, W. L. Weaver (INEL), T. Downar, H. G. Joo (Purdue Uni.), Proceedings of 1994 Topical Meeting on Advances in Reactor Physics”, April 11-15, 1994, Knoxville, TN 13. “Optimization of PWR Shuffling by Simulated Annealing with Heuristics”, J. G. Stevens, K. S. Smith, K. R. Rempe (Studsvik of Amerika), T. J. Downar (Purdue University), Proceedings of 1994 Topical Meeting on Advances in Reactor Physics”, April 11-15, 1994, Knoxville, TN 14. ”The application of SIMD, MIMD, and mixed-mode parallel computing to nuclear reactor simulation”, Janardhan, R.S., Downar, T.J.; So, J.E.; Siegel, H.J., High Performance Computing Symposium 1995, January 27, 1995, San Diego, CA, 15. ”Incomplete domain decomposition preconditioning for coarse mesh neutron diffusion problems”, Joo, H.G. Downar, T.J. Proceedings of the International Conference, Mathematics and Computations, Reactor Physics, and Environmental Analyses, April 30-May 4, 1995, Portland, Oregon. 16. “Mapping the preconditioned conjugate gradient algorithm for neutron diffusion applications onto parallel machines”, So, J.J.E. Janardhan, R., Downar, T.J., Siegel, H.J., Proceedings of the 1996 International Conference on Parallel Processing. Vol.2 Algorithms and Applications, August 1216, 1996, Bloomingdale, IL 17. “Methods and Performance of a Parallel Reactor Kinetics Code PARCS”, Han Gyu Joo, Thomas J. Downar, Douglas A. Barber (Purdue Uni.), PHYSOR 96, September 16-20, 1996, Mito, Ibaraki, Japan. 18. “Parallel Computing Methods for the EPRI Spatial Kinetics Code ARROTTA”, H.G. Joo, T. J. Downar, D. A. Barber, G. Jiang (Purdue Uni.), L. D. Eisenhart, A. F. Dias, J. L. Vaskuil (S. Levy, Inc.) , Proceedings of the American Nuclear Society Topical Meeting- Advances in Nuclear Fuel Management II, March 23-26, 1997 Myrtle Beach, South Carolina. 19. “A RELAP/NESTLE Engineering Simulator for Shared-Memory Multuprocessors”, D. Barber, H. Joo, T. Downar (Purdue Uni.), P. Turinsky, H. Sarsour (North Carolina State University), J. Judd (Science Applications International Corp.), R. Wagner, W. Weaver (Idaho National Engineering Lab.) Proceedings of the American Nuclear Society Topical Meeting- Advances in Nuclear Fuel Management II, March 23-26, 1997 Myrtle Beach, South Carolina. 20. “A Hybrid ANM/NEM Interface Current Technique for the Nonlinear Nodal Calculation”, Thomas J. Downar, Han Gyu Joo, Guobing Jiang (Purdue University) Proceedings: Joint International Conference on Mathematical Methods and Supercomputing for Nuclear Applications, October 5-9, 1997, Saratoga Springs, NY 21. “A Krylov Subspace Method with BILU-3D Preconditioning for the CMFD Problem in Hexagonal Geometries”, Douglas A. Barber, Thomas J. Downar (Purdue University) Proceedings: Joint International Conference on Mathematical Methods and Supercomputing for Nuclear Applications, October 5-9, 1997, Saratoga Springs, NY 22. “A Harmonic Analytic Nodal Method”, Guobing Jiang, Thomas J. Downar (Purdue Uni.) Proceedings: International Conference on the Physics of Nuclear Science and Technology, October 5-8, 1998, Long Island, New York

