Journal of Nuclear Science and Technology, Vol.50, No.8, pp.813-827, 2013

Author

H.Kim, S.H.Kim, S.-J.Lee, I.K.Park, H.Y.Yoon, H.K.Cho, J.J.Jeong

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.

https://doi.org/10.1016/j.pnucene.2014.06.007