Book Chapters and Thesis

P. J. Turinsky, The Degenerate Kernel Technique in Neutron Thermalization Theory, Doctorate Dissertation, University of Michigan, 1970.

P. J. Turinsky, Chapter 12: Thermal Reactors Calculations, Handbook of Nuclear Reactors Calculations, CRC Press, Inc., Boca Raton, 189, 1987.

P. J. Turinsky, "Nuclear Fuel Management Optimization," Computational Science Education Project Text, Case Study, DOE, 1992.

P. J. Turinsky and G. T. Parks, Chapter: Advances in Nuclear Fuel Management Optimization for Light Water Reactors, Advances in Nuclear Science and Technology, 21, 137, Kluwer Academic/Plenum Publishers, NYC, 1999.

Archived Journal Articles

P. J. Turinsky, "The Super-Variational Technique Revisited," Journal. of Math. Ana. and Appl., 33, 605, 1971.

P. J. Turinsky and J. J. Duderstadt, "The Degenerate Kernel Technique and Neutron Thermalization Calculations in Asymptotic Reactor Theory," Nucl. Sci. and Eng., 45, 156, 1971.

P. J. Turinsky and J. J. Duderstadt, "Applications of the Degenerate Kernel Technique to Thermal Neutron Spectra Calculations," Nucl. Sci. and Eng., 45, 167, 1971.

G. J. Kirouac and P. J. Turinsky, "Interpretation of Intermediate Structure inthe Ca-40 Neutron Elastic Scattering Cross-Section," Nuclear Physics A, #A228, 445, 1974.

R. C. Block, K. Alfieri and P. J. Turinsky, "Measurement and Evaluation of Total Neutron Cross- Section Minima in Elemental Iron," Nucl. Sci. and Eng., 51, 25, 1973.

Alberto L. Casadei and P. J. Turinsky, "An Improved Water Density Feedback Model for Pressurized Water Reactors," Nucl. Tech., 44, 221, 1979.

G. H. Hobson and P. J. Turinsky, "Automatic Determination of Pressurized Water Reactor Core Loading Patterns That Maximize Beginning-of-Cycle Reactivity Within Power-Peaking and Burnup Constraints," Nucl. Tech., 74, 5, 1986.

M. S. Song and P. J. Turinsky, "Analytic Predictions of Boiling Film Stability for Conditions Consistent with Light Water Reactor Degraded Core Conditions," Nucl. Sci. and Eng., 101, 117, 1989.

S. K. Zee, P. J. Turinsky and Z. Shayer, "Vectorized and Multi-Tasked Solution of the Few-Group Neutron Diffusion Equations," Nucl. Sci. and Eng., 101, 205, 1989.

D. J. Kropaczek and P. J. Turinsky, "In-Core Nuclear Fuel Management Optimization for PWRs Utilizing Simulated Annealing," Nucl. Tech., 95, 9, 1991.

G. I. Maldonado and P. J. Turinsky, "Application of Non-Linear Nodal Diffusion Generalized Perturbation Theory to Nuclear Fuel Reload Optimization," Nucl. Tech., 110, 198, 1995.

P. J. Turinsky, R. M. Al-Chalabi, P. Engrand, H. N. Sarsour, F. X. Faure and W. Guo, "Code Abstract - NESTLE: A Few-Group Neutron Diffusion Equation Solver Utilizing the Nodal Expansion Method for Eigenvalue, Adjoint, Fixed-Source Steady-State and Transient Problems," Nucl. Sci. & Engr., 120, 72, 1995.

G. I. Maldonado, P. J. Turinsky and D. J. Kropaczek, "Constrained Minimization of Fresh Reload Fuel Enrichment Within the FORMOSA Codes Nodal GPT Optimization Framework," Nucl. Sci. & Engr., 121, 312, 1995.

E. Fuentes and P. J. Turinsky, "Parallel Solution of the Integral Transport Equation Utilizing Collision Probability and Interface Current Methods," Nucl. Sci. & Engr., 121, 277, 1995.