DOWNAR - 9 23. "A Generalized Interface Module for the Coupling of Spatial Kinetics and Thermal-Hydraulics Codes," D. Barber, R. M. Miller, H. G. Joo, T. J. Downar, W. Wang, V. Mousseau, and D. Ebert, to be presented at the 9th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-9), San Francisco, CA, October 3-8 1999. 24. "Consistent Analytic Pin Power Reconstruction Method for Static and Transient Reactor Analysis," H. Joo and T. Downar, International Meeting on Mathematics and Computation, M&C'99, Madrid, Spain, Oct., 1999. 25. "Analysis of the OECD MSLB Benchmark with RELAP-PARCS and TRACM-PARCS," R.Miller, H. Joo, D. Barber, T.Downar, D.Ebert, International Meeting on Mathematics and Computation, M&C'99, Madrid, Spain, Oct., 1999. 26. "Coupled 3D Reactor Kinetics and Thermal-Hydraulic Code Activities at the US Nuclear Regulatory Commission," D. Barber, R. Miller, H. Joo, T. Downar, W. Wang, V. Mousseau, International Meeting on Mathematics and Computation, M&C'99, Madrid, Spain, Oct., 1999. 27. "Polar Interface Current Characteristics Method," PHYSOR-2000, J. Young, C. Lee, T. Downar, ANS Reactor Physics Topical Meeting, Pittsburgh, February, 2000. 28. "Analysis of the OECD MSLB Benchmark with Coupled Neutronic and Thermal-Hydraulics Codes RELAP5/PARCS and TRAC-M/PARCS," T. Kozlowski, R. Miller, T. Downar, PHYSOR2000, ANS Reactor Physics Topical Meeting, Pittsburgh, February, 2000. 29. "Consistent Two-Group Spatial Kinetics with Bilinear Weighting for MOX Cores," C. Lee, T. Downar, H. Joo, K. Ott, PHYSOR-2000, ANS Reactor Physics Topical Meeting, Pittsburgh, February, 2000. 30. T. Downar, C. Lee, G. Jiang, "Advanced Nodal Methods for MOX Fuel Analysis," PHYSOR2000, ANS Reactor Physics Topical Meeting, Pittsburgh, February, 2000. 31. Fuel Cycle Depletion Capability for the U.S. NRC Neutornics Code PARCS, Y. Xu, T. Kim, D. Tinkler, T. Downar, M&C 2001 Salt Lake City, Utah, USA, September 2001 32. “Neutronics Design and Analysis of a High Conversion Boiling Water Reactor,” Y. Xu, T. Downar, K .Rohatgi, H. Takahashi, ICONE-10, Washington, D.C., April, 2002. 33. “Analysis of Control Rod Drive Failure in the Oconnee Nuclear Power Plant Using the TRACM/PARCS Code”, Gascon, T. Downar, K. Ivanov, ICONE-10, Washington, D.C., April, 2002. 34. “Neutronics Design of a Mixed Oxide Cermet Dispersion Fuel Using Thorium Uranium Oxide in a Zirconium Metal Matrix,” T. Downar, S. McDeavitt, A. Solomon,ICONE-10, Washington, D.C., April, 2002. 35. Analysis of the OECD Peach Bottom Turbine Trip 2 Transient Benchmark with Coupled Neutronic and Thermal-Hydraulics Code TRAC-M/PARCS, D. J. Lee, T. Downar, T. Ulses, K. Ivanov, B. Akdeniz, PHYSOR-2002, Seoul Korea, October, 2002. 36. Benchmarking of the Multigroup, Fine Mesh, SP3 Methods in PARCS with the VENUS-2 MOX Critical Experiments, T. Kozlowski, C. Lee, T. Downar, School of Nuclear Engineering Purdue University, PHYSOR-2002, Seoul Korea, October, 2002.

