Paul J. Turinsky

Generation of nodal neutronic parameters’ library based upon high-fidelity core-wide simulations - Part I: Base model

Turinsky, P., Graham, A., & Collins, B. (2025, November 4). Progress in Nuclear Energy.

Generation of nodal neutronic parameters’ library based upon high-fidelity core-wide simulations - Part II: Partially inserted absorber rods

Turinsky, P., & Graham, A. (2025, November 25). Progress in Nuclear Energy.

Non-linear, time dependent target accuracy assessment algorithm for multi-physics, high dimensional nuclear reactor calculations

Khuwaileh, B. A., & Turinsky, P. J. (2019, March 21). Progress in Nuclear Energy.

Verification of Reduced Order Modeling based Uncertainty/Sensitivity Estimator (ROMUSE)

Khuwaileh, B., Williams, B., Turinsky, P., & Hartanto, D. (2019, January 31). Nuclear Engineering and Technology.

Preface to Shippingport Atomic Power Station thematic issue

Turinsky, P. J. (2017, April 28). Progress in Nuclear Energy.

Special issue on the “Consortium for Advanced Simulation of Light Water Reactors Research and Development Progress”

Turinsky, P. J., & Martin, W. R. (2017, January 20). Special issue on the “Consortium for Advanced Simulation of Light Water Reactors Research and Development Progress.” Journal of Computational Physics.

Modeling and simulation challenges pursued by the Consortium for Advanced Simulation of Light Water Reactors (CASL)

Turinsky, P. J., & Kothe, D. B. (2016, February 20). Journal of Computational Physics.

Stochastic Optimization for Nuclear Facility Deployment Scenarios Using VISION

Hays, R., & Turinsky, P. (2014, April 1). Nuclear Technology.

Optimization of Thermal-Hydraulic Reactor System for SMRs via Data Assimilation and Uncertainty Quantification

Heo, J., Turinsky, P. J., & Doster, J. M. (2013, March 1). Nuclear Science and Engineering.

ADVANCES IN MULTI-PHYSICS AND HIGH PERFORMANCE COMPUTING IN SUPPORT OF NUCLEAR REACTOR POWER SYSTEMS MODELING AND SIMULATION

Turinsky, P. J. (2012, March 25). Nuclear Engineering and Technology.

Experiment Optimization to Reduce Nuclear Data Uncertainties in Support of Reactor Design

Stover, T. E., & Turinsky, P. J. (2012, November 1). Nuclear Technology.

Many-Group Cross-Section Adjustment Techniques for Boiling Water Reactor Adaptive Simulation

Jessee, M. A., Turinsky, P. J., & Abdel-Khalik, H. S. (2011, September 1). Nuclear Science and Engineering.

BWR in-core fuel management optimization using parallel simulated annealing in FORMOSA-B

Hays, R., & Turinsky, P. (2010, October 15). Progress in Nuclear Energy.

A comparative study of ZPR-6/7 with MCNP/5 and MC2-2/REBUS

Masood, I., Hany, A.-K., & Paul, T. (2009, April 3). Annals of Nuclear Energy.

Efficient Subspace Methods-Based Algorithms for Performing Sensitivity, Uncertainty, and Adaptive Simulation of Large-Scale Computational Models

Abdel-Khalik, H. S., Turinsky, P. J., & Jessee, M. A. (2008, July 1). Nuclear Science and Engineering.

Uncertainty Quantification, Sensitivity Analysis, and Data Assimilation for Nuclear Systems Simulation

Abdel-Khalik, H., Turinsky, P., Jessee, M., Elkins, J., Stover, T., & Iqbal, M. (2008, December 1). Nuclear Data Sheets.

Adaptive Core Simulation Employing Discrete Inverse Theory - Part II: Numerical Experiments

Abdel-Khalik, H. S., & Turinsky, P. J. (2005, July 1). Nuclear Technology.

Adaptive core simulation employing discrete inverse theory - Part I: Theory

Nuclear Technology, 151(1), 21-.

Development and Implementation of a Newton-BICGSTAB Iterative Solver in the FORMOSA-B BWR Core Simulator Code

Kastanya, D. Y. F., & Turinsky, P. J. (2005, May 1). Nuclear Science and Engineering.

Nuclear fuel management optimization: A work in progress

Nuclear Technology, 151(1), 08-.

Super-Nodal Methods for Space-Time Kinetics

Mertyurek, U., & Turinsky, P. J. (2004, June 1). Nuclear Science and Engineering.

FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package III

Karve, A. A., & Turinsky, P. J. (2001, September 1). Nuclear Technology.

FORMOSA-P Three-Dimensional/Two-Dimensional Geometry Collapse Methodology

Keller, P. M., & Turinsky, P. J. (2001, November 1). Nuclear Science and Engineering.

FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package II

Karve, A. A., & Turinsky, P. J. (2000, July 1). Nuclear Technology.

FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package

Moore, B. R., Turinsky, P. J., & Karve, A. A. (1999, May 1). Nuclear Technology.

Mathematical optimization of incore nuclear fuel management decisions: status and trends

ATW - Internationale Zeitschrift Fur Kernenergie, 44(7), 454.

Higher Order Generalized Perturbation Theory for Boiling Water Reactor In-Core Fuel Management Optimization

Moore, B. R., & Turinsky, P. J. (1998, September 1). Nuclear Science and Engineering.

Pressurized Water Reactor Core Maneuvering Utilizing Optimal Control Theory

Ye, J., & Turinsky, P. J. (1998, June 1). Nuclear Science and Engineering.

A nuclear power plant operator aid utilizing on-line simulation models

Proceedings of the Topical Meeting on America Nuclear Society's Advances in Nuclear Engineering Computation and Radiation Shielding, Eldorado Hotel, Santa Fe, New Mexico, April 9-13, 1989. Santa Fe, NM: American Nuclear Society.