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Email: downar@nuc.berkeley.edu
Phone: 510-643-3288
Fax: 510-643-9685

UCB Department of Nuclear Engineering
4105 Etcheverry Hall
MC 1730
Berkeley, CA 94720-1730

Thomas J. Downar
Professor of Nuclear Engineering

Education

  • 1984  Ph.D. Massachusetts Institute of Technology.  Discipline: Nuclear Engineering
  • 1975  M.S.  Massachusetts Institute of Technology.  Discipline:  Nuclear Engineering
  • 1974  B.S.   United States Military Academy, West Point Commissioned Lieutenant in U.S. Army Corps of Engineers

Professional Experience

  • 2007-present   Professor, Department of Nuclear Engineering, UC Berkeley
  • 1998-2006       Professor, School of Nuclear Engineering, Purdue University
    engineering.purdue.edu/NE/
  • 2003-Present    Co-Director, Computer Research Institute, Purdue University
    www.cri.purdue.edu
  • 2002-Present    Director, Computational Science and Engineering Program, Purdue
    www.cse.purdue.edu
  • 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
  • Captain, Company Commander, U.S. Army, Ft. Devens, MA

Awards and Honors in Teaching & Research

  • 2002                 Fellow, American Nuclear Society
  • 1995, 96           Best Paper Award, American Nuclear Society Annual Meeting,
                             Reactor Physics Division
  • 1989, 90, 92     Best Teacher Award, School of Nuclear Engineering, Purdue
  • 1980-84            Hertz Fellow, MIT
  • 1980                 Best Teacher Award, U.S. Military Academy, West Point, NY
  • 1974                 Distinguished Graduate (U.S. Military Academy)

Professonal Ogranizations

  • Chairman, Reactor Physics Division, American Nuclear Society, 1996
  • Nominating Committee, American Nuclear Society, 2005

TEACHING

A) Courses Taught and Evaluated

 

Year

 

Semester

 

Course No.

 

Name of Course

Cred.
Hours

Rating*/
Core

 

2005

 

Spring
Fall

 

NUCL 511
NUCL 510

 

Nuclear Reactor Dynamics
Nuclear Reactor Physics

 

3
3

 

4.85/5.0
4.90/5.0

 

2004

 

Spring
Fall

 

NUCL 511
NUCL 510

 

Nuclear Reactor Dynamics
Nuclear Reactor Physics

 

3
3

 

4.80/5.0
4.75/5.0

 

2003

 

Fall

 

NUCL 510

 

Nuclear Reactor Physics

 

3

 

4.65/5.0

 

2002

 

Spring
Fall

 

NUCL 511
NUCL 510

 

Nuclear Reactor Dynamics
Nuclear Reactor Physics

 

3
3

 

4.90/5.0
4.80/5.0

Student Counseling

  • Undergraduate Committee
  • Graduate Committee
  • Advisor for Student Design Project (NUCL 450)                                           (Advisor for Team that won the 2003 National Design Competition)

Other Teaching Responsibilities

B) Research and Scholarship

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, 37-42, 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.
  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.
  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.  “Multigroup SP3 Methods for Neutronics Analysis of MOX Fueled Cores,” C. Lee and T. Downar, 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 One-dimensional 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 Three-dimensional 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 Self-Shielding Calculations,” Z.Zhong, T. Downar, M. Williams, M. DeHart, Nuclear Science and Engineering, Vol. 152, No. 4, April, 2006.
  42. 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, 156, 74-85, March,  2007.
  43. "Zirconium Matrix Cermet for a Uranium-Thorium Oxide Fuel in a SBWR", S. McDeavitt, T. Downar, A. Solomon, accepted for publication, Nuclear Technology, 157, pp 37-52, January,  2007.
  44. "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, Vol. 155, No. 3, pp. 395-408, March, 2007.

Submitted for Publication

  1.  “Coarse Mesh Finite Difference Acceleration in the Two-Dimensional Discrete Ordinates Transport Calculation,”  Z. Zhong, T. Downar, M. DeHart, K. Clarno, submitted to Nuclear Science and Engineering, January, 2006.
  2. "Parallelization in the SCALE Continuous-Energy Resonance Module GEMINEWTRN and the Transport Module NEWT,”  Z. Zhong, T. Downar, M. DeHart, M. Williams, submitted to Nuclear Science and Engineering, January, 2006.
  3. “The Implementation of Matrix Free Newton /Krylov Methods Based on a Fixed Point Iteration”,  Yunlin Xu, Thomas J. Downar, submitted for publication, Annals of Nuclear Energy,February, 2006.