N. Crouzet and P. J. Turinsky, "Development of an Adaptive Time-Step Size Control," 123, 206, 1996.

R. C. Penland, Y. Y. Azmy and P. J. Turinsky, "Error Analysis of the Quartic Nodal Expansion Method," Nucl. Sci. & Engr., 125, 284, 1997.

J. Ye and P. J. Turinsky, "Pressurized Water Reactor Core Maneuvering Utilizing Optimal Control," 129, 97, 1998.

B. R. Moore and P. J. Turinsky, "Analysis of Higher Order Generalized Perturbation Theory for BWR Fuel Management Optimization," Nucl. Sci. & Engr., 130, 98, 1998.

B. R. Moore, P. J. Turinsky and A. A. Karve, "FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package," Nucl. Tech., 126, 153, 1999.

P. J. Turinsky, "Mathematical Optimization of Incore Nuclear Fuel Management Decisions: Status and Trends," Internationale Zeitschrift fur Kernenergie, 7, 454, 1999.

A. A. Karve and P. J. Turinsky, "FORMOSA-B: A Boiling Water Reactor Incore Fuel Management Optimization Package II," Nucl. Tech., 131, 48, 2000.

A. A. Karve and P. J. Turinsky, "FORMOSA-B: A Boiling Water Reactor Incore Fuel Management Optimization Package III," Nucl. Tech., 135, 241, 2001.

P. M. Keller and P. J. Turinsky, "FORMOSA-P 3-D/2-D Geometry Collapse Methodology," Nucl. Sci. & Engr., 139, 235, 2001.

Topical Meetings; Reviewed Full Length Papers

Jose M. Sierra and P. J. Turinsky, "Optical Model Calculations at Rensselaer Polytechnic Institute," JAERI-M 5984, 193, 1975. [Invited]

M. S. Song and P. J. Turinsky, "Boiling Film Growth in Core-Melt Water System," Second Proceedings of Nuclear Thermal Hydraulics, ANS, 187, 1984.

D. C. Krupp and P. J. Turinsky, "Consistent Comparison Between the Drift Flux and Two-Fluids Formulations of Two-Phase Flow in LWRs," Third International Conference on Reactor Thermal Hydraulics, 2.A, 1985.

S. K. Zee and P. J. Turinsky, "Progress Toward Establishing an Engineering Workstation Based Nuclear Fuel Management Analysis Capability," Proceedings of the Topical Meeting on Advances in Fuel Management, 237, 1986.

G. H. Hobson and P. J. Turinsky, "Automatic Optimization of Core Loading Patterns to Maximize Cycle Energy Production Within Operational Constraints," Proceedings of the Topical Meeting on Advances in Fuel Management, 509, 1986.

S. A. Comes and P. J. Turinsky, "Out-of-Core Fuel Cycle Cost Minimization Using Monte Carlo Integer Programming," Proceedings of the Topical Meeting on Advances in Fuel Management, 533, 1986.

S. K. Zee and P. J. Turinsky, "Solution of the Few Group Neutron Diffusion Equations on Parallel Architecture Computers," Second International Conference on Simulation Methods in Nuclear Engineering, 270, 1986. [Invited]

S. K. Zee and P. J. Turinsky, "Vectorized and Multi-Tasked Solutions of the Neutron Diffusion Equations," International Meeting on Advances in Reactor Physics, Mathematics and Computation Division, ANS, 83, 1987.

P. J. Turinsky, Z. Shayer, H. N. Sarsour and R. Al-Chalabi, "Benchmarking of Codes on Computers with Parallel Hardware," Advances in Nuclear Engineering Computation and Radiation Shielding Topical Meeting, Mathematics and Computation Division, ANS, Paper 40, 1989.

G. T. Parks, P. J. Turinsky and G. I. Maldonado, "Solving the PWR Reload Core Optimization Problem," Paper CIN-90-0095-I, 1991 IBM Supercomputing Competition, Third Prize- Engineering Category, 281, 1991.

