A semi-implicit numerical scheme for transient two-phase flows on unstructured grids
Creators
- 1. Korea Atomic Energy Research Institute (KAERI), Dukjin 150, Yuseong, Daejeon 305-353 (Korea, Republic of)
Description
A component-scale 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 an unstructured grid to make CUPID very useful for flow analysis in complicated geometries. For the numerical solution scheme, the semi-implicit method of the RELAP5 code, which has been proved to be very stable and accurate for most practical applications, was used with some modifications for an application to an unstructured non-staggered grid. This paper presents the modified semi-implicit numerical method for an unstructured grid and the preliminary results of the calculations
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2008.08.017Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2008.08.017;
- PII
- S0029-5493(08)00461-5;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 238
- Journal Issue
- 12
- Journal Page Range
- p. 3403-3412
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40053159
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- GEOMETRY; NUMERICAL SOLUTION; SIMULATION; TRANSIENTS; TWO-PHASE FLOW; WATER COOLED REACTORS
- Descriptors DEC
- FLUID FLOW; MATHEMATICAL SOLUTIONS; MATHEMATICS; REACTORS
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.