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, 71-126, 1988.

c) Conference Proceedings (1996-2005)

  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
  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 12-16, 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
  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, PHYSOR-2000, 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," PHYSOR-2000, 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 TRAC-M/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.
  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, PHYSOR-2002, Seoul Korea, October, 2002.
  38. “Analysis of Control Rod Ejection Accident in MOX and MOX/UOX Cores with Time-Dependent 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, Two-Group 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,  PHYSOR-04,  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, 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, Proceedings of ANS Reactor Physics Topical Meeting PHYSOR-06, Vancouver, B.C.  September, 2006.
  54.  The Analysis of the OECD/NEA/NSC PBMR-400 Benchmark Problem Using PARCS-DIREKT, 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.

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.

Graduate Research Program

  1. M.S. Degrees Completed

Date

Name Of Student and Thesis Topic

 

 

1986

R. Launstein, 'PINCAS: A Fuel Cycle Economics Code'

1987

T. Niggel, 'Optimal Burnable Absorber Assignment for PWR Core Reload Design'

1987

D. Edwards, 'Non-linear Programming Solutions to the Minimum Fuel Loading Problem'

1987

C. Wemple, 'A Vectorized Source Algorithm for the Nodal Code SIMULATE-E'

1987

H.S. Kim, 'Effects of Availability on the Determination of Cycle Length'

1992

M. Zika, ‘Numerical Divergence Effects in Nodal Equivalence Theory’

1994

D. Phegley, ‘Harmonic Perturbation Theory for the Analysis of Boiling Water Reactor Regional Instabilities’

1995

S. Cooper, ‘The Application of the BICGSTAB Semi-Iterative Algorithm to the ARROTTA Spatial Kinetics Code’

1995

R. Janardhan, ‘A Multi-Level FGMRES Method for Parallel Calculation of Nuclear Reactor Transients’

1997

J. Chai, ‘The Application of Neural Networks and Parallel Computing to PRA’ (Co-major Professsor with L. Tsoukalas)

1997

D. Barber, ‘A Preconditioned Krylov Subspace Method for the Neutron Diffusion Problem in Hexabgonal Geometry’

1997

J. Steill, ‘Nested Krylov Methods for Fluid Dynamics’

1998

S. Spooner, ‘Reactor Dehomogenization Methods for the Advanced Nodal Methods’

1999

Q. Wang  ‘Parallel Computing Methods for Coupled Thermal-Hydarulics/Neutronics Analysis’

1999

V. Krishnan, ‘‘High Performance Computing for the Power-Flow Systems Equations’ (Co-advisor)

2000

M. Miller ‘Advanced Time Integration Methods for Coupled Field Calculations’

2001

S. Spillane, ‘Anticipatory Control of the Electric Power Grid’

2002

D. Tinkler, “Design and Analysis of a 200 MWe Simplified Boiling Water Reactor”

2004

C. Cotton, “Neutronics Methods for the Advanced CANDU Reactor”

2006

E. Swain, “Neural Networks for Power Grid Applications”

1. Ph.D. Degrees Completed

Date

Name of Student and Thesis Topic

1986

Y.J. Kim, 'Optimization of Core Reload Design for Low Leakage Fuel
Management in Pressurized Water Reactors'
(Co-Major Professor)

1988

H.R. Hwang, 'Optimal Space-Time Fuel Distribution in the Light Water Reactor'   

1989

W.S. Yang, 'Depletion Perturbation Theory for the Constrained Equilibrium Cycle'

1989

J.A. Stillman, 'The Optimum Fuel and Power Distribution for a PWR Burnup Cycle'