H. N. Sarsour, P. J. Turinsky and C. S. Henkel, "Parallel Solution of the Few-Group Neutron Diffusion Equations," Fifth SIAM Conference on Parallel Processing for Scientific Computing, SIAM, 269, 1991.

A. M. Yacout, P. J. Turinsky, R. Al-Chalabi and W. J. Rasdorf, "A Nuclear Power Plant Operator Aid Utilizing On-Line Simulation Models," Advances in Nuclear Engineering Computation and Radiation Shielding Topical Meeting, Mathematics and Computation Division, ANS, Paper 27, 1989.

D. J. Kropaczek, G. T. Parks, Ivan Maldonado and P. J. Turinsky, "Applications of Simulated Annealing to In-Core Nuclear Fuel Management Optimization," Advances in Mathematics, Computations, and Reactor Physics International Topical Meeting, Mathematics and Computation Division, ANS, 5, 22.1 1-1, 1991. [Invited]

P. J. Turinsky, "Computational Engineering & Sciences Interdisciplinary Graduate Program Curriculum Design," Undergraduate and Graduate Education in Computational Sciences, Editors D. L. Greenwell, R. K. Kalia & P. Vashishta, 87, LSU & ANL, 1991.

C. S. Henkel and P. J. Turinsky, "Solution of the Few-Group Neutron Diffusion Equations on a Distributed Memory Multi-Processor," Proceedings of the Topical Meeting on Advances in Reactor Physics, ANS, 1, 108, 1992.

P. J. Turinsky and G. T. Parks, "Successful Inter-Organizational and International Collaboration in Nuclear Fuel Management R&D," Research & Development in the Nuclear Industry, British Nuclear Forum, Cambridge, 1992.

G. I. Maldonado, P. J. Turinsky and D. J. Kropaczek, "PWR In-Core Nuclear Fuel Management Optimization Utilizing Nodal (Non-Linear NEM) Generalized Perturbation Theory," Joint International Conference on Mathematical Methods and Supercomputers in Nuclear Applications, ECS-ANS, I, 787, 1993.

E. Fuentes and P. J. Turinsky, "Parallel Solution of the Collision Probability Method on the CM- 2," Domain Decomposition Methods for Partial Differential Equations, University Park, SIAM, 1993.

D. J. Kropaczek, P. J. Turinsky, G. I. Maldonado and G. T. Parks, "The Efficiency and Fidelity of the In-Core Fuel Management Code FROMOSA-P," International Conference on Reactor Physics and Reactor Computations, Tel Aviv, 572, INS/ENS, 1994.

G. I. Maldonado, P. J. Turinsky and D. J. Kropaczek, "Constrained Minimization of Fresh Reload Fuel Enrichment Within the FORMOSA Codes Nodal GPT Optimization Framework," 1994 Topical Meeting on Advances in Reactor Physics, Knoxville, ANS, III-314, 1994.

E. Fuentes and P. J. Turinsky, "Parallel Solution of the Integral Transport Equation Utilizing Collision Probability and Interface Current Methods," 1994 Topical Meeting on Advances in Reactor Physics, Knoxville, I-416, ANS, 1994.

E. Fuentes and P. J. Turinsky, "Core-Wide Parallel Implementation of the IC and CCCP Methods," Seventh SIAM Conference on Parallel Processing for Scientific Computing," SIAM, 502, 1995.

D. J. Kropaczek, Jeffrey D. McElroy, P. J. Turinsky and S. B. Thomas, "Integration of the FORMOSA-P Fuel Management Code Into Design Licensing Code Systems," International Conference on Fuel Management and Handling, BNES, Paper 6, 1995.

D. J. Kropaczek, P. J. Turinsky and S. B. Thomas, "Optimization of Reload Core Designs for Pressurized Water Reactors," Nuclear Plant Journal, 13, 34, 1995.

R. C. Penland, Y. Y. Azmy, and P. J. Turinsky, "Error Analysis of the Quartic Nodal Expansion Method in Slab Geometry," International Conference on Mathematics and Computations, Reactor Physics, and Environment Analysis, ANS, 1418, 1995.

