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- W1994396908 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." @default.
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- W1994396908 date "2010-12-31" @default.
- W1994396908 modified "2023-10-16" @default.
- W1994396908 title "THE CUPID CODE DEVELOPMENT AND ASSESSMENT STRATEGY" @default.
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- W1994396908 doi "https://doi.org/10.5516/net.2010.42.6.636" @default.
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