1993

H. Choi, 'The Design and Analysis of a Liquid Metal Reactor for Burning Minor Actinides'

1994

C. Hah, ‘The Augmented Source Method for the Application of Nodal Equivalence Theory’

1995

J. Stevens, ‘Light Water Reactor Core Reload Optimization’

1996

H. Joo, ‘An Incomplete Domain Decomposition Preconditioning Method for Nonlinear Nodal Spatial Kinetics’

1997

J. Wu, ‘The Application of Domain Decomposition and Krylov Subspace Methods to Reactor Safety Analysis’

1999

G. Jiang, ‘Multigroup Analytic Nodal Methods for MOX Fuel Analysis’

2000

C. Lee, “SP3 Methods for MOX Fuel Neutronics Analysis”

2004

D. Lee, “Numerical Convergence Analysis of the Nonlinear Nodal Method”

2004

Y. Xu, “Matrix Free Newton Krylov Methods for Coupled Nonlinear Subsystems”

2005

T. Kozlowski, “Homogenization Methods for Pin-by-Pin Neutron Transport”

2005

Z. Zhong, “Continuous Energy Multi-Dimensional Resonance Self-Shielding”

2006

J. Thomas, “The Method of Characteristics for Solution of the Integral Neutron Transport Equation in Boiling Water Reactors”

  1. Graduate Degrees in Progress

 

Degree

Name of
Student

 

Thesis Topic

Approximate
Grad. Date

Ph.D.

J. Gan

“Newton-Krylov Methods “

2006

Ph.D

V. Seker

“High Temperature Pebble Bed Gas Reactor”

2007

Ph.D

S. Clarke

“Nuclear Source Attribution”

2008

M.S.

A. Ward

“Coupled Codes for Advanced Reactor Design”

2008

Ph.D

J. Jenkins

“Advanced Fuel Cycle Initiative:  TRU Burning”

2009

Ph.D.

Z. Gao

“Subgroup Method for Resonance Self-Shielding”

2009

Ph.D.

M.Hursin

“Integral Transport for Nuclear Reactor Analysis”

2010

Ph.D.

B. Kochunas

“Coupled Field Calculations for Reactor Simulation”

2011

Professional Staff Supported

  • 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. Yunlin Xu, Visiting Professor, 2004-present
  • Dr. Mikhail Kalugin, Post-doctoral Researcher, 2005-present

Research Grants and Contracts

    a. Active (*Amount Shown is Responsibility of Prof Downar)

Source

Dates

Description

Amount*

Co PI’s

DOE NEER

2005-08

Continuous Energy, Multi-Dimensional Transport Calculations

$221,000

None

DOE UNERI

2005-08

Development of Engineered Product Storage Concept for the UREX+1 Combined TRU

$203,000

S. McDeavitt

U.S. NRC

2003-06

Neutronics Methods for MOX Fuel

$367,000

None

U.S. NRC

2003-06

TRACE Code Development

$489,500

None

U.S. NRC

2005-6

LOCA Analysis

$25,000

None

DOE (ANL)

2002-06

High Fidelity Reactor Methods

$397,000

None

Studsvik Co.

2005

Convergence Analysis of the CMFD Method

$17,100

None

Navy/NSWC

2004

Intelligent Sensor Networking

$70,000

L. Tsoukalas

Dept of Ed.

2001-05

GAANN: Computational Science Engineering (CSE)  Fellowships

$410,000

J. Mathur

NSF

2006

Dynamic Data Driven Systems:  U.S. Power Grid

$200,000

4 Others

*Amount for which Prof Downar is Responsible

 b) Proposals Under Review

Source

Dates

Description

Amount*

Co PI’s

ARN, ARGENTIA

2006-07

Reactor Analysis Methods for the ATUCHA-2 Reactor

$250,000

M. Bertodano

U.S. NRC

2006-07

Reactor Core Depletion Methods

$360,000

ORNL

U.S. NRC

2006-07

BWR Stability Analysis

$210,000

PSU

Bettis Atomic

2006-07

Advanced Linear Solvers

$90,000

None

ISL

2006-08

Reactor Spatial Kinetics Methods

$150,000

None

 c. Previously Funded

Source

Dates

Description

Amount

Co PI’s

NSF

1986-88

Optimization of Nuclear Fuel Utilization with the Cyber-205 Super Computer

$64,000

PI

EPRI

1986-87

Light Water Reactor Fuel Cycle Optimization

$45,000

PI

Westinghouse
Electric

1986-87

Core Loading Pattern Optimization for the Pressurized Water Reactor

$30,000

PI

Argonne National Laboratory

1987-90

Generalized Perturbation Theory for Fast Reactor Core Depletion Analysis

$56,000

PI

DOE

1988-91

Advanced Depletion Perturbation methods with Application to the Integral Fast Reactor

