RECENT IMPROVEMENTS IN THE CUPID CODE FOR A MULTI-DIMENSIONAL TWO-PHASE FLOW ANALYSIS OF NUCLEAR REACTOR COMPONENTS

The CUPID code has been developed at KAERI for a transient, three-dimensional analysis of a two-phase flow in light water nuclear reactor components. It can provide both a component-scale and a CFD-scale simulation by using a porous media or an open media model for a two-phase flow. In this paper, r...

Full description

Saved in:
Bibliographic Details
Published inNuclear engineering and technology Vol. 46; no. 5; pp. 655 - 666
Main Authors Yoon, Han Young, Lee, Jae Ryong, Kim, Hyungrae, Park, Ik Kyu, Song, Chul-Hwa, Cho, Hyoung Kyu, Jeong, Jae Jun
Format Journal Article
LanguageKorean
Published 2014
Subjects
Online AccessGet full text

Cover

Loading…
More Information
Summary:The CUPID code has been developed at KAERI for a transient, three-dimensional analysis of a two-phase flow in light water nuclear reactor components. It can provide both a component-scale and a CFD-scale simulation by using a porous media or an open media model for a two-phase flow. In this paper, recent advances in the CUPID code are presented in three sections. First, the domain decomposition parallel method implemented in the CUPID code is described with the parallel efficiency test for multiple processors. Then, the coupling of CUPID-MARS via heat structure is introduced, where CUPID has been coupled with a system-scale thermal-hydraulics code, MARS, through the heat structure. The coupled code has been applied to a multi-scale thermal-hydraulic analysis of a pool mixing test. Finally, CUPID-SG is developed for analyzing two-phase flows in PWR steam generators. Physical models and validation results of CUPID-SG are discussed.
Bibliography:KISTI1.1003/JNL.JAKO201431057576890
ISSN:1738-5733
2234-358X