Publications

 

Books and Chapters of Books:

 

    1. Nuclear Power Reactor Safety, John Wiley & Sons, New York, l977, 630 pp.
    2. "Finite Element Approximations to the Even-Parity Transport Equation," in Adv. Nucl. Science and Technology, Vol. l3, J. Lewins & M. Becker (eds.), Plenum Press, New York, l98l.
    3. (with J. J. Duderstadt and C. Bardos), Neutron Transport Equation, Editions Eyrolles, Paris, l983.
    4. (with W. F. Miller, Jr.), Computational Methods in Neutron Transport, John Wiley & Sons, New York, l984, 40l pp. (Republished by Am. Nucl. Soc. 1993)
    5. Japanese Edition, Nuclear Power Reactor Safety, Vols. l & 2, Tuttle-Mori Agency, Inc., Tokyo, l985 & l986.
    6. Introduction to Reliability Engineering, John Wiley & Sons, New York, l987, 400 pp.
    7. (second edition , 1995)
    8. ( with F. Boehm), "A Stress-Strength Interference Methodology for Ceramic Component Reliability Analysis," Computational Mechanics of Probabilistic and Reliability Analysis, W. K. Liu & T. Belytschko (eds.) Elme Press Int., 1989
    9. Masterworks of Technology: The Story of Creative Engineering, Architecture, and Design, Prometheus Books, Amherst, NY, Scheduled publication: fall 2004
    10. “Second-Order Methods,” Neutronics Computational Methods, Y. Azmy Editor, Kluwer Academic Publishers, NY Scheduled publication: 2006
    11. Fundamentals of Nuclear Reactor Physics, Academic Press imprint of Elsevier Science, in press

 

Archival Journals

 

