Proceedings of the KSME Conference (대한기계학회:학술대회논문집)
- 2001.06e
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- Pages.463-468
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- 2001
Thermal Hydraulic Analysis Methodology for PWR Nuclear Power Plant Steam Generators
원전 가압경수로 증기발생기 열유동 해석법
Abstract
This paper presents the methodology for thermal hydraulic analysis of Pressurized Water Reactor (PWR) steam generators. Topics include porous media approach, governing equations, physical models and correlations for solid-to-fluid interaction and heat transfer and numerical solution scheme. Some details about the ATHOS3 code currently used widely for thermal hydraulic analysis of PWR steam generators in the industry are presented. The ATHOS3 code is applied to the thermal hydraulic analysis of steam generator in the Korea YGN 3&4 nuclear power plant and the computed results are presented.