H. N. Sarsour, P. J. Turinsky, R. M. Al-Chalabi, and B. R. Moore, "Development of a Consistent Collapsed Three to Two Dimensional Nodal Model for PWR Loading Pattern Determination," International Conference on Mathematics and Computations, Reactor Physics, and Environment Analysis, ANS, 605, 1995.

R. M. Al-Chalabi and P. J. Turinsky, "Multigrid Method Applied to the Solution of an Elliptic, Generalized Eigenvalue Problem," Proceedings of the Copper Mountain Conference on Iterative Methods, Vol. II, SIAM, 1996.

P. J. Turinsky and K. Verghese, "North Carolina State University Master of Nuclear Engineering Traineeship Program," ASEE Annual Conference Proceedings, 1996.

P. M. Keller and P. J. Turinsky, "Recent Developments in FORMOSA-P," Advances in Nuclear Fuel Management II, Myrtle Beach, ANS, 8-39, 1997.

B. R. Moore and P. J. Turinsky, "FORMOSA-B: A BWR Incore Fuel Management Optimization Package," Advances in Nuclear Fuel Management II, Myrtle Beach, ANS, 17-21, 1997.

B. R. Moore and P. J. Turinsky, "Analysis of Higher Order Generalized Perturbation Theory for BWR Fuel Management Optimization," Advances in Nuclear Fuel Management II, Myrtle Beach, ANS, 15-33, 1997.

D. F. Kastanya, I. Ariani and P. J. Turinsky, "Verification of Dynamic Rod Worth Measurement Calculational Methodology," Advances in Nuclear Fuel Management II, Myrtle Beach, ANS, 14- 65, 1997.

V. Bartro and P. J. Turinsky, "Incorporation of Rodded Core Configurations Treatment Within FORMOSA-P Incore Fuel Management Optimization Code," Advances in Nuclear Fuel Management II, Myrtle Beach, ANS, 15-59, 1997.

J. Judd, D. Barber, T. Downar, P. J. Turinsky, H. Joo, H. Sarsour, K. Ross, S. Clement, R. J. Wagner and R. J. Beelman, "A RELAP/NESTLE Engineering Simulator for Shared-Memory Multiprocessors," Advances in Nuclear Fuel Management II, Myrtle Beach, ANS, 20-13, 1997.

P. J. Turinsky, "Nuclear Fuel Management Optimization for LWRs," XI ENFIR, Pocos de Caldas, Brazilian Association for Nuclear Energy, 1997.

P. J. Turinsky, "Mathematical Optimization of Incore Nuclear Fuel Management Decisions: Status and Trends," Proc. of Annual Meeting of Nuclear Technology, Karlsruhe, Atomwirthschaft, 47, 1999. [Invited]

P. M. Keller and P. J. Turinsky, "Three Dimensional Perturbations Algorithms for FORMOSA-P Nonlinear 3-D/2-D Collapse Methodology," Proc. of the Int. Conf. on Mathematics and Compu­tation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, 1489, 1999. [Invited]

A. A. Karve and P. J. Turinsky, "Effectiveness of BWR Control Rod Pattern Sampling Capability in the Incore Fuel Management Code FORMOSA-B," Proc. of the Int. Conf. on Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, 1459, 1999. [Invited]

I. Ariani, P. J. Turinsky and D. Kastanya, "Development and Verification of an Alternative Formulation for Dynamic Reactivity Measurement of Rod Worth," Proc. of the 2001 ANS International Meeting on Mathematical Methods for Nuclear Applications, Salt Lake City, 2001.

H. N. Sarsour, P. J. Turinsky, F. Rahnema, S. Mosher, D. Serghiuta, G. Marleau and T. Courau, "HELIOS/DRAGON/NESTLE Codes; Simulation of the Gentilly-2 Loss of Class 4 Power Event," CNS Simulation Conference, Ottawa (2002).