    1. "A Generalization of the Dirac Chord Method to Include Charged Particle Phenomena," Nucl. Sci. Eng. 25, 359-364 (l966).
    2. (With R. Pfeffer): "The Influence of Source Geometry on Fission-Fragment Escape Properties," Nucl. Sci. Eng. 27, 58l-585 (l967).
    3. "An Extension of the Path-Length Formalism to Anisotropic Charge-Particle Sources," Nucl. Sci. Eng. 28, 3ll-3l2 (l967).
    4. (With F. T. Adler): "A Boltzmann Integral Equation Treatment of Resonance Absorption in Reactor Lattices," Nucl. Sci. Eng. 3l, ll7-l26 (l968).
    5. "A Polynomial Approximation for Integral Transport Calculations," J. Nucl. Energy 23, 87-97 (l969).
    6. (With S. T. Huang): "A Comparison of P1 Vacuum Boundary Conditions," Nucl. Sci. Eng. 42, 4l8-4l9 (l970).
    7. "A Transient Heat Conduction Model for Reactor Fuel Elements," Nucl. Eng. & Design l5, 33-40 (l97l).
    8. (With S. T. Huang): "Asymptotic PN and Double PN Approximations," J. Nucl. Energy 26, 23l-236 (l972).
    9. (With L. A. Semenza and E. C. Rossow): "The Application of the Finite Method to the Multigroup Neutron Diffusion Equation," Nucl. Sci. Eng. 47, 302-3l0 (l972).
    10. (With W. F. Miller, Jr. and E. C. Rossow): "The Application of Phase-Space Finite Elements to One-Dimensional Neutron Transport Problems," Nucl. Sci. Eng. 51, l48-l56 (l973).
    11. (With W. F. Miller, Jr. and E. C. Rossow): "The Application of Phase-Space Finite Elements to the Two-Dimensional Transport Equation in x-y Geometry," Nucl. Sci. Eng. 52, l2-22 (l973).
    12. (With L. L. Briggs and W. F. Miller, Jr.): "Ray Effect Mitigation in Discrete Ordinate-Like Angular Finite Element Approximations," Nucl. Sci. Eng. 57, 205-2l7 (l975).
    13. (With W. F. Miller, Jr. and T. P. Henry): "A Two-Dimensional Finite Element Method for Integral Neutron Transport Calculations," Nucl. Sci. Eng. 58, 203-2l2 (l975).
    14. (With L. L. Briggs): "A Comparison of Constrained Finite Elements and Response Matrices as one Dimensional Transport Approximations," Nucl. Sci. Eng. 63, 225-235 (l977).
    15. "Progress in Multidimensional Neutron Transport Computations," Nucl. .Sci. Eng. 64, 278-292 (l977).
    16. (With R. N. Blomquist): "A Rigorous Treatment of Transverse Buckling Effects in Two-Dimensional Neutron Transport Computations" Nucl. Sci. Eng. 73, l25-l39 (l980).
    17. (With L. L. Briggs): "Application of Constrained Finite Elements to Two- Dimensional Lattice Problems," Nucl. Sci. Eng. 75, 76-97 (l980).
    18. (With H. A. Ozgener): "The Constrained Finite Element Approach to Coarse-Mesh Transport Computations," Annals Nucl. Energy 8, 683-687 (l98l).
    19. (with Wm. A. Thomas): "Two Vectorized Algorithms for the Solution of Three- Dimensional Neutron Diffusion Equations," Nucl. Sci. Eng. 84, 67-7l (l983).
    20. (with F. Boehm): "Monte Carlo Simulation of Markov Unreliability Models," Nucl. Eng. & Design 77, 49-62 (l984).
    21. (with I. Dilber): "Variational Nodal Methods for Neutron Transport," Nucl. Sci. Eng. 9l, l32-l42 (l985).
    22. (with Z. Tu): "Component Dependency Models in Markov Monte Carlo Reliability Analysis," Reliability Engr. 13, 45-6l (l985).
    23. (with I. Dilber): "Finite Elements, Nodal and Response Matrix Methods: A Variational Synthesis for Neutron Transport," Prog. Nucl. Energy 18, 63-74 (l986).
    24. (with Z. Tu): "Monte Carlo Modeling by Inhomogeneous Markov Processes," Reliability Engr. 16, 277-296 (l986).
    25. (25) (with L. Olvey): "Accuracy Comparisons for Variational R, T and T-1 Response Matrix Formulations," Annals Nucl. Energy 14, 203-209 (l987).
    26. "Interface Angular Coupling Reductions in Variational Nodal Methods for Neutron Transport," Nucl. Sci. Eng. 102, 140-152 (1989)
    27. (with U. R. Hanebutte and R. F. Stefan): "A Two-Dimensional Nonlinear Response Matrix Method with Scattering and Absorption-Emission," Transport Theory and Statistical Physics, 19, 387-404, (1990)
    28. (with F. Boehm): "A Stress-Strength Interference Approach to Reliability Analysis of Ceramics, Part I: Fast Fracture," Probabilistic Engr. Mech. 7, 1-8 (1992)
    29. (with F. Boehm): "A Stress-Strength Interference Approach to Reliability Analysis of Ceramics, Part II: Delayed Fracture," Probabilistic Engr. Mech. 7, 9-14 (1992)
    30. (with U. R. Hanebutte): " A Massively Parallel Discrete Ordinate Response Matrix Method for Neutron Transport," Nucl. Sci. Eng. 111, 46-56 (1992)
    31. (with C. B. Carrico and G. Palmiotti): " Three-Dimensional Variational Nodal Transport Methods for Cartesian, Triangular and Hexagonal Criticality Calculations," Nucl. Sci. Eng. 111, 168-179 (1992)
    32. (with G. Palmiotti and C. B. Carrico) " Variational Nodal Transport Methods with Anisotropic Scattering," Nucl. Sci. Eng 115 233-243 (1993)
    33. (with H-C. Chen); " Load-Capacity Interference Theory and the Bathtub Curve," IEEE Trans. Reliability, 43,470-476 (1994)
    34. (with C. B. Carrico and G. Palmiotti), "Variational Nodal Formulation for the Spherical Harmonics Equations," Nucl. Sci. Eng., 122, 194-203 (1996)
    35. (with K. F. Laurin-Kovitz ), "Variational Nodal Transport Perturbation Theory," Nucl. Sci. Eng., 123, 369-380 (1996)
    36. (with G. Palmiotti), "Simplified Spherical Harmonics in the Variational Nodal Method," Nucl. Sci. Eng., 126, 48-58 (1997)
    37. (with G. Palmiotti) “ Red-Black Response Matrix Acceleration by Transformation of Interface Variables,” Nucl. Sci. Eng. 130, 181-193 (1998)
    38. "A Load-Capacity Interference Model for Common-Mode Failures in 1-out-of-2:G Parallel Systems," IEEE Trans. on Reliability, 50, 47-51 (2001)
    39. (with H. Zhang ) "An Adaptive Approach to Variational Nodal Diffusion Problems," Nucl. Sci. & Eng., 137, 1-9 (2001)
    40. (with W. S. Yang & G. Palmiotti ), "Numerical Optimization of Computing Algorithms of rhe Variational Nodal Method Based on Transformations of Variables" Nucl. Sci. & Eng 139 174-185 (2001)
    41. (with H. Zhang), “Spatial Adaptivity Applied to the Variational Nodal Pn Equations,” Nucl. Sci. & Eng. 142, 1-7 (2002)
    42. (with M. A. Smith, N. Tsoulfanidis, G. Palmiotti and T. A. Taiwo), " A Finite Subelement Generalization of the Variational Nodal Method," Nucl. Sci. & Eng 144, 36-46 (2002)
    43. (with M. A. Smith, G. Palmiotti and N. Tsoulfanidis), “An Integral Form of the Variational Nodal Method” Nucl. Sci. & Eng. 146, 141 (2004).
    44. “Much Ado about Nothing: Response Matrices for Void Regions,” Ann. Nucl. Energy, 31, 2025-2037 (2004)
    45. (with M. A. Smith and Byung-Chan Na), “ Benchmark on Deterministic 2-D MOX Fuel Assembly Transport Calculations without Spatial Homogenization,” Prog. Nucl. Energy, 45, 107-118 (2004)
    46. (with W. S. Yang, M. A. Smith, and G. Palmiotti), “ Interface Conditions for Spherical Harmonics Methods,” Nucl. Sci. & Eng. 150, 1-10 (2005)
    47. (with Hui Zhang), “Generalization of the Variational Nodal Method to Spherical Harmonics Approximations in R-Z Geometry." Nucl. Sci. & Eng. 152, 29-36 (2006)
    48. ( with M. A. Smith and Byung-Chang Na), “Benchmark on Deterministic 3-D MOX Fuel Assembly Transport Calculations without Spatial Homogenization,” Progress Nucl. Energy, 48, 383-393, 2006
    49. (with S. Van Criekingen and R. Beauwens), “Mixed-Hybrid Transport Discretizaton Using Even and Odd PN Expansions,” Nuc. Sci. & Eng. 152, 149-163 (2006)
    50. (with S. Van Criekingen, R Beauwens and J. W. Jerome ), “Mixed-Hybrid discretization Methods for the Linear Boltzmann Transport Equations,” Comput. Methods Appl. Mech. Eng. ( accepted for publication)

