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http://dx.doi.org/10.5516/NET.02.2014.023

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

Yoon, Han Young (Korea Atomic Energy Research Institute)
Lee, Jae Ryong (Korea Atomic Energy Research Institute)
Kim, Hyungrae (Korea Atomic Energy Research Institute)
Park, Ik Kyu (Korea Atomic Energy Research Institute)
Song, Chul-Hwa (Korea Atomic Energy Research Institute)
Cho, Hyoung Kyu (Department of Nuclear Engineering, Seoul National University)
Jeong, Jae Jun (School of Mechanical Engineering, Pusan National University)
Publication Information
Nuclear Engineering and Technology / v.46, no.5, 2014 , pp. 655-666 More about this Journal
Abstract
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.
Keywords
The CUPID Code; Domain Decomposition Parallel Method; Code Coupling Via Heat Structure; Steam Generator;
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Times Cited By KSCI : 3  (Citation Analysis)
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