H. N. Sarsour, P. J. Turinsky, F. Rahnema, S. Mosher, D. Serghiuta, G. Marleau and T. Courau, "Best Estimate HELIOS/DRAGON/NESTLE Codes; Simulation of a LOCA Power Pulse for a Simplified CANDU-6 Core," CNS Simulation Conference, Ottawa (2002).

H. N. Sarsour, F. Rahnema, S. Mosher, P. J. Turinsky, D. Serghiuta, G. Marleau and T. Courau, "HELIOS/DRAGON/NESTLE Codes; Simulation of tVoid Reactivity in a CANDU Core," CNS Simulation Conference, Ottawa (2002).

Meetings; Reviewed Summary Papers

P. J. Turinsky and J. J. Duderstadt, "The Degenerate Kernel Technique and Applications to Neutron Thermalization," Trans. Am. Nucl. Soc., 12, 628, 1969.

P. J. Turinsky, "Mark Mill's Award Paper: The Degenerate Kernel Technique in Neutron Thermalization Calculations," Trans. Am. Nucl. Soc., 14, 669, 1971. [Invited]

R. C. Block, K. Alfieri and P. J. Turinsky, "Differential and Area Analysis of Iron Total Cross- Section Minima," Trans. Am. Nucl. Soc., 15, 531, 1972.

Alberto L. Casadei and P. J. Turinsky, "Spectral Modeling for PWRs," Trans. Am. Nucl. Soc., 23, 576, 1976.

Alberto L. Casadei and P. J. Turinsky, "PWR Neutronic Predictions Employing An Improved Water Density Model," Trans. Am. Nucl. Soc., 24, 442, 1976.

D. E. Kusner, M. A. Mann, and P. J. Turinsky, "Planned Cycle Stretchout in PWRs," Trans. Am. Nucl. Soc., 27, 467, 1977.

Alberto L. Casadei and P. J. Turinsky, "Subcooled Boiling and Open Channel Effects in PWR Neutronic Calculations," Trans. Am. Nucl. Soc., 32, 718, 1979. [Invited]

P. J. Turinsky and S. K. Zee, "Qualification of the Core Physics Models Used in the Shearon Harris Nuclear Station Simulator," Trans. Am. Nucl. Soc., 45, 672, 1983.

G. H. Hobson and P. J. Turinsky, "Automatic Determination of PWR Core Loading Patterns That Maximize Core Reactivity," Trans. Am. Nucl. Soc., 45, 96, 1983.

M. S. Song and P. J. Turinsky, Boiling Film Growth in Core Melt/Water Systems," Trans. Am. Nucl. Soc., 46, 864, 1984.

P. J. Turinsky, J. M. Doster, A. M. Yacout and M. S. Song, "Computer Utilization in Nuclear Engineering Education at NCSU," Trans. Am. Nucl. Soc., 47, 48, 1984.

P. Y. Li and P. J. Turinsky, "Multiple-Cycle Fuel Cycle Cost Scoping Computer Program," Trans. Am. Nucl. Soc., 47, 116, 1984.

G. H. Hobson and P. J. Turinsky, "Maximization of Core Reactivity Within Power and Burnup Constraints," Trans. Am. Nucl. Soc., 47, 117, 1984.

P. J. Turinsky, "Future Potential Pitfalls for Nuclear Engineering Education," Trans. Am. Nucl. Soc., 49, 18, 1985. [Invited]

P. J. Turinsky and S. K. Zee, "Large Sparse Matrix Systems Solution Algorithms for Parallel Processors Computer Architectures," Trans. Am. Nucl. Soc., 49, 212, 1985.

S. Haq and P. J. Turinsky, "Out-of-Core Fuel Management Optimization Utilizing the Integer Linear Programming Technique," Trans. Am. Nucl. Soc., 50, 95, 1985.

P. J. Turinsky and S. A. Comes, "Out-of-Core Fuel Cycle Optimization Utilizing an Engineering Workstation," Trans. Am. Nucl . Soc., 52, 94, 1986. [Invited]

S. A. Comes and P. J. Turinsky, "Examination of Fuel Reinsertion Strategies for Out-of-Core Fuel Management," Trans. Am. Nucl. Soc., 53, 82, 1986.

