Steam generator is one of the key equipments in the pressurized water reactor, from the performance point of view, it is necessary to apply optimization techniques to the design of the steam generator. In this work, the optimal designs of a U-tube steam generator (UTSG), taking minimization of the total volume and net weight as objective respectively, are carried out by considering thermohydraulic and geometric constraints using a complex-genetic algorithm (CGA). And the sensitivities of some parameters which influence the total volume and net weight of UTSG are also analyzed. Under the condition of constant secondary thermalhydraulic parameters of the steam generator, the optimal design indicates an obvious effect taking either the overall volume or the total weight of the steam generator as the objective. The optimization results show that the proposed optimal method is feasible and effective. And the results of optimal designs and sensitivity analysis would provide guidance in the engineering design of UTSG.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4933-0
PROCEEDINGS PAPER
Investigations on Optimal Design of a U-Tube Steam Generator
Hui-min Qin,
Hui-min Qin
Harbin Engineering University, Harbin, China
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Chang-qi Yan,
Chang-qi Yan
Harbin Engineering University, Harbin, China
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Meng Wang,
Meng Wang
Harbin Engineering University, Harbin, China
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Shi-jing He
Shi-jing He
Harbin Engineering University, Harbin, China
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Hui-min Qin
Harbin Engineering University, Harbin, China
Chang-qi Yan
Harbin Engineering University, Harbin, China
Meng Wang
Harbin Engineering University, Harbin, China
Shi-jing He
Harbin Engineering University, Harbin, China
Paper No:
ICONE18-29930, pp. 617-624; 8 pages
Published Online:
April 8, 2011
Citation
Qin, H, Yan, C, Wang, M, & He, S. "Investigations on Optimal Design of a U-Tube Steam Generator." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 5. Xi’an, China. May 17–21, 2010. pp. 617-624. ASME. https://doi.org/10.1115/ICONE18-29930
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