 

Refereed Meeting Proceedings and Transactions

 

    1. (With F. T. Adler): "Exact Solution of the Slowing Down Equations in Lattices," Trans. Am. Nucl. Soc. 5, 4ll (l962).
    2. (With F. T. Adler): "Comparison of Exact and Approximate Treatments of Resonance Effects in Cylindrical Lattices," Trans. Am. Nucl. Soc. 7, 29 (l964).
    3. (With D. B. Adler and F. T. Adler): "A Family of FORTRAN Routines for the Analysis of Neutron Resonance Effects," Proc. Conf. on the Application of Computing Methods to Reactor Problems, May l7-l9, l965, 457-470, ANL-5070.
    4. "Polynomial Flux Approximations in Integral Transport Theory," Trans. Am. Nucl. Soc. 10, 547 (l967).
    5. "An Asymptotic P3 Approximation," Trans. Am. Nucl. Soc. 11, No. 2, 55l-552 (l968).
    6. "A Comparison of Two Exact Transport Methods," Trans. Am. Nucl. Soc. l2, 428-429 (l969).
    7. (With B. M. Bingman): "An Approximate Monte Carlo Treatment of Resonance Absorption in Reactor Lattices," Trans. Am. Nucl. Soc. l4, 2l9 (l97l).
    8. (With L. A. Semenza and E. C. Rossow): "A Finite Element Treatment of Neutron Diffusion," Trans. Am. Nucl. Soc. 14, 200-201 (l97l).
    9. (With B. A. Zolotar, M. Salvatores and B. M. Bingman): "A Comparative Study of Heterogeneity Treatments for ZPR Place Cells," Trans. Am. Nucl. Soc. l4, 848-849 (l97l).
    10. (With B. Snyder): "BWR Control-Rod Withdrawal Optimization Using Dynamic Programming," Trans. Am. Nucl. Soc. l4, 646 (l97l).
    11. (With W. F. Miller, Jr. and E. C. Rossow): "Transport Solutions Using Finite Elements in Space-Angle Phase Space," Trans. Am. Nucl. Soc. 14, 65l-652 (l97l).
    12. (With L. A. Semenza and E. C. Rossow): "Dual Finite Element Methods for Neutron Diffusion," Trans. Am. Nucl. Soc. 14, 662-664 (l971).
    13. (With L. A. Semenza and E. C. Rossow): "Finite Element Neutron Diffusion in Curvilinear Coordinates," Trans. Am. Nucl. Soc. 15, 780 (l972).
    14. (With W. F. Miller, Jr. and E. C. Rossow): "Two Dimensional Transport Calculations Using Phase-Space Finite Elements," Trans. Am. Nucl. Soc. 15, 780-781 (l972).
    15. (With B. Snyder): "Optimal Control Rod Policies for an Operating Cycle of a Simulated Boiling-Water Reactor Core," Proc. Natl. Topical Conf. on Mathematical Models and Computational Techniques for Analysis of Nuclear Systems, April 9-ll, l973, Ann Arbor, Michigan.
    16. (With T. R. Tramm): "Integral Control Rod Predictions for a BWR", Trans. Am. Nucl. Soc. l6, l7l (l973).
    17. (With D. T. Eggen, C. D. Livengood and R. H. Shum): "Evaluation of a Back-up Safety Device for LMFBR," Trans. Am. Nucl. Soc. 16, l88 (l973).
    18. (With W. F. Miller, Jr.): "Quadratic Finite Elements in Neutron Transport," Trans. Am. Nucl. Soc. 16, 235 (l973).
    19. (With W. F. Miller, Jr.): "Finite Element Integral Neutron Transport," Trans. Am. Nucl. Soc. 16, 238 (l973).
    20. (With M. B. Snyder): "Optimal Control Rod Policies for an Operating Cycle of a Simulated Boiling Water Reactor Core," Trans. Am. Nucl. Soc. 16, 2, (l973).
    21. (With L. L. Briggs and W. F. Miller, Jr.): "Ray-Effect Mitigation in Discrete-Ordinate-Like Equation," Trans. Am. Nucl. Soc. 19, l65 (l974).
    22. (With Y. C. Yuan and W. F. Miller, Jr.): "Iterative Solution Methods for Two-Dimensional Finite Element Approximations in Neutron Transport," Proc. ANS Topical Meeting on Computational Methods in Nuclear Engineering, April l5-l7, l975, Charleston, S.C., CONF-750413, Vol. II, pp. III-85-III-95 (l975).
    23. (With Y. C. Yuan): "Two Dimensional Multigroup Transport Calculations Using Phase-Space Finite Elements," Trans. Am. Nucl. Soc. 2l, 227 (l975).
    24. (With R. E. Alcouffe): "Synthetic Acceleration Methods for the Neutron Transport Equation," Proc. Tech. Comm. Meeting on Methods of Neutron Transport Theory in Reactor Calculations, Bologna, Italy, Nov. 3-5, l975, (also appeared as Los Alamos Scientific Laboratory Report LA-UR-l56l).
    25. (With W. F. Miller, Jr.): "A Comparison of P1 Synthetic Acceleration Techniques," Trans. Am. Nucl. Soc. 23, 202 (l976).
    26. (With L. L. Briggs): "A Variational Coarse-Mesh Transport Method Based on Constrained Angular Trial Functions," Trans. Am. Nucl. Soc. 24, l83 (l976).
    27. "Conjugate Gradient Solutions to the Discrete Ordinates Equation," Trans. Am. Nucl. Soc. 25, 225-226 (l977).
    28. (With D. R. McCoy, M. J. Lee, L. L. Briggs and R. N. Blomquist): "The Inclusion of Buckling Approximations in Finite Element Neutron Transport Equations," Trans. Am. Nucl. Soc. 25, 226-227 (l977).
    29. "Finite Element Methods for Radiation Transport Calculations," Trans. Am. Nucl. Soc. 25, 474-475 (l977).