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37. The Application of a Threads Parallel Computing Model to the U.S. NRC Neutron Kinetics Code PARCS, D.J. Lee and T.J. Downar, School of Nuclear Engineering Purdue University, PHYSOR2002, Seoul Korea, October, 2002. 38. “Analysis of Control Rod Ejection Accident in MOX and MOX/UOX Cores with TimeDependent Multigroup Pin-by-Pin SP3 Methods”, Chang-Ho Lee, Tomasz Kozlowski, Thomas J. Downar, School of Nuclear Engineering Purdue University, PHYSOR-2002, Seoul Korea, October, 2002. 39. Benchmarking the DeCART Integral Transport Code with the VENUS-2 MOX Critical Experiment, Z.Zhong, H.G.Joo, J.Y.Cho, T.J.Downar, Reactor Physics ANS Topical Meeting, PHYSOR-04, April, 2004, Chicago, IL 40. The Implementation of Pin-Cell Discontinuity Factors in PARCS Using an Artificial Neural Network with Application to MOX Fuel Analysis, T. Kozlowski D. Lee T. J. Downar, Reactor Physics ANS Topical Meeting, PHYSOR-04, April, 2004, Chicago, IL 41. Convergence Analysis of 2-D/1-D Coupling Strategies for the Neutron Diffusion Equation, Hyun Chul Lee, Thomas J. Downar, Reactor Physics ANS Topical Meeting, PHYSOR-04, April, 2004, Chicago, IL 42. Fourier Analysis of the Nonlinear CMFD Method for One-Dimensional Two-Group Fixed Source Diffusion Problem, D. Lee, T. J. Downar, and Y. Kim, Reactor Physics ANS Topical Meeting, PHYSOR-04, April, 2004, Chicago, IL 43. Numerical Convergence Analysis of the Nonlinear CMFD Method for Three-Dimensional, TwoGroup LWR Diffusion Problems, D. Lee, T. J. Downar, and Y. Kim, Reactor Physics ANS Topical Meeting, PHYSOR-04, April, 2004, Chicago, IL 44. Analysis of Results for the OECD/NEA and U.S. NRC PWR MOX/UO2 Core Transient Benchmark, T. Kozlowski C. A. Cotton T. J. Downar, Reactor Physics ANS Topical Meeting, PHYSOR-04, April, 2004, Chicago, IL 45. Methodology for Coupling Computational Fluid Dynamics with Integral Transport Neutronics, J.W. Thomas, Z.Zhong, T. Sofu, T.J.Downar, Reactor Physics ANS Topical Meeting, PHYSOR04, April, 2004, Chicago, IL 46. Analysis of the OECD/NEA Ringhalls Instability Benchmark with TRACE/PARCS, Y. Xu, T. Downar, K. Ivanov, J. Veldovi, A. Petruzzi, J. Staudenmeier, Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Application, Palais des Papes, Avignon, France, September 12-15, 2005, American Nuclear Society 47. Methodolgies for BWR Stability Analysis with TRACE/PARCS, Y. Xu and T. Downar, K. Ivanov, A. Petruzzi, F. Maggini, R. Miró, J. Staudenmeier, Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Application, Palais des Papes, Avignon, France, September 12-15, 2005, American Nuclear Society 48. The Numerical Nuclear Reactor – A High Fidelity, Integrated Neutronic, Thermal-Hydraulic, and Thermo-Mechanical Code, D. P. Weber, T. Sofu, P. Pfeiffer, W. S. Yang, K. S. Kim, T. H. Chun, T. Downar, J. Thomas, H. G. Joo, C. H. Kim, Mathematics and Computation, Supercomputing,

DOWNAR - 11 Reactor Physics and Nuclear and Biological Application, Palais des Papes, Avignon, France, September 12-15, 2005, American Nuclear Society 49. Fourier Convergence Analysis Applied to the Neutron Diffusion Eigenvalue Problem, Hyun Chul Lee, Jae Man Noh and Hyung Kook Joo, Deokjung Lee and Thomas J. Downar, Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Application, Palais des Papes, Avignon, France, September 12-15, 2005, American Nuclear Society 50. The Implementation of Matrix Free Newton /Krylov Methods Based on a Fixed Point Iteration, Y. Xu, T. Downar, Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Application, Palais des Papes, Avignon, France, September 12-15, 2005, American Nuclear Society 51. Assembly Based Modular Ray Tracing and CMFD Acceleration for BWR Cores with Different Fuel Lattices, J.W. Thomas, H.G. Joo, Y. Xu, M. Kalugin, B. Kochunas, T.J. Downar, Proceedings of ICAPP ’06, Reno, Nevada, June, 2006. 52. Parallelization of the Continuous Energy Resonance Code GEMINEWTRN, Z. Zhong, T. Downar, M. DeHart, M. Williams, Proceedings of ANS Reactor Physics Topical Meeting PHYSOR-06, Vancouver, B.C. September, 2006. 53. Multi-Physics Coupled Code Reactor Analysis with the U.S. NRC Code System TRACE/PARCS, T. Downar, Proceedings of ANS Reactor Physics Topical Meeting PHYSOR06, Vancouver, B.C. September, 2006. 54. The Analysis of the OECD/NEA/NSC PBMR-400 Benchmark Problem Using PARCSDIREKT, V. Seker, T. Downar, Proceedings of ANS Reactor Physics Topical Meeting PHYSOR-06, Vancouver, B.C. September, 2006. 55. Monte Carlo Modeling of Photon Interrogation Methods for Special Nuclear Material Characterization, S. Clarke, S. Pozzi, T. Downar, Proceedings of ANS Reactor Physics Topical Meeting PHYSOR-06, Vancouver, B.C. September, 2006. 56. Coarse Mesh Finite Difference Acceleration in the Two-Dimensional Discrete Ordinates Transport Calculation, Z. Zhong, T. Downar, K. Clarno, M. Dehart, Proceedings of ANS Reactor Physics Topical Meeting PHYSOR-06, Vancouver, B.C. September, 2006. 57. The Calculation of Resonance Parameters for the DeCART MOC Code, Z. Gao, Y. Xu, T. Downar, Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications (M&C + SNA 2007), Monterey, California, April 1519, 2007, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2007) 58. Advanced Heat Transfer and Fluid Flow Calculations for Pebble Bed Reactors, V. Seker and T. Downar, International Conference on Emerging Nuclear Energy Systems (ICENES-2007), Istanbul, TURKEY, June 3 – 8 2007

