Core Reload Design Using Genetic Optimization for Cost Savings in a Two-Reactor Power Plant With Used Fuel Sharing

References

• D. JANIN, “Core Design and Optimization of the High Conversion Small Modular Reactor,” PhD Thesis, Technische Universität München (2018).
   Google Scholar
• M. Z. NEJAD and G. R. ANSARIFAR, “Optimal Design of a Small Modular Reactor Core with Dual Cooled Annular Fuel Based on the Neutronics and Natural Circulation Parameters,” Nucl. Eng. Des., 360, 110518 (2020); https://doi.org/10.1016/j.nucengdes.2020.110518.
   Web of Science ®Google Scholar
• C. MARTIN-DEL-CAMPO et al., “Optimization of BWR Fuel Lattice Enrichment and Gadolinia Distribution Using Genetic Algorithms and Knowledge,” Ann. Nucl. Energy, 34, 4, 248 (2007); https://doi.org/10.1016/j.anucene.2006.12.008.
   Web of Science ®Google Scholar
• M. I. RADAIDEH et al., “Physics-Informed Reinforcement Learning Optimization of Nuclear Assembly Design,” Nucl. Eng. Des., 372, 110966 (2020).
   Web of Science ®Google Scholar
• C. LIN et al., “Pressurized Water Reactor Loading Pattern Design Using the Simple Tabu Search,” Nucl. Sci. Eng., 129, 1, 61 (1998); https://doi.org/10.13182/NSE98-A1963.
   Web of Science ®Google Scholar
• N. J. HILL and G. T. PARKS, “Pressurized Water Reactor In-Core Nuclear Fuel Management by Tabu Search,” Ann. Nucl. Energy, 75, 64 (2015); https://doi.org/10.1016/j.anucene.2014.07.051.
   Web of Science ®Google Scholar
• M. D. DECHAINE and M. A. FELTUS, “Nuclear Fuel Management Optimization Using Genetic Algorithms,” Nucl. Technol., 111, 1, 109 (1995); https://doi.org/10.13182/NT95-A35149.
   Web of Science ®Google Scholar
• E. ISRAELI and E. GILAD, “Novel Genetic Algorithm for Loading Pattern Optimization Based on Core Physics Heuristics,” Ann. Nucl. Energy, 118, 35 (2018); https://doi.org/10.1016/j.anucene.2018.03.042.
   Web of Science ®Google Scholar
• A. ZAMEER et al., “Fractional-Order Particle Swarm Based Multi-Objective PWR Core Loading Pattern Optimization,” Ann. Nucl. Energy, 135, 106982 (2020); https://doi.org/10.1016/j.anucene.2019.106982.
   Web of Science ®Google Scholar
• K. E. OTTINGER et al., “SMR Fuel Cycle Optimization and Control Rod Depletion Using NESTLE and LWROpt,” Proc. Advances in Nuclear Fuel Management V (ANFM 2015), Hilton Head Island, South Carolina, March 29–April 1, 2015, American Nuclear Society (2015).
   Google Scholar
• K. E. OTTINGER and G. I. MALDONADO, “SMR Fuel Cycle Optimization Using LWROpt,” J. Nucl. Eng. Radiat. Sci., 3, 1 (2017); https://doi.org/10.1115/1.4034573.
   Google Scholar
• K. A. ANDERSON, P. J. TURINSKY, and P. M. KELLER, “Improvement of OCEON-P Optimization Capabilities,” Trans. Am. Nucl. Soc., 96, 1, 201 (2007).
   Google Scholar
• S. DU, “Implementation of Genetic Algorithms and Parallel Simulated Annealing in OCEON- P,” PhD Thesis, North Carolina State University (2008).
   Google Scholar
• D. J. KROPACZEK, “COPERNICUS: A Multi-Cycle Optimization Code for Nuclear Fuel Based on Parallel Simulated Annealing with Mixing of States,” Prog. Nucl. Energy, 53, 6, 554 (2011); https://doi.org/10.1016/j.pnucene.2010.08.009.
   Web of Science ®Google Scholar
• B. LILLEY and T. S. PALMER, “Multi-Reactor, Multicycle Optimization of Core Reload Design for an SMR Power Plant,” Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Virtual Meeting, October 3–7, 2021, American Nuclear Society (2021).
   Google Scholar
• B. LILLEY and T. S. PALMER, “A Comparison of Random Sampling and Genetic Optimization in a Multi-Reactor Shared Fuel Pool Power Plant,” Proc. Int. Conf. Physics of Reactors, Pittsburgh, Pennsylvania, May 15–20, 2022, American Nuclear Society (2022).
   Google Scholar
• “NuScale Standard Plant Design Certification Application, Chapter Four, Reactor,” ML20036D438 (Rev 4), NuScale Power, LLC (2020).
   Google Scholar
• A. SOLDATOV and T. S. PALMER, “A Five-Year Core for a Small Modular Light Water Reactor,” Nucl. Sci. Eng., 167, 1, 77 (2011); https://doi.org/10.13182/NSE09-39.
   Web of Science ®Google Scholar
• M. EDENIUS et al., “CASMO-4, A Fuel Assembly Burnup Program, User’s Manual,” Studsvik 0SOA-9501, Studsvik of America, Inc. (1995).
   Google Scholar
• “SIMULATE-3: Advanced Three-Dimensional Two-Group Reactor Analysis Code—User’s Manual (University Release),” SSP-09/447-U Rev 0, Studsvik Scandpower, Inc. (2009).
   Google Scholar
• B. M. ADAMS, “The DAKOTA Toolkit for Parallel Optimization and Uncertainty Analysis,” Sandia National Laboratories (2008).
   Google Scholar
• N. TSOULFANIDIS, The Nuclear Fuel Cycle, American Nuclear Society, La Grange Park, Illinois (2013).
   Google Scholar
• H. W. GRAVES, Nuclear Fuel Management, John Wiley & Sons, Inc. (1979).
   Google Scholar
• M. BUNN et al., “The Economics of Reprocessing vs. Direct Disposal of Spent Nuclear Fuel,” Belfer Center (2003).
   Google Scholar
• “Nuclear Costs in Context,” Nuclear Energy Institute Inc. (2022).
   Google Scholar