    30. (With L. L. Briggs): "Two Dimensional Transport Applications of Constrained Finite Elements, Trans. Am. Nucl. Soc. 27, 350-35l (l977).
    31. "Reactor Safety Education at Northwestern University," Trans. Am. Nucl. Soc. 27, l09-ll0 (l977).
    32. (With R. N. Blomquist): "Complex Trial Functions in the Even-Parity Transport Equation," Trans. Am. Nucl. Soc. 28, 256-257 (l978).
    33. (With R. N. Blomquist): "Assessment of DB2 Transverse Leakage Predictions in Neutron Transport Calculations," Trans. Am. Nucl. Soc. 32, 308-3l0 (l979).
    34. (With C. H. Adams): "A Modified Transport Formulation Compatible with Anisotropic Diffusion Theory," Trans. Am. Nucl. Soc. 33, 3l9-320 (l979).
    35. (With H. A. Ozgener): "Multigroup Criticality Calculations for Nonuniform Lattices Using a Constrained Finite Element Method," Trans Am. Nucl. Soc. 35, 235-236 (l980).
    36. "A Generalization of the Benoist Formalism for Anisotropic Neutron Transport Computation," Proc. ANS/ENS International Topical Meeting on Advances in Mathematical Methods for Nuclear Engineering Problems, April 27-29, l98l, Munich, Germany, pp. l88-l94.
    37. (With C. D. Swanson): "Comparison of Vector Computer Methods for the Solution of Slab Geometry Neutron Transport Problems," Proc. ANS/ENS International Topical Meeting on Advances in Mathematical Methods for Nuclear Engineering Problems, April 27-29, 198l, Munich, Germany, pp. 549-563.
    38. "Anisotropic Neutron Transport in r-z Geometry," Trans. Am. Nucl. Soc. 37, 220-22l (l98l).
    39. (with P. Ellison): "A Coarse Mesh Finite Element Method for Boiling Water Reactor Analysis," Proc. Am. Nucl. Soc. Topical Meeting on Advances in Reactor Computations, Salt Lake City, Utah, March 28-3l, l983, pp. l0l6-l029, American Nuclear Society, l983.
    40. (with J. E. Langan): "Variance Reduction by Forced Failure in Monte Carlo Unreliability Analysis," Trans. Am. Nucl. Soc. 44, 365-366 (l983).
    41. "Preface," Proc. Am. Nucl. Soc. Topical Meeting on Advances in Reactor Computations, Salt Lake City, Utah, March 28-3l, l983, American Nuclear Society, l983.
    42. (with F. Boehm): "Markov Monte Carlo Reliability Analysis," Trans Am. Nucl. Soc. 45, 329-330 (l983).
    43. (with I. Dilber): "A Comparison of Variational Coarse-Mesh Methods," Trans. Am. Nucl. Soc. 46, 40l-402 (l984).
    44. "Monte Carlo Markov Analysis," Proc. Intl. 84 Athens AMSE Summer Conf. on Modeling and Simulation, Vol. l, ll7-l2l, l984.
    45. (with I. Dilber): "Two Dimensional Variational Coarse Mesh Methods," Proc. Am. Nucl. Soc. Topical Meeting on Reactor Physics and Shielding, Chicago, Sept. l7-l9, l984.
    46. (with L. Olvey): "Monte Carlo Unavailability Analysis," Trans. Am. Nucl. Soc. 47, 329 (l984).
    47. (with I. Dilber): "A Variational Nodal Transport Method," Trans. Am. Nucl. Sci. 49, 225-226 (l985).
    48. (with Z. Tu): "Component Dependency Modeling in Markov Monte Carlo Calculations," Trans. Am. Nucl. Soc. 49, 287 (l985).
    49. (with Z. Tu): "Monte Carlo Simulation of Reliability Problems," Proc. ASME Pressure Vessel & Piping Conf., PVP-Vol. 98-5, New Orleans, June 24-26, l985.
    50. (50) "The Source Term," Proc. Health Physics Conference, Evanston, Ill., June 3-7, l985.
    51. (51) (with W. F. Miller, Jr.): "A Nonlinear Response Matrix Method for Radiative Transfer in Absorbing-Emitting Media," Proc. Intl. Topical Meeting on Advances in Reactor Physics, Mathematics and Computation, Paris, April 27-30, l987.
    52. (with F. Boehm, U. P. Hald & Z. Tu): "Generalization of Markov-Monte Carlo Reliability Analysis to Include Non-Markovian Maintenance Strategies," Proc. Int. Topical Conf. Probabilistic Safety Assessment and Risk Management, Zurich, Aug. 30-Sept. 4, l987, Verlag TUV Rheinland, l987.
    53. "Improvement of Variational Nodal Transport Methods by Lagrange Multiplier Techniques," Trans. Am. Nucl. Soc. 55, 349-350 (l987).
    54. (with Z. Tu, U. P. Hald and F. Boehm): "Explicit Time-Dependent Analysis in Monte Carlo Reliability Simulations," Trans. Am. Nucl. Soc. 55, 443-444 (l987).
    55. (with V. Schaber and F. Boehm): "Monte Carlo Simulation of Buffered Production Lines," Quality: Design, Planning and Control PED - Vol. 27, pp. 37-45, Am. Soc. Mech. Engr., l987.
    56. (with F. Boehm and U. P. Hald): "Parts Renewal in Continuous-Time Monte Carlo Reliability Simulation," Proc. l988 Reliability and Maintainability Symposium, Jan. 2l-28, l988, Los Angeles, pp. 345-349.
