B212 DEVELOPMENT OF THERMAL-HYDRAULIC COMPUTER CODE (TWO-FLUID MODEL) FOR STEAM GENERATOR(Nuclear power-3)

概要

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This paper describes the development and verification of PORTHOS-MHI, which is a gas-liquid two-phase flow simulation code with the two fluid model. This code was developed to analyze the thermal-hydraulic behaviors within a tube bundle of a steam generator (SG) of a Pressurized Water Reactor (PWR) nuclear power plant. The accuracy of the code was verified by comparing numerical results with the interfacial-velocity and the void-fraction distributions among of a tube-bundle experiment of a two-dimensional full-scale model SG with Freon R-123 as the secondary working fluid. Good agreement between the prediction of PORTHOS-MHI and experimental results were obtained.
一般社団法人日本機械学会の論文
2000-10-01