The objective of this paper is to develop a new hybrid mutation in genetic algorithm (GA) for designing the loading pattern (LP) in pressurized water reactors. Because of huge number of possible combinations for the fuel assemblies (FA’s) loading in a core, finding the optimum solution is truly a complex problem. In common genetic algorithm the mutation and crossover techniques are used to optimize an objective function but in this paper a new hybrid mutation is presented. In this study flattening of power inside a reactor core is chosen as an objective function. To obtain optimal FA arrangement, a core reload package code, MAKNOGA, based on well established MAKGA code is developed. This code is applicable for all types of PWR core having different geometries and designs with an unlimited number of FA types. The result is well improved in comparison with pattern proposed by designer.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4355-0
PROCEEDINGS PAPER
PWR Nuclear Power Plants Fuel Management Optimization
Ahmad Zolfaghari,
Ahmad Zolfaghari
University of Shahid Beheshti, Tehran, Iran
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Hamid Minuchehr,
Hamid Minuchehr
University of Shahid Beheshti, Tehran, Iran
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Ali Noroozy,
Ali Noroozy
University of Shahid Beheshti, Tehran, Iran
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Peymaan Makarachi,
Peymaan Makarachi
University of Shahid Beheshti, Tehran, Iran
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F. Koshahval
F. Koshahval
University of Shahid Beheshti, Tehran, Iran
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Ahmad Zolfaghari
University of Shahid Beheshti, Tehran, Iran
Hamid Minuchehr
University of Shahid Beheshti, Tehran, Iran
Ali Noroozy
University of Shahid Beheshti, Tehran, Iran
Peymaan Makarachi
University of Shahid Beheshti, Tehran, Iran
F. Koshahval
University of Shahid Beheshti, Tehran, Iran
Paper No:
ICONE17-75924, pp. 667-672; 6 pages
Published Online:
February 25, 2010
Citation
Zolfaghari, A, Minuchehr, H, Noroozy, A, Makarachi, P, & Koshahval, F. "PWR Nuclear Power Plants Fuel Management Optimization." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control. Brussels, Belgium. July 12–16, 2009. pp. 667-672. ASME. https://doi.org/10.1115/ICONE17-75924
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