    57. (with U. R. Hanebutte and R. F. Stefan): "A Two-Dimensional Nonlinear Response Matrix Method with Scattering and Absorption-Emission," Trans. Am. Nucl. Soc. Tpcl. Meeting on Advances in Nuclear Engineering, Computation and Radiation Shielding, Sante Fe, NM. April 9-13, 1989
    58. ( with F. Boehm, C. Kirsch and B. P. Kelkhoff), "Monte Carlo Simulation of Complex System Mission Reliability," Proc. 1989 Winter Simulation Conference, Washington D. C., Dec. 4-6, 1989
    59. "Response Matrix Methods Revisited," Trans. Am. Nucl. Soc. 59, (1989)
    60. (with U. R. Hanebutte): " A Discrete Ordinate Response Matrix Method for Massively Parallel Computers," Proc. Int. Meeting, Adv. in Mathematics , computations, and Reactor Physics, Pittsburgh, PA, April 28 - May 1, 1991, Vo1. 1, 1.1 1-1,11, Am. Nucl. Soc. 1991
    61. ( with C. B. Carrico): "Variational Nodal Solution Algorithms for Multigroup Criticality Problems," Proc. Int. Meeting, Adv. in Mathematics , computations, and Reactor Physics, Pittsburgh, PA, April 28 - May 1, 1991, Vol. 2, 7.1 4-1,10, Am. Nucl. Soc. 1991
    62. ( with U. R. Hanebutte and C. B. Carrico): "Comparison of Sn and Pn Response Matrix Methods for Massively Parallel Computers, "Trans. Am. Nucl. Soc. 63, 181-182 (1991)
    63. (with C. B. Carrico and G. Palmiotti): "Nodal Variational Transport Methods for Triangular and Hexagonal Geometries," Trans. Am. Nucl. Soc. 63, 186-187 (1991)
    64. (with C. B. Carrico and G. Palmiotti): "Variational Nodal Methods in Three Dimensions: Cartesian, Triangular and Hexagonal Geometries" Trans. Am. Nucl. Soc. 63, 173-174 (1991)
    65. (with U. R. Hanebutte): "A Generalized Discrete Ordinate Response Matrix Formulation for Anisotropic Scattering," Trans. Am. Nucl. Soc. 63, 178-179 (1991)
    66. (with U. R. Hanebutte): "A Massively Parallel Algorithm for Radiative Transfer Calculations," ASME paper: 91-WA-HT-10, Dec. 1991
    67. (with C. B. Carrico and G. Palmiotti): "A Reduced Trial Function Set for the Variational Nodal Methods" Trans. Am. Nucl. Soc. 64, 200-202 (1992)
    68. (with U. R. Hanebutte): "A Massively Parallel Nodal Discrete Ordinate Method," Trans. Am. Nucl. Soc. 64, 199-200 (1992)
    69. (with C. B. Carrico and G. Palmiotti): "The Variational Nodal Method: A Three-Dimensional Transport Method in Cartesian, Triangular and Hexagonal Geometries, "Trans. Am. Nucl. Soc. 66, 265-266 (1992)
    70. (with G. Palmiotti and C. B. Carrico): "Generalization of the Variational Nodal Method to Include Anisotropic Scattering," Trans. Am. Nucl. Soc. 66, 271-272 (1992)
    71. (with U. R. Hanebutte and K. Laurin-Kovitz): " Massively Parallel Red/Black Algorithms for X-Y-Z Response Matrix Equations," Trans. Am. Nuc. Soc. 66, 275-276(1992)
    72. (with C. B. Carrico and U. R. Hanebutte); "Comparison of Space-AngleApproximations in Response Matrix Algorithms, Proc. Joint Int. Conf. Mathematical Methods and Supercomputing in Nuclear Applications, Karlsruhe, Germany, April 19-23, 1993
    73. (with U. R. Hanebutte): "Massively Parallel Performance of Neutron Transport Response Matrix Algorithms," Proc. Joint Int. Conf. Mathematical Methods and Supercomputing in Nuclear Applications, Karlsruhe, Germany, April 19-23, 1993
    74. (with T. Belytschko, B. Moran, H. H. Harkness and M. Platt, "Computational Methods for Fatigue Reliability," Durability of Metal Aircraft Structures, (eds. S. N. Atluri, C. E. Harris, A. Hoggard, N. Miller and S. G. Sampath), Proc. Int. Workshop on Structural Integrity of Aging Airplanes, pp. 146-159, March 31 - April 2, 1992
    75. (with K. Laurin-Kovitz), "The Adjoint Variational Nodal Method," Trans. Am. Nuc. Soc. 69 323-324(1993)
    76. (with H-C. Cheng), "Loads, Capacity and Failure Rate Modeling," Trans. Am.Nuc. Soc. , 70, 231-232 (1994)
    77. (with C. B. Carrico and G. Palmiotti); "Matrix Rank in Variational Nodal Approximations, Trans. Am. Nuc. Soc. 70, 162-163 (1994)
    78. (with K. Laurin-Kovitz), "Perturbation Formulation for the Variational Nodal Method;" Trans. Am. Nuc. Soc. 70, 161-162 (1994)
    79. (with G. Palmiotti and c. B. Carrico); "VARIANT - Variational Anisotropic Nodal Transport, Proc. Int. Conf. on Mathematics and Computations, Reactor Physics, and Environmental Analysis, Vol 2, 1165-1167 Portland Oregon, April 30- May 4, 1995 American Nuclear Society, 1995
    80. "Monte Carlo Reliability Simulation", Proc. Int. Conf. on Mathematics and Computations, Reactor Physics, and Environmental Analysis, Vol 1, 94-102,Portland Oregon, April 30- May 4, 1995 American Nuclear Society, 1995
    81. (with G. Palmiotti and c. B. Carrico); "Progress and Applications of the Variational Nodal Method, Proc. Int. Conf. on Mathematics and Computations, Reactor Physics, and Environmental Analysis, Vol 1 449-507,Portland Oregon, April 30- May 4, 1995, American Nuclear Society 1995