$137,000

PI

EG&G

1989-91

Sensitivity Theory for Thermal Reactor Analysis

$105,000

PI

Studsvik of America

1990-91

Light Water Reactor Loading Pattern Optimization

$37,000

PI

DOE

1993

Nodal Equivalence Theory

$40,000

PI

EPRI

1994

Fundamental Studies of Mixed Mode Multi Processing for the Solution of Linear Systems of Equations

$25,000

PI

EPRI

1995-96

Parallel Computing Methods for Reactor Simulation

$210,000

w.A. Sharon

EPRI

1995-96

Krylov Linear Solvers for the ARROTTA Spatial Kinetics Code

$10,000

Sole PI

INEL/DOE

1995-97

Spatial Kinetics for the RELAP5 Safety Analysis Code

$335,000

w/ P. Turinsky

EPRI

1997-99

The Application of Krylov Subspace Methods and Parallel Computing to Nuclear Reactor Analysis

$125,000

Sole PI

Scientech

1996-01

Advanced Methods Development for the TRAC Reactor Analysis Code

$534,000

w/V. Ransom

Scientech

1997-01

Advanced Methods Development for the RELAP5 Reactor Analysis Code

$622,000

w/V. Ransom

SAIC

1996-97

Krylov Subspace Methods for Hexagonal Geometry

$30,000

Sole PI

U.S. NRC

1997-00

A Parallel Numerical Solution Algorithm for the TRAC Systems Code

$180,300

Sole PI

U.S. NRC

1998-02

Methods Development for Reactor Spatial Kinetics

$1,020,000

Sole PI

EPRI/DOD

1999-02

Intelligent Management of Electric Power Grid

$505,000

w/Tsoukalas,
Bement

DOE NERI

1999-02

Simplified Boiling Water Reactor

$806,000

(w/M. Ishii)

DOE NERI

1999-02

High Conversion Reactor

$640,000

w/ BNL

DOE NERI

1999-02

Thorium Fuel Cycle

$539,000

w/ANL

DOE NEER

2001-05

Adaptive Neutron Transport Methods

$211,000

E. Lewis

 Industrial and Consulting Experience

1986-1992

Consultant Engineer, Reactor Analysis Division, Argonne National Laboratory, Argonne, IL

1985-1989

Consultant Engineer, Nuclear Fuels Services, Commonwealth Edison Co., Chicago, IL

1984-1987

Consultant Engineer, Nuclear Fuels Division, Westinghouse Corporation, Pittsburgh, PA

1982-1983

Consultant Engineer, Fuel Management Group, Yankee Atomic Electric Company, Framingham, MA

1993-Present

Consultant Engineer, Information Systems Laboratory, Rockville, Md.

1996-Present

Consultant Engineer, Korea Atomic Energy Research Institute

2003-present

Consultant, U.S. Department of Justice

2003-
present

Consultant, U.S. NRC

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

Referee for Professional Journals

    • Reviewer for Nuclear Science and Engineering
    • Reviewer for Nuclear Technology
    • Reviewer for Nuclear Engineering and Design, ANS Annual Conference, 1987
    • Reviewer for National Science Foundation Grant Proposals
    • Reviewer for DOE Grant Proposals

Professional Meetings

  • Session Organizer, numerous ANS meetings
  • Organizing committee, numerous topical meetings, (e.g. PHYSOR-04)

Other Honors and Awards

  • 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
  • School of Nuclear Engineering Nominee for Purdue University Amoco Best Teacher Award
  • Best Teacher Award, U.S. Military Academy, West Point, NY – 1980
  • Alpha Nu Sigma (Nuclear Engineering Honor Society) – 1982
  • Phi Kappa Phi (National Honor Society – 1985
  • Sigma Xi (Scientific Research Society) – 1985
  • Distinguished Graduate (U.S. Military Academy) – 1974
  • Hertz, Fellow, MIT – 1980-1983

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
  • ANS Nominating Committee, 2005-present

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