Paul Turinsky Khuwaileh, B. A., & Turinsky, P. J. (2019). Non-linear, time dependent target accuracy assessment algorithm for multi-physics, high dimensional nuclear reactor calculations. PROGRESS IN NUCLEAR ENERGY, 114, 227–233. https://doi.org/10.1016/j.pnucene.2019.01.023 Khuwaileh, B., Williams, B., Turinsky, P., & Hartanto, D. (2019). Verification of Reduced Order Modeling based Uncertainty/Sensitivity Estimator (ROMUSE). NUCLEAR ENGINEERING AND TECHNOLOGY, 51(4), 968–976. https://doi.org/10.1016/j.net.2019.01.020 Turinsky, P. J. (2018, January). Preface to Shippingport Atomic Power Station thematic issue. PROGRESS IN NUCLEAR ENERGY, Vol. 102, pp. 1–8. https://doi.org/10.1016/j.pnucene.2017.03.030 Turinsky, P. J., & Martin, W. R. (2017, April 1). Special issue on the "Consortium for Advanced Simulation of Light Water Reactors Research and Development Progress". JOURNAL OF COMPUTATIONAL PHYSICS, Vol. 334, pp. 687–688. https://doi.org/10.1016/j.jcp.2017.01.028 Turinsky, P. J., & Kothe, D. B. (2016). Modeling and simulation challenges pursued by the Consortium for Advanced Simulation of Light Water Reactors (CASL). JOURNAL OF COMPUTATIONAL PHYSICS, 313, 367–376. https://doi.org/10.1016/j.jcp.2016.02.043 Hays, R., & Turinsky, P. (2014). STOCHASTIC OPTIMIZATION FOR NUCLEAR FACILITY DEPLOYMENT SCENARIOS USING VISION. NUCLEAR TECHNOLOGY, 186(1), 76–89. https://doi.org/10.13182/nt13-68 Heo, J., Turinsky, P. J., & Doster, J. M. (2013). Optimization of Thermal-Hydraulic Reactor System for SMRs via Data Assimilation and Uncertainty Quantification. NUCLEAR SCIENCE AND ENGINEERING, 173(3), 293–311. https://doi.org/10.13182/nse11-113 Turinsky, P. J. (2012). 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. https://doi.org/10.5516/net.01.2012.500 Stover, T. E., & Turinsky, P. J. (2012). EXPERIMENT OPTIMIZATION TO REDUCE NUCLEAR DATA UNCERTAINTIES IN SUPPORT OF REACTOR DESIGN. NUCLEAR TECHNOLOGY, 180(2), 216–230. https://doi.org/10.13182/nt12-a14635 Hays, R., & Turinsky, P. (2011, August). BWR in-core fuel management optimization using parallel simulated annealing in FORMOSA-B. PROGRESS IN NUCLEAR ENERGY, Vol. 53, pp. 600–606. https://doi.org/10.1016/j.pnucene.2010.09.002 Jessee, M. A., Turinsky, P. J., & Abdel-Khalik, H. S. (2011). Many-Group Cross-Section Adjustment Techniques for Boiling Water Reactor Adaptive Simulation. NUCLEAR SCIENCE AND ENGINEERING, 169(1), 40–55. https://doi.org/10.13182/nse09-67 Iqbal, M., Abdel-Khalik, H., & Turinsky, P. (2009). A comparative study of ZPR-6/7 with MCNP/5 and MC2-2/REBUS. ANNALS OF NUCLEAR ENERGY, 36(7), 995–997. https://doi.org/10.1016/j.anucene.2009.03.005 Abdel-Khalik, H. S., Turinsky, P. J., & Jessee, M. A. (2008). 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. https://doi.org/10.13182/NSE159-256 Abdel-Khalik, H., Turinsky, P., Jessee, M., Elkins, J., Stover, T., & Iqbal, M. (2008, December). Uncertainty Quantification, Sensitivity Analysis, and Data Assimilation for Nuclear Systems Simulation. NUCLEAR DATA SHEETS, Vol. 109, pp. 2785–2790. https://doi.org/10.1016/j.nds.2008.11.010 Abdel-Khalik, H. S., & Turinsky, P. J. (2005). Adaptive core simulation employing discrete inverse theory - Part I: Theory. Nuclear Technology, 151(1), 21-. Abdel-Khalik, H. S., & Turinsky, P. J. (2005, July). Adaptive core simulation employing discrete inverse theory - Part II: Numerical experiments. NUCLEAR TECHNOLOGY, Vol. 151, pp. 22–34. https://doi.org/10.13182/NT05-A3628 Kastanya, D. Y. F., & Turinsky, P. J. (2005). 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. https://doi.org/10.13182/NSE05-A2501 Turinsky, P. J. (2005). Nuclear fuel management optimization: A work in progress. Nuclear Technology, 151(1), 08-. Mertyurek, U., & Turinsky, P. J. (2004). Super-nodal methods for space-time kinetics. NUCLEAR SCIENCE AND ENGINEERING, 147(2), 93–126. https://doi.org/10.13182/NSE04-A2422 Karve, A. A., & Turinsky, P. J. (2001). FORMOSA-B: A boiling water reactor in-core fuel management optimization package III. NUCLEAR TECHNOLOGY, 135(3), 241–251. https://doi.org/10.13182/NT01-A3219 Keller, P. M., & Turinsky, P. J. (2001). FORMOSA-P three-dimensional/two-dimensional geometry collapse methodology. NUCLEAR SCIENCE AND ENGINEERING, 139(3), 235–247. https://doi.org/10.13182/NSE01-A2234 Karve, A. A., & Turinsky, P. J. (2000). FORMOSA-B: A boiling water reactor in-core fuel management optimization package II. NUCLEAR TECHNOLOGY, 131(1), 48–68. https://doi.org/10.13182/NT00-A3104 Moore, B. R., Turinsky, P. J., & Karve, A. A. (1999). Formosa-B: A boiling water reactor in-core fuel management optimization package. NUCLEAR TECHNOLOGY, 126(2), 153–169. https://doi.org/10.13182/NT99-A2964 Turinsky, P. J. (1999). Mathematical optimization of incore nuclear fuel management decisions: status and trends. ATW - Internationale Zeitschrift Fur Kernenergie, 44(7), 454. Moore, B. R., & Turinsky, P. J. (1998). Higher order generalized perturbation theory for boiling water reactor in-core fuel management optimization. NUCLEAR SCIENCE AND ENGINEERING, 130(1), 98–112. https://doi.org/10.13182/NSE98-A1993 Ye, J. Q., & Turinsky, P. J. (1998). Pressurized water reactor core maneuvering utilizing optimal control theory. NUCLEAR SCIENCE AND ENGINEERING, 129(2), 97–123. https://doi.org/10.13182/NSE98-A1967 Yacout, A. M., Turinsky, P. J., Al-Chalabi, R., & Rasdorf, W. J. (1989). 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.