    82. (with K. F. Laurin-Kovitz): "Perturbation Theory Based on the Variational Nodal Transport Method in X-Y-Z Geometry, Proc. Int. Conf. on Mathematics and Computations, Reactor Physics, and Environmental Analysis, Vol 2 , 970- 979,,Portland Oregon, April 30- May 4, 1995, American Nuclear Society 1995
    83. (with G. Palmiotti): "Comparison of Simplified and Standard Spherical Harmonics in the Variational Nodal Method," Tran. Am. Nuc. Soc, 73, 200-201 (1995)
    84. "A Stochastic Model for Common Mode Effects in Redundant Systems," Tran. Am. Nuc. Soc, 75, 135-136 (1996)
    85. (with K. F. Laurin-Kovitz and G. Palmiotti), "Variational Nodal Perturbation Calculations Using Simplified Spherical Harmonics," Tran. Am. Nuc. Soc, 75, 130-131 (1996)
    86. (with G. Palmiotti, H. S. Khalil, K. Laurin-Kovitz, T. Fanning and U. R. Hanebutte), "Three-Dimensional Transport with Variational Nodal Methods, Proc. OECD Seminar on 3D Deterministic Radiation Transport Computer Programs: Features, Applications and Perspectives, Paris, Dec 2-3, 1996
    87. (with U. R. Hanebutte, M. Tatsumi, G. Palmiotti, and H. S. Khalil), " Response Matrix Transport Calculations on Parallel Computers," Proc. OECD Seminar on 3D Deterministic Radiation Transport Computer Programs: Features, Applications and Perspectives, Paris, Dec 2-3, 1996
    88. (with G. Palmiotti), "An Acceleration Technique for Red-Black Response Matrix Algorithms," Proc. Int. Conf. Mathematical Methods and Supercomputing for Nuclear Applications, Saratoga Springs, NY, Oct 6-10, 1997
    89. (with K. Laurin-Kovitz and G. Palmiotti), "Variational Nodal Perturbation with Anisotropic Scattering," Proc. . Int. Conf. Mathematical Methods and Supercomputing for Nuclear Applications, Saratoga Springs, NY, Oct 6-10, 1997
    90. (with Hui Zhang )"Error Estimation for Variational Nodal Calculations," Trans. Am. Nuc. Soc, 77,145 (1998)
    91. (with G. Palmiotti) ," A Finite Subelement Formulation of the Variational Nodal Method,"
    92. Tran. Am. Nuc. Soc, 77, 146 (1998)
    93. “Primal, Mixed and Hybrid Finite Elements for Neutronics Computations,” Proc. Int. Conf. Mathematics and Computation, Reactor Physics and Environmental Analysis of Nuclear Systems, Madrid, 27-30 Sept. 1999
    94. (with G., Palmiotti and T. Taiwo) “ Space-Angle Approximations in the Variational Nodal Method,” ,” Proc. Int. Conf. Mathematics and Computation, Reactor Physics and Environmental Analysis of Nuclear Systems, Madrid, 27-30 Sept. 1999,
    95. (with Hui Zhang) “An Adaptive Method within the Variational Nodal Framework,” ,” Proc. Int. Conf. Mathematics and Computation, Reactor Physics and Environmental Analysis of Nuclear Systems, Madrid, 27-30 Sept. 1999,
    96. (with G. Palmiotti and T. Taiwo), “ Finite Subelements for Whole Core Variational Nodal Calculations,” Trans. Am. Nuc. Soc. 78 (1999)
    97. M. A. Smith, N. Tsoulfanidis, E. E. Lewis, G. Palmiotti & T. A. Taiwo, "Whole-Core Neutron Transport Calculations without Cross Section Homogenization", Proc. Eighth International Conference on Nuclear Engineering , Baltimore, April 2-6, 2000,
    98. M. A. Smith, N. Tsoulfanidis, E. E. Lewis, G. Palmiotti & T. A. Taiwo, "Whole-Core Neutron Transport Calculations without Fuel-Coolant Homogenization", Proc. .Int.. Mtg Advances in Reactor Physics and Mathematics and Computation into the Next Millennium. Pittsburgh, May 7-11, 2000
    99. W. S. Yang, G. Palmiotti & E. E. Lewis, "Numerical Optimization of Computing Algorithms of the Variational Nodal Method," Proc. Int.. Mtg Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, Pittsburgh, May 7-11, 2000
    100. (with G Palmiotti), "Recent Progress in Variational Nodal Methods for Whole-Core Neutron Transport Calculations," Trans. Am. Nucl. Soc. 83, 296-297 (2000)
    101. (with M. A. Smith, N. Tsoulfanidis, R. N. Blomquist & G. Palmiotti) "Neutron Transport Validation of Variational Nodal Subelement Methods," Proc. Fourth Int. Conf. Supercomputing in Nuclear Applications, Tokyo, Sept. 4-7, 2000
    102. (with S. VanCriekingen),, "Neutron Diffusion Response Matrices from Mixed Formulations," Trans. Am. Nucl. Soc. 83, 430-431 (2000)
    103. (with M. A. Smith, N. Tsoulfanidis & G. Palmiotti ), "Comparison of Angular Approximations for PWR Cell Calculations," Trans. Am. Nucl. Soc. 84, 90-92 (2001)
    104. H. Zhang & E. E. Lewis, "Spatial Adaptivity Applied to the Nodal Pn Equations," Proc. Am. Nucl. Soc. Int. Mtg. Mathematical Methods for Nuclear Applications, Salt Lake City, Sept. 9-13, 2001
