Application of Evolutionary Simulated Annealing Method to Design a Small 200 MWt Reactor Core
Main Article Content
Abstract
This paper presents the application of an evolutionary simulated annealing (ESA) method to design a small 200 MWt reactor core. The core design is based on a reference ACPR50 reactor deployed in a floating nuclear power plant. The core consists of 37 typical 17x17 PWR fuel assemblies with three different U-235 enrichments of 4.45, 3.40 and 2.35 wt%. Core loading pattern (LP) has been optimized for obtaining the cycle length of 900 effective full power days, while minimizing the average U-235 enrichment and the radial power peaking factor. The optimization process was performed by coupling the ESA method with the COREBN module of the SRAC2006 system code.
Article Details
Keywords
Small reactor, core design optimization, ESA method
References
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[4]. Mahlers Y P., “Core loading pattern optimization based on simulated annealing and successive linear programming”, Ann. Nucl. Energy, 22, p 29, 1995.
[5]. J. G. Stevens J G., Smith K S, Rempe K R, Downar T J, “Optimization of pressurized water reactor shuffling by simulated annealing with heuristics”, Nucl. Sci. Eng., 121, p 67, 1995.
[6]. Sikander M M, Aneela A, Nasir M M., “Adaptive Simulated Annealing Methodology for Fuel Loading Pattern Optimization”, Nucl. Sci. J., 37, p 340, 2000.
[7]. Hyun C L, Hyung J S, Chang H K., “Parallel computing adaptive simulated annealing scheme for fuel assembly loading pattern optimization in PWRs”, Nucl. Technol., 135, p 39, 2001.
[8]. Timothy R, Jean R, Stephen S, Robert S C., “Optimization of PWR fuel assembly radial enrichment and burnable poison location based on adaptive simulated annealing”, Nucl. Eng. Des., 239, p 1019, 2009.
[9]. Aneela Z, Sikander M M, Nasir M M., “Core loading pattern optimization of a typical twoloop 300 MWe PWR using Simulated Annealing (SA), novel crossover Genetic Algorithms (GA) and hybrid GA(SA) schemes, Ann”, Nucl. Energy, 65, p 122, 2014.
[10]. DeChaine M D and Feltus M A., “Nuclear fuel management optimization using genetic algorithms”, Nucl. Technol., 111, p 109, 1995.
[11]. Parks G T., “Multiobjective pressurized water reactor reload core design by nondominated genetic algorithm search”, Nucl. Sci. Eng., 124, p 178, 1996.
[12]. DeChaine D M and Feltus M A., “Fuel management optimization using genetic algorithms and expert knowledge”, Nucl. Sci. Eng., 124, p 188, 1996.
[13]. Axmann J K., “Parallel adaptive evolutionary algorithms for pressurized water reactor reload pattern optimization”, Nucl. Technol., 119, p 276, 1997.
[14]. Babazadeh D, Boroushaki M, Lucas C., “Optimization of fuel core loading pattern design in a VVER nuclear power reactors using Particle Swarm Optimization (PSO)”, Ann. Nucl. Energy, 36, p 923, 2009.
[15]. Yadav R D S, Gupta H P., “Optimization studies of fuel loading pattern for a typical Pressurized Water Reactor (PWR) using particle swarm method”, Ann. Nucl. Energy, 38, p 2086, 2011.
[16]. Jamalipour M, Sayareh R, Gharib M, Khoshahval F, Karimi M R., “Quantum behaved Particle Swarm Optimization with Differential Mutation operator applied to WWER-1000 in-core fuel management optimization”, Ann. Nucl. Energy, 54, p 134, 2013.
[17]. Phan, G.T.T., Do, Q.B., Ngo, Q.H., Tran, T.A., Tran, H.N., “Application of differential evolution algorithm for fuel loading optimization of the dnrr research reactor”, Nuclear Engineering and Design 362, 110582, 2020.
[18]. Aghaie M, Mahmoudi S M., “A novel multi objective Loading Pattern Optimization by Gravitational Search Algorithm (GSA) for WWER1000 core”, Prog. Nucl. Energy, 93, p 1, 2016.
[19]. Viet Phu Tran, Giang T.T. Phan, Van Khanh Hoang, Pham Nhu Viet Ha, Akio Yamamoto, Hoai Nam Tran., “Evolutionary simulated annealing for fuel loading optimization of VVER-1000 reactor”, Annals of Nuclear Energy 151, 107938, 2021.
[20]. U.S. Nuclear Regulatory Commission (NRC), “Westinghouse AP1000 Design Control Documentation (DCD)”, Westinghouse Electric Company, 2011, Chapter 4, Rev. 19, 2011.
[21]. VK Hoang, VP Tran, VT Dinh, HN Tran., “Conceptual design of a small-pressurized water reactor using the AP1000 fuel assembly design”, Nuclear Science and Technology, Vol.9, No. 2, p 25, 2019.
[22]. K Okumura, T Kugo, K Kaneko, K Tsuchihashi., “SRAC2006: A Comprehensive Neutronics Calculation Code System”, JAEAData/Code, 2007, 2007-004, 2007.
[23]. Keisuke Okumura., “COREBN: A Core Burnup Calculation Module for SRAC2006”, JAEA-Data/Code, 2007-003, 2007.