A two-phase analysis code, CUPID, has been developed for a realistic simulation of transient two-phase flows in light water nuclear reactor components. In the CUPID code, a two-fluid three-field model is adopted and the governing equations are solved on unstructured grids for flow analyses in complicated geometries. For the numerical solution scheme, the semi-implicit method of the RELAP5 code, which has been proved to be stable and accurate for most practical applications, was used with some modifications for an application to unstructured non-staggered grids. In the present study, constitutive relations of the two-fluid model were employed including models for an interfacial drag force, interfacial heat transfer, interfacial area, wall heat partition and interfacial non-drag forces. The inter-phase surface topology concept which was proposed for CFD-BWR was applied in order for the present numerical solver to be applicable not only to dispersed flows but also to a flow with a sharp interface. The current paper presents some preliminary calculation results which have been performed for the verification of the inter-phase surface topology. This paper is also concerned with the effects of interpolation schemes on the simulation of two-phase flows. So as to assure a high numerical accuracy, the second-order upwind scheme is implemented into the CUPID code. The calculation results with the second-order upwind scheme were compared with those with the first-order upwind difference. For the comparison, a single-phase laminar flow and a phase separation were simulated. The comparison results among the two interpolation schemes and the exact solutions apparently showed a reduced numerical diffusion with the second order scheme.
Skip Nav Destination
17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4353-6
PROCEEDINGS PAPER
Recent Improvements to the Multi-Dimensional Semi-Implicit Two-Phase Flow Solver, CUPID Available to Purchase
H. K. Cho,
H. K. Cho
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Search for other works by this author on:
I. K. Park,
I. K. Park
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Search for other works by this author on:
H. D. Lee,
H. D. Lee
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Search for other works by this author on:
J. J. Jeong
J. J. Jeong
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Search for other works by this author on:
H. K. Cho
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
I. K. Park
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
H. D. Lee
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
J. J. Jeong
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Paper No:
ICONE17-75724, pp. 599-608; 10 pages
Published Online:
February 25, 2010
Citation
Cho, HK, Park, IK, Lee, HD, & Jeong, JJ. "Recent Improvements to the Multi-Dimensional Semi-Implicit Two-Phase Flow Solver, CUPID." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance. Brussels, Belgium. July 12–16, 2009. pp. 599-608. ASME. https://doi.org/10.1115/ICONE17-75724
Download citation file:
9
Views
Related Proceedings Papers
Related Articles
Separation of a Two-Phase Slug Flow in Branched 90 deg Elbows
J. Fluids Eng (May,2010)
Steady-State and Transient Behavior of Gas/Liquid Phase Boundaries in Impulse Pipes
J. Eng. Gas Turbines Power (March,2013)
Transient Double-Diffusive Convection of Water Around 4 ° C in a Porous Cavity
J. Heat Transfer (May,2009)
Related Chapters
Introduction
Heat Transfer & Hydraulic Resistance at Supercritical Pressures in Power Engineering Applications
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Pre-Service Cleaning Philosophy for Boiling Water Reactors
Cleaning Stainless Steel