S. K. Zee, E. D. Sills, P. J. Turinsky and J. M. Doster, "Solution of Neutronic and Thermal- Hydraulic Problems on an Engineering Workstation," Trans. Am. Nucl. Soc., 53, 538, 1986. [Invited]

S. K. Zee and P. J. Turinsky, "Parallel Solutions of the Two-Group Neutron Diffusion Equations," Trans. Am. Nucl. Soc., 55, 319, 1987. [Invited]

S. A. Comes and P. J. Turinsky, "Out-of-Core Fuel Cycle Optimization for Non-equilibrium Cycles," Nucl. Tech., 83, 31, 1988.

D. J. Kropaczek and P. J. Turinsky, "Quantification of Cost of Margin Associated with Incore Nuclear Fuel Management for PWR," Trans. Am. Nucl. Soc., 30, 87, 1989.

R. L. Thomas, Jr. and P. J. Turinsky, "Evaluation of the Need for Stochastic Optimization of Out- of-Core Nuclear Fuel Management Decisions," Trans. Am. Nucl. Soc., 30, 88, 1989.

D. C. Hance, P. J. Turinsky and A. M. Yacout, "An Abnormal Event Advisory Expert System Prototype for Reactor Operators, " Trans. Am. Nucl. Soc., 30, 126, 1989.

J. R. Caves, J. M. Doster, G. D. Miller, B. W. Wehring and P. J. Turinsky, "The NCSU Freon PWR Loop," Trans. Am. Nucl. Soc., 59, 30, 1989.

D. J. Kropaczek and P. J. Turinsky, "A High-Order Depletion Perturbation Theory with Application to In-Core Fuel Management Optimization," Trans. Am. Nucl. Soc., 61, 362, 1990.

D. J. Kropaczek and P. J. Turinsky, "In-Core Fuel Management Optimization for a PWR Utilizing Simulated Annealing," Trans. Am. Nucl. Soc., 61, 74, 1990.

P. J. Turinsky, J. M. Doster, K. D. Kim, R. M. Al-Chalabi, T. Kheda, R. H. Sues and A. M. Yacout, "Development of a Test Bed for Operator Aid and Advanced Control," 61, 121, 1990. [Invited]

J. M. Sawyer, P. R. Murphy, G. T. Parks, Ivan Maldonado, P. J. Turinsky and D. Daniels, "Integration of the W.R FORMOSA In-Core Nuclear Fuel Management Code into Nuclear Design Code Systems," Trans. Am. Nucl. Soc., 63, 416, 1991. [Invited]

H. N. Sarsour and P. J. Turinsky, "Coarse Grain Parallel Solution of the Few-Group Neutron Diffusion Equations," Trans. Am. Nucl. Soc., 63, 203, 1991.

P. Engrand and P. J. Turinsky, "Evaluation of Alternative Temporal Treatments for the Neutron Kinetics Equations," Trans. Am. Nucl. Soc., 63, 204, 1991.

P. J. Turinsky, J. M. Doster, J. A. Turner and S. K. Zee, "Parallel Sparse Matrix Solution Algorithm Applications in Nuclear Engineering," Trans. Am. Nucl. Soc., 50, 276, 1985. [Invited]

P. Engrand, G. I. Maldonado, R. M. Al-Chalabi and P. J. Turinsky, "Non-Linear Iterative Strategy for NEM Refinement and Extension," Trans. Am. Nucl. Soc., 65, 221, 1992.

R. M. Al-Chalabi and P. J. Turinsky, "Acceleration Techniques for the Few-Group Neutron Diffusion Equations with Fixed Source and Feedback," Trans. Am. Nucl. Soc., 65, 223, 1992.

S. Sun, G. I. Maldonado and P. J. Turinsky, "Loading Pattern Sensitivity to Burnable Poison Availability," Trans. Am. Nucl. Soc., 65, 67, 1992.

