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http://dx.doi.org/10.5516/NET.2010.42.6.636

THE CUPID CODE DEVELOPMENT AND ASSESSMENT STRATEGY  

Jeong, J.J. (Korea Atomic Energy Research Institute (KAERI))
Yoon, H.Y. (Korea Atomic Energy Research Institute (KAERI))
Park, I.K. (Korea Atomic Energy Research Institute (KAERI))
Cho, H.K. (Korea Atomic Energy Research Institute (KAERI))
Publication Information
Nuclear Engineering and Technology / v.42, no.6, 2010 , pp. 636-655 More about this Journal
Abstract
A thermal-hydraulic code, named CUPID, has been being developed for the realistic analysis of transient two-phase flows in nuclear reactor components. The CUPID code development was motivated from very practical needs, including the analyses of a downcomer boiling, a two-phase flow mixing in a pool, and a two-phase flow in a direct vessel injection system. The CUPID code adopts a two-fluid, three-field model for two-phase flows, and the governing equations are solved over unstructured grids with a semi-implicit two-step method. This paper presents an overview of the CUPID code development and assessment strategy. It also presents the code couplings with a system code, MARS, and, a three-dimensional reactor kinetics code, MASTER.
Keywords
The CUPID Code Development; Assessment Strategy; Component Scale; Two-Fluid Three-Field Model; Code Couplings;
Citations & Related Records
Times Cited By KSCI : 4  (Citation Analysis)
Times Cited By Web Of Science : 1  (Related Records In Web of Science)
Times Cited By SCOPUS : 3
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