    105. “Nodal Transport Methods in Retrospect,”, Trans. Am. Nucl. Soc.85, 281-283 (2001))
    106. (with C.-H. Lee, T. Kozlowski, & T. J. Downar) “Adaptive Methods for Nodal and Pin-by-Pin Multigroup Transport Neutronics Calculations,” Trans. Am. Nucl. Soc. 86, 175-176 (2002)
    107. (with M. A. Smith, N. Tsoulfanidis & G. Palmiotti), “Higher Order Angular Capabilities of the VARIANT Code,” Trans. Am. Nucl. Soc. 86, 321-322 (2002)
    108. (with M. A. Smith, N. Tsoulfanidis, G. Palmiotti and T. A. Taiwo), "Results for the G5G7 Benchmark Problem,” Proc. Int. Conf.: Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, Seoul, Korea, Oct 7-10,2002)
    109. (with M. A. Smith, N. Tsoulfanidis, G. Palmiotti and T. A. Taiwo), " A Finite Subelement Generalization of the Variational Nodal Method," Trans. Am. Nucl. Soc. 87 421-422 (2002)
    110. (with M. A. Smith, G. Palmiotti and N. Tsoulfanidis), “Even-Parity Integral Transport Enhancement of the Variational Nodal Method,” Trans. Am. Nucl. Soc. 87 127-128 (2002)
    111. (with Ferrero, N. Tsoulfanidis ), “Homogenization Effects on Neutron Flux Monte Carlo Calculations for Accelerator Driven Systems,” Trans. Am. Nucl. Soc. 89, 635-637 (2003)
    112. (with M. A. Smith, G. Palmiotti, T. A. Taiwo, and N. Tsoulfanidis),, “Two-and Three-Dimensional Results for the C5G7 Benchmark Problem using the Variational Nodal Method,” Trans. Am. Nucl. Soc. 89, ,(2003)
    113. (with M. A. Smith & Byung-Chan Na), “Recent Benchmarking Experience of the OECD/NEA Experts Group on Three-Dimensional Radiation Transport,” Proc. Int. Conf. Supercomputing in Nuclear Applications, Paris, France, Sept 22-24, 2003
    114. (with Hui Zhang), “The Variational Nodal Method in R-Z Geometry.” Proc. PHYSOR_2004 Tpg. Mtg on the Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, April 2004
    115. (with S. Van Criekingen & R. Beauwens), “Mixed-Hybrid Methods for the Linear Transport Equation,” Proc. PHYSOR_2004 Tpg. Mtg on the Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, April 2004
    116. ( with M. A. Smith, G. Palmiotti ), First-Order Spherical Harmonics Formulation Capable of Treating Low Density and Void Regions within the Framework of VARIANT’’ Proc. PHYSOR_2004 Tpg. Mtg on the Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, April 2004
    117. “The Variational Nodal Method: History and Recent Accomplishments,” Proc Int. Jnt. Mtg. Toward Latin American Cooperation in the Development of Nuclear Energy and Radiological Health, Cancun, Mexico, July 2004
    118. (with M. A. Smith and Byung-Chan Na), “Benchmark for Deterministic 3-D MOX Fuel Assembly Transport Calculations without Spatial Homogenization, ,” Proc. Conf. Mathematics and Computations Supercomputing, Reactor Physics and Nuclear and Biological Applications, Avignon, France, Sept. 12-15, 2005
    119. (with M. A. Smith and G. Palmiotti), “Argonne National Laboratory Results for the OECD 3-D MOX Fuel Assembly Benchmark,” Proc. Conf. Mathematics and Computations Supercomputing, Reactor Physics and Nuclear and Biological Applications, Avignon, France, Sept. 12-15, 2005
    120. (with M. A. Smith and G. Palmiotti), “The Variational Nodal Method: Some History and Recent Activity,” Proc. Conf. Mathematics and Computations Supercomputing, Reactor Physics and Nuclear and Biological Applications, Avignon, France, Sept. 12-15, 2005
    121. (with M. A. Smith and G. Palmiotti), “Quasi-reflected Interface Conditions for Variational Nodal Lattice Calculations,” Proc. PHYSOR-2006: Int. Tpg. Mtg., Adv. In Nuclear Analysis and Simulation, Vancouver, Canada, Sept. 10-14, 2006
    122. (with M. A. Smith, G. Palmiotti and W. S. Yang), “A First-Order Integral Method Developed for the VARIANT Code,” Proc. PHYSOR-2006: Int. Tpg. Mtg., Adv. In Nuclear Analysis and Simulation, Vancouver, Canada, Sept. 10-14, 2006
    123. (with M. A. Smith and G. Palmiotti), “Tailored Spherical Harmonics for Coupled Lattice Whole-Core Variational Nodal Transport Calculations”, Trans. Am. Nucl. Soc. 95, 568-571 (2006)
    124. (with M. A. Smith and G. Palmiotti), “A New Paradigm for Whole Core Neutron Transport Without Homogenization,” Proc. Joint Int. Mtg. Mathematics and Computation and Supercomputing for Nuclear Applications, Monterey Calif. April 15-19, 2007
    125. ( with G. Palmiotti, M. Smith, C. Rabiti, M. LeclereD. Kaushik, A. Siegel, and B. Smith), “UNÌC: Ultimate Neutronic Investigation Code” Proc. Joint Int. Mtg. Mathematics and Computation and Supercomputing for Nuclear Applications, Monterey Calif. April 15-19, 2007,

