CUPID-SG is a component scale thermal-hydraulic analysis tool based on CUPID, which is intended to be a computer code for analyzing two-phase flows in porous media with tube bundles such as PWR steam generators. CUPID-SG adopts two-fluid, three-field conservation equations, and uses an in-house semi-implicit solver to obtain numerical efficiency. CUPID-SG can handle unstructured meshes that enable its application in complex geometries. CUPID-SG also has constitutive models for a two-phase flow map, interfacial heat and mass transfer, interfacial drag, wall friction, wall heating, and heat partitioning. CUPID-SG is benchmarked against a few cases of FRIGG tests to confirm that the transport models are correctly implemented and the code is applicable to a two-phase flow over tube bundles. The comparison showed that the constitutive models are properly implemented and CUPID-SG is capable of analyzing a two-phase boiling flow over tube bundles.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5580-5
PROCEEDINGS PAPER
Preliminary Analysis of Two-Phase Flow in a Steam Generator Using CUPID-SG
Hyungrae Kim,
Hyungrae Kim
Korea Atomic Energy Research Institute, Daejeon, Korea
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Soo Hyoung Kim,
Soo Hyoung Kim
Korea Atomic Energy Research Institute, Daejeon, Korea
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Seung-Jun Lee,
Seung-Jun Lee
Korea Atomic Energy Research Institute, Daejeon, Korea
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Ik Kyu Park,
Ik Kyu Park
Korea Atomic Energy Research Institute, Daejeon, Korea
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Han Young Yoon
Han Young Yoon
Korea Atomic Energy Research Institute, Daejeon, Korea
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Hyungrae Kim
Korea Atomic Energy Research Institute, Daejeon, Korea
Soo Hyoung Kim
Korea Atomic Energy Research Institute, Daejeon, Korea
Seung-Jun Lee
Korea Atomic Energy Research Institute, Daejeon, Korea
Ik Kyu Park
Korea Atomic Energy Research Institute, Daejeon, Korea
Han Young Yoon
Korea Atomic Energy Research Institute, Daejeon, Korea
Paper No:
ICONE21-15124, V003T10A006; 11 pages
Published Online:
February 7, 2014
Citation
Kim, H, Kim, SH, Lee, S, Park, IK, & Yoon, HY. "Preliminary Analysis of Two-Phase Flow in a Steam Generator Using CUPID-SG." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes. Chengdu, China. July 29–August 2, 2013. V003T10A006. ASME. https://doi.org/10.1115/ICONE21-15124
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