R. M. Al-Chalabi, P. J. Turinsky, F. X. Faure, H. N. Sarsour and P. R. Engrand, "NESTLE: A Nodal Kinetics Code," Trans. Am. Nucl. Soc., 68, 432, 1993.

S. Sun, D. J. Kropaczek and P. J. Turinsky, "Haling Principle: True or False?," Trans. Am. Nucl. Soc., 68, 482, 1993.

Z. Zhu, D. J. Kropaczek and P. J. Turinsky, "Application of Computer Visualization to Core Reactor Physics Analysis and Design," Trans. Am. Nucl. Soc., 68, 480, 1993.

G. I. Maldonado, P. J. Turinsky and D. J. Kropaczek, "On the Treatment of Non-Linear Local Feedbacks Within Advanced Nodal Generalized Perturbation Theory," Trans. Am. Nucl. Soc., 68, 218, 1993.

D. J. Kropaczek, J. McElroy and P. J. Turinsky, "Validity of Single Cycle Objective Functions for Multicycle Reload Design Optimization," Trans. Am. Nucl. Soc., 69, 419, 1993.

S. Sun, P. J. Turinsky and D. J. Kropaczek, "Enhancement of Neutronics Model Utilized in Multi- Cycle Fuel Management Code OCEON," Trans. Am. Nucl. Soc., 70, 91, 1994.

E. Fuentes and P. J. Turinsky, "Consistent Fidelity Comparison of Integral Transport Methods," Trans. Am. Nucl. Soc., 71, 270, 1994.

N. Crouzet and P. J. Turinsky, "Adaptive Time-Step Size Control," 71, 453, 1994. [Invited]

R. M. Al-Chalabi and P. J. Turinsky, "Application of Multigrid Method to Solving the NEM Form of Multigroup Neutron Diffusion Equations," Trans. Am. Nucl. Soc., 71, 259, 1994.

J. Ye, D. J. Kropaczek and P. J. Turinsky, "Optimal Control." 71, 501, 1994.

R. C. Penland, Y. Y. Azmy, and P. J. Turinsky, "Error Analysis of the Quadratic Nodal Expansion Method in Slab Geometry," Trans. Am. Nucl. Soc., 71, 247, 1994.

J. S. Imbriani, P. J. Turinsky and D. J. Kropaczek, "Generalized Perturbation Theory Error Control," 72, 345, 1995.

J. Judd, T. Downar, P. Turinsky, D. Barber, H. Joo, H. Sarsour, K. Ross, S. Clement, A. Arora, K. C. Wagner, R. J. Wagner and R. J. Beelman, "High Fidelity, Real Time Simulation with RELAP5/NESTLE," Trans. Am. Nucl. Soc., 75, 321, 1996. [Best Paper Award-Reactor Physics Divsion]

D. K. Kastanya and P. J. Turinsky, "Simulation Error Propagation for a Dynamic Rod Measurement Technique," Trans. Am. Nucl. Soc., 75, 359, 1996.

P. M. Keller and P. J. Turinsky, "FORMOSA-P Multiple Adaptive Penalty Function Methodology," Trans. Am. Nucl. Soc., 75, 341, 1996.

J-M Noh, P. J. Turinsky and H. N. Sarsour, "Microscopic to Macroscopic Depletion Model Developed for FORMOSA-P," Trans. Am. Nucl. Soc., 75, 339, 1996.

I. Ariani and P. J. Turinsky, "Evaluation of Mixed LEU-MOX Loading Patterns for LWRs Originating from Inability to Deliver MOX Assemblies," Trans. Am. Nucl. Soc., 79, 301, 1998.

P. J. Turinsky and P. Narahanan, "Enhancements to OCEON-P Code Multicycle Optimization Capability," Trans. Am. Nucl. Soc., 79, 320, 1998.

X. Mouney and P. J. Turinsky, "Evaluation of the Potential to Misdirect a Loading Pattern Optimization Search Due to Core Simulator Errors," Trans. Am. Nucl. Soc., 79, 322, 1998.