 

Technical Reports

 

  1. (with J. Hanson): "Development of an Electro-Mechanical System for Measuring Artillery Recoil Displacement and Velocity RIA Rep. 6l-2725, Rock Island Arsenal, l96l.
  2. (with R. N. Blomquist): "Buckled Spherical Harmonics Solutions of Neutron Transport Problems," U. S. Nuclear Regulatory Commission Report, NUREG/CR-0823, l979.
  3. (with R. V. Laney, E. A. Mason, D. L. Morrison, T. L. Martin, Jr. and J. H. Rust): "Report of the Senior Advisory Panel on Nuclear Safety to the Commonwealth Edison Company," June l979.
  4. "The DIF3D Transport Extension for Discrete Ordinates Neutronic Calculations in Two Dimensions," Argonne National Laboratory, Report FRA-TM-l49, l983.
  5. Solution Manual for Introduction to Reliability Engineering, Wiley, l987.
  6. (with G. Palmiotti and C. B. Carrico): "Variational nodal method for the Solution of the Diffusion and Transport Equation in Two and Three Dimensional Geometries," Commissiariat a l'Energie Atomique, Centre d'Etudes Nucleaires de Cadarache, France, 1991
  7. (with G. Palmiotti and C. B. Carrico), VARIANT: VARIational Anisotropic Nodal Transport for Multidimensional Cartesian and Hexagonal Geometry Calculation, ANL-95/40 Argonne National Laboratory, 1995, 140p.
  8. Solution Manual for second edition, Introduction to Reliability Engineering, Wiley, NY. 1995
  9. (with G. Palmiotti, T. A. Taiwo, M. A. Smith & N. Tsoulfanidis, “ Benchmark Specification for Deterministic 2-D/3-D MOX Fuel assembly Transport Calculations with Spatial Homogenization,” (C5G7 MOX) NEA/NSC/DOC(2001) 4, March 28,2001
  10. (with M. A. Smith & N. Tsoulfanidis ,G. Palmiotti, T. A. Taiwo & R. N. Blomquist, Eds), “Benchmark on Deterministic Transports Calculations Without Spatial Homogenization,” OECD/ Nuclear Energy Agency Document 16, 2003