59. “Overview of Development and Design of MPACT: Michigan Parallel Characteristics Transport Code” B. Kochunas, B. Collins, T. Downar, and W. Martin, M&C 2013, Sun Valley, Idaho, May, 2013.

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60. “Assessment of the 2D MOC Solver in MPACT, B. Collins, B. Kochunas, T. Downar, M&C 2013, Sun Valley, Idaho, May, 2013. 61. “Parallel 3-D MOC in MPACT,” B. Kochunas, T. Downar, Z. Liu, M&C 2013, Sun Valley, Idaho, May, 2013. 62. “The Method of Modular Characteristic Direction Probabilities in MPACT,” Z. Liu, B. Kochunas, B. Collins, T. Downar, H .Wu, M&C 2013, Sun Valley, Idaho, May, 2013. 63. “Assessment and Improvement of the 2D/1D Method Stability in DeCART”, S. Stimpson, M. Young, B. Collins, B. Kelley and T. Downar, M&C 2013, Sun Valley, Idaho, May, 2013. 64. “The Application of PARCS/PATHS to Depletion of Hatch Cycles 1-3,” P. Yarsky, A. Ward, Y. Xu, T. Downar, N. Hudson, NURETH-15, Pisa, Italy, May 12-15, 2013.

d. Book 1. "The Linear Reactivity Model for Nuclear Fuel Management," M.J. Driscoll, T.J. Downar, E.E. Pilat, American Nuclear Society, Oct. 1990. 2. Graduate Research Program a. M.S. Degrees Completed (27) Date 1986 1987 1987 1987 1987 1992 1994 1995 1995 1997 1997 1997 1998

Name Of Student and Thesis Topic R. Launstein, 'PINCAS: A Fuel Cycle Economics Code' T. Niggel, 'Optimal Burnable Absorber Assignment for PWR Core Reload Design' D. Edwards, 'Non-linear Programming Solutions to the Minimum Fuel Loading Problem' C. Wemple, 'A Vectorized Source Algorithm for the Nodal Code SIMULATE-E' H.S. Kim, 'Effects of Availability on the Determination of Cycle Length' M. Zika, ‘Numerical Divergence Effects in Nodal Equivalence Theory’ D. Phegley, ‘Harmonic Perturbation Theory for the Analysis of Boiling Water Reactor Regional Instabilities’ S. Cooper, ‘The Application of the BICGSTAB Semi-Iterative Algorithm to the ARROTTA Spatial Kinetics Code’ R. Janardhan, ‘A Multi-Level FGMRES Method for Parallel Calculation of Nuclear Reactor Transients’ J. Chai, ‘The Application of Neural Networks and Parallel Computing to PRA’ (Comajor Professsor with L. Tsoukalas) D. Barber, ‘A Preconditioned Krylov Subspace Method for the Neutron Diffusion Problem in Hexabgonal Geometry’ J. Steill, ‘Nested Krylov Methods for Fluid Dynamics’ S. Spooner, ‘Reactor Dehomogenization Methods for the Advanced Nodal Methods’

DOWNAR - 13 1999 1999 2000 2001 2002 2004 2006 2007 2007 2007 2007 2007 2009 2012

Q. Wang ‘Parallel Computing Methods for Coupled Thermal-Hydarulics/Neutronics Analysis’ V. Krishnan, ‘‘High Performance Computing for the Power-Flow Systems Equations’ (Co-advisor) M. Miller ‘Advanced Time Integration Methods for Coupled Field Calculations’ S. Spillane, ‘Anticipatory Control of the Electric Power Grid’ D. Tinkler, “Design and Analysis of a 200 MWe Simplified Boiling Water Reactor” C. Cotton, “Neutronics Methods for the Advanced CANDU Reactor” E. Swain, “Neural Networks for Power Grid Applications” J. Jenkins, “Redesign of the PUR-1 Reactor” K. Kramer, “Monte Carlo Depletion Analysis of the ABR” (UC Berkeley) A. Ward, “LOCA Analysis of the ATUCHA-II Reactor” C. Glass, “Design and Analysis of the SFR for Transuranic Burning” J. Seifred, “Two-Phase Flow Multipliers in TRACE” (UC Berkeley) D. Jabaay, “Coupled Code Methods for Analysis of the CANDU Reactor” R. Wang, “Transient Analysis of Reactivity Insertion Accident”

b. Ph.D. Degrees Completed (23) Date 1986 1988 1989 1989 1993 1994 1995 1996 1997 1999 2000 2004 2004 2005 2005 2006 2007 2007 2009

