Paul J Turinsky

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

PROGRESS IN NUCLEAR ENERGY, 114, 227–233.

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

NUCLEAR ENGINEERING AND TECHNOLOGY, 51(4), 968–976.

Preface to Shippingport Atomic Power Station thematic issue

Turinsky, P. J. (2018, January). PROGRESS IN NUCLEAR ENERGY, Vol. 102, pp. 1–8.

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

Turinsky, P. J., & Martin, W. R. (2017, April 1). JOURNAL OF COMPUTATIONAL PHYSICS, Vol. 334, pp. 687–688.

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

JOURNAL OF COMPUTATIONAL PHYSICS, 313, 367–376.

STOCHASTIC OPTIMIZATION FOR NUCLEAR FACILITY DEPLOYMENT SCENARIOS USING VISION

NUCLEAR TECHNOLOGY, 186(1), 76–89.

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

NUCLEAR SCIENCE AND ENGINEERING, 173(3), 293–311.

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

NUCLEAR ENGINEERING AND TECHNOLOGY, 44(2), 103–112.

EXPERIMENT OPTIMIZATION TO REDUCE NUCLEAR DATA UNCERTAINTIES IN SUPPORT OF REACTOR DESIGN

NUCLEAR TECHNOLOGY, 180(2), 216–230.

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

Hays, R., & Turinsky, P. (2011, August). PROGRESS IN NUCLEAR ENERGY, Vol. 53, pp. 600–606.

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

NUCLEAR SCIENCE AND ENGINEERING, 169(1), 40–55.

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

ANNALS OF NUCLEAR ENERGY, 36(7), 995–997.

Efficient subspace methods-based algorithms for performing sensitivity, uncertainty, and adaptive simulation of large-scale computational models

NUCLEAR SCIENCE AND ENGINEERING, 159(3), 256–272.

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). NUCLEAR DATA SHEETS, Vol. 109, pp. 2785–2790.

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

Nuclear Technology, 151(1), 21-.

Adaptive core simulation employing discrete inverse theory - Part II: Numerical experiments

Abdel-Khalik, H. S., & Turinsky, P. J. (2005, July). NUCLEAR TECHNOLOGY, Vol. 151, pp. 22–34.

Development and implementation of a Newton-BICGSTAB iterative solver in the FORMOSA-B BWR core simulator code

NUCLEAR SCIENCE AND ENGINEERING, 150(1), 56–71.

Nuclear fuel management optimization: A work in progress

Nuclear Technology, 151(1), 08-.

Super-nodal methods for space-time kinetics

NUCLEAR SCIENCE AND ENGINEERING, 147(2), 93–126.

FORMOSA-B: A boiling water reactor in-core fuel management optimization package III

NUCLEAR TECHNOLOGY, 135(3), 241–251.

FORMOSA-P three-dimensional/two-dimensional geometry collapse methodology

NUCLEAR SCIENCE AND ENGINEERING, 139(3), 235–247.

FORMOSA-B: A boiling water reactor in-core fuel management optimization package II

NUCLEAR TECHNOLOGY, 131(1), 48–68.

Formosa-B: A boiling water reactor in-core fuel management optimization package

NUCLEAR TECHNOLOGY, 126(2), 153–169.

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

NUCLEAR SCIENCE AND ENGINEERING, 130(1), 98–112.

Pressurized water reactor core maneuvering utilizing optimal control theory

NUCLEAR SCIENCE AND ENGINEERING, 129(2), 97–123.

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.