A. A. Karve and P. J. Turinsky, "BWR Control-Cell-Core Loading Pattern and Control," 79, 324, 1998.

P. M. Keller and P. J. Turinsky, "FORMOSA-P 3-D/2-D Nonlinear Collapse Methodology," Trans. Am. Nucl. Soc., 80, 230, 1999.

A. A. Karve and P. J. Turinsky, "Effectiveness of Heuristic Control," 80, 227, 1999.

A. A. Karve and P. J. Turinsky, "Fast Shutdown Margin Evaluator in the FORMOSA-B Fuel Management Optimization Code," Trans. Am. Nucl. Soc., 83, 272, 2000.

P. M. Keller and P. J. Turinsky, "FORMOSA-P 3-D/2-D Pin Reconstruction Collapse Methodolgy," Trans. Am. Nucl. Soc., 83, 402, 2000.

U. Mertyurek and P. J. Turinsky, "Improved Transverse Leakage Treatment for a Supernodal Method," Trans. Am. Nucl. Soc., 83, 404, 2000.

D. Kastanya and P. J. Turinsky, "Implementation of Newton-Krylov Solver in FORMOSA-B," Trans. Am. Nucl. Soc., 83, 420, 2000.

A. A. Karve, P. M. Keller, P. J. Turinsky and G. I. Maldonado, "Nuclear Fuel Management Optimization Capabilities," Trans. Am. Nucl. Soc., 84, 59, 2001.

U. Mertyurek and P. J. Turinsky, "An Improved Supernodal Method for Nuclear Reactor Analysis," Trans. Am. Nucl. Soc., 86, 363, 2002.

D. Kastanya and P. J. Turinsky, "Development of Newton-Krylov Solver in FORMOSA-B," Trans. Am. Nucl. Soc., 86, 226, 2002.

H. Abdel-Khalik and P. J. Turinsky, "Inverse Method Applied to Adaptive Core Simulation," Trans. Am. Nucl. Soc., 86, 366, 2002. [Best Paper Award-Reactor Physics Division]

P. J. Turinsky, "Challenging Issues Related to Satisfying ABET200 Criteria," Trans. Am. Nucl. Soc., 87, 223, 2002. [Invited Paper]

National Laboratory Reports

P. J. Turinsky, West European Nuclear Power Generation Research and Development, Foreign Applied Sciences Assessment Center Technical Assessment Report, Chapters I, II & III Author and Overall Editor, SAIC, 1991.

P. J. Turinsky et. al., NESTLE: A Few-Group Neutron Diffusion Equation Solver Utilizing the Nodal Expansion Method for Eigenvalue, Adjoint, Fixed-Source Steady State and Transient Problems, EGG-NRE-11406, INEL, 1994.

I. Ariani and P. J. Turinsky, Evaluation of Mixed LEU-MOX Loading Patterns for LWRs Origination from Inability to Deliver MOX Assemblies: ABB-CE System 80 Reload Core Study, ORNL Report, Oak Ridge, 1998.

I. Ariani and P. J. Turinsky, Evaluation of Mixed LEU-MOX Loading Patterns for LWRs Origination from Inability to Deliver MOX Assemblies: Westinghouse Reload Core Study, ORNL Report, Oak Ridge, 1999.

I. Ariani and P. J. Turinsky, Evaluation of Mixed LEU-MOX Loading Patterns for LWRs Origination from Inability to Deliver MOX Assemblies: GE BWR/6 Reload Core Study, ORNL Report, Oak Ridge, 2000.

H. N. Sarsour and P. J. Turinsky, Reactivity Void Calculations - Phase 4, CNS Report, Ottawa, 2000.

H. N. Sarsour and P. J. Turinsky, Reactor Physics Aspects of LOCA Analysis, CNS Report, Ottawa, 2001.

H. N. Sarsour and P. J. Turinsky, Loss of Reactivity Control, CNS Report, Ottawa, 2002.

[From 1973-80, Dr. Turinsky published numerous proprietary technical reports internal to Westinghouse Electric Corporation.]