Name of Student and Thesis Topic Y.J. Kim, 'Optimization of Core Reload Design for Low Leakage Fuel Management in Pressurized Water Reactors' (Co-Major Professor) H.R. Hwang, 'Optimal Space-Time Fuel Distribution in the Light Water Reactor' W.S. Yang, 'Depletion Perturbation Theory for the Constrained Equilibrium Cycle' J.A. Stillman, 'The Optimum Fuel and Power Distribution for a PWR Burnup Cycle' H. Choi, 'The Design and Analysis of a Liquid Metal Reactor for Burning Minor Actinides' C. Hah, ‘The Augmented Source Method for the Application of Nodal Equivalence Theory’ J. Stevens, ‘Light Water Reactor Core Reload Optimization’ H. Joo, ‘An Incomplete Domain Decomposition Preconditioning Method for Nonlinear Nodal Spatial Kinetics’ J. Wu, ‘The Application of Domain Decomposition and Krylov Subspace Methods to Reactor Safety Analysis’ G. Jiang, ‘Multigroup Analytic Nodal Methods for MOX Fuel Analysis’ C. Lee, “SP3 Methods for MOX Fuel Neutronics Analysis” D. Lee, “Numerical Convergence Analysis of the Nonlinear Nodal Method” Y. Xu, “Matrix Free Newton Krylov Methods for Coupled Nonlinear Subsystems” T. Kozlowski, “Homogenization Methods for Pin-by-Pin Neutron Transport” Z. Zhong, “Continuous Energy Multi-Dimensional Resonance Self-Shielding” J. Thomas, “The Method of Characteristics for Solution of the Integral Neutron Transport Equation in Boiling Water Reactors” S. Clarke, “Analysis of Prompt Emissions Following Photon Interrogation of Fissionable Material” V. Seker, “Multiphysics Methods for Analysis of the High Temperature Gas Reactor” M. Hursin, “Coupled MOC and CFD Methods for Analysis of the PWR Control Rod Ejection Event” (UC Berkeley)

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B. Collins, “Hybrid Transport-Diffusion Methods for LWR Analysis” A. Ward “Newton-Krylov Methods for Solution of the Coupled Neutron Kinetics and Thermal-Hydrualics Equations” B. Kochunas, “3-D Method of Characteristics for LWR Applications” T. Drzwiecki, “Adjoint Methods Uncertainty Quantification Methods for HTR Analysis”

2013 2013

c. Graduate Degrees in Progress (12) Name of Student A. Yankov A.Wysocki A. Hall T. Sallar S. Stimpson M. Rose A.Beilen A.Zhu M. Jarrett A.Graham H. Zhou Nghia Nguyen

Degree Ph.D. Ph.D. Ph.D. Ph.D. Ph.D. Ph.D. Ph.D Ph.D. Ph.D. Ph.D. Ph.D. Ph.D.

Thesis Topic “Uncertainty Quantification for Reactor Analysis” “Boiling Water Reactor Stability Analysis” “Transuranic Burning in Fast Spectrum Reactors” “Advanced Methods for High Temperature Reactors” “Advanced Methods for Light Water Reactor Analysis” “Reactor Fuel Performance and Transport Neutronics” “Coupled Neutronic and Fuel Performance” Time-Dependent SP3 Transport Methods Topic To Be Determined Topic To Be Determined Topic To Be Determined Topic To Be Determined

