Development of CUPID-SG for the analysis of two-phase flows in PWR steam generators
| Autor: | Hyoung Kyu Cho, Ik Kyu Park, Jae Jun Jeong, Seung Jun Lee, Hyungrae Kim, Soo Hyoung Kim, Han Young Yoon |
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| Rok vydání: | 2014 |
| Předmět: |
Source code
Conservation equations Computer science media_common.quotation_subject Pressurized water reactor Boiler (power generation) Energy Engineering and Power Technology Mechanics law.invention Nuclear Energy and Engineering law Boiling Heat transfer Polygon mesh Two-phase flow Safety Risk Reliability and Quality Waste Management and Disposal media_common |
| Zdroj: | Progress in Nuclear Energy. 77:132-140 |
| ISSN: | 0149-1970 |
| DOI: | 10.1016/j.pnucene.2014.06.007 |
| Popis: | CUPID-SG (CUPID code for Steam Generators) is a computer code for analyzing two-phase flows and heat transfer in PWR steam generators. It was derived from CUPID (Component Unstructured Program for Interfacial Dynamics), which is a component-scale thermo-hydraulic analysis code developed at KAERI (Korea Atomic Energy Research Institute). CUPID-SG shares the code structure with CUPID, which adopts two-fluid, three-field conservation equations, and semi-implicit numerical algorithms. CUPID-SG supports unstructured meshes to handle complex geometries, and adopts constitutive models of two-fluid model based system analysis codes for two-phase boiling flows. FRIGG tests are the benchmark in confirming the correct implementation of the transport models and the applicability of CUPID-SG to two-phase flows over heated tube bundles. A comparison with the FRIGG experiments showed that the constitutive models are properly implemented, and that CUPID-SG is capable of analyzing vertical two-phase boiling flows over tube bundles typically appearing in steam generators. |
| Databáze: | OpenAIRE |
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