d. Professional Staff Supported • • • • • • • • • • • • • • • • •

Dr. Y. Xu, 2000-present, Research Faculty Dr. V. Seker, 2007-present, Research Staff Lead Dr. A. Ward, 2012-present, Research Staff Lead Dr. B. Kochunas, 2013-present, Research Scientist Dan Jabaay, 2012-present, Computer Technician Dr. B. Collins, 2011-2014, Research Scientist Dr. J. Y. Wu, Post-doctoral Researcher, 1997-1998 Dr. D. Y. Yang, Post-doctoral Researcher, 1997-1999 Dr. H. Joo, Post-doctoral Researcher, 1996-99 Mr. D. Barber, Post-graduate Researcher, 1997-1998 Dr. Y.J. Cho, Post-doctoral Researcher, 1999-00 Prof C.H. Kim, Visiting Professor, 2000 Dr. T.K. Kim, Post-doctoral Researcher, 2000-2002 Dr. Jean Ragusa, Visiting Professor, 2001-2002 Dr. Hyun Chul Lee, Visiting Professor, 2001-2003 Dr. Deok Jong Lee, Post-doctoral Researcher, 2003-2005 Dr. Mikhail Kalugin, Post-doctoral Researcher, 2005-2006

3. Research Grants and Contracts a. Active

Approx. Grad. Date 2014 2014 2015 2015 2015 2015 2015 2016 2017 2017 2018 2018

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Dates

U.S. NRC U.S. NRC ORNL INL DOE (ORNL) DOE NEUP DOE NEUP DOE NEUP/IRP DOE NEUP/IRP DOE NEUP Hitachi Corp.

2010-15 2009-14 2012-14 2013-14 2010-15 2011-14 2011-14 2012-15 2012-15 2013-16 2013-14

Description PARCS Code Development HTR Advanced Thermal-Fluids Methods BWR TH Code Development HTR Code Development Nuclear Reactor Simulation Hub RBWR Transient Analysis Thorium Fueled RBWR (from UCB) Accident Tolerant Fuel (from U Illinois) Inherently Safe LWRs (from GT) Surrogate Methods for Fuel Performance Transuranic Burning Reactors

Amount*

Co PI’s

$1,316,000 $1,485,000 $145,000 $100,000 $1,500,000 $299,000 $280,000 $270,000 $275,000 $599,000 $145,000

None None None None None None None None None None None

*Amount for which Prof Downar is Responsible

b. Industrial and Consulting Experience 1986-1992 1985-1989 1984-1987 1982-1983 1993-Present 1996-Present 2003-present 2008-present

Consultant Engineer, Reactor Analysis Division, Argonne National Laboratory, Argonne, IL Consultant Engineer, Nuclear Fuels Services, Commonwealth Edison Co., Chicago, IL Consultant Engineer, Nuclear Fuels Division, Westinghouse Corporation, Pittsburgh, PA Consultant Engineer, Fuel Management Group, Yankee Atomic Electric Company, Framingham, MA Consultant Engineer, Information Systems Laboratory, Rockville, Md. Consultant Engineer, Korea Atomic Energy Research Institute Consultant, Greylock-McKinnon, (for DOJ) Consultant, U.S. NRC ACRS, Advisory Committee on Reactor Safety

4. Other Evidence of Professional Recognition Fellow, American Nuclear Society Member of Lab Annual Review Team (2002-present), Paul Scherer Institute Member of Lab Review Team, Brookhaven National Laboratory, 2001 Member of University External Review, EPFL, Lusanne, Switzerland Referee for Professional Journals o o o o o

Reviewer for Nuclear Science and Engineering Reviewer for Nuclear Technology Reviewer for Nuclear Engineering and Design Reviewer for National Science Foundation Grant Proposals Reviewer for DOE Grant Proposals

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Other Honors and Awards • • • • • • • • •

Distinguished Graduate (U.S. Military Academy) – 1974 Best Teacher Award, U.S. Military Academy, West Point, NY – 1980 Hertz Fellow, MIT, 1980-1984 Alpha Nu Sigma (Nuclear Engineering Honor Society) – 1982 Phi Kappa Phi (National Honor Society – 1985 Sigma Xi (Scientific Research Society) – 1985 Best Paper Award, American Nuclear Society Annual Meeting, Reactor Physics Division – 1995, 1996, 2004 Best Teacher Award, School of Nuclear Engineering, Purdue – 1989, 90, 92 Outstanding Faculty Achievement, NERS, UM, 2010

Activities in Professional Societies • • • • • •

Chairman, Reactor Physics Division, American Nuclear Society, 1996 Industrial Liaison, ANS 1997 Fuel Management Topical Meeting, Myrtle Beach, NC ANS Honors and Awards Committee, 1996-1999 ANS Journals Oversight Committee, 1996-1999 Organizing Committee, PHYSOR-04, Chicago, ILL. ANS Nominating Committee, 2005-present