フクゴウ リュウロ ニ オケル キエキ ニソウリュウタイ ノ リュウドウ ダイ3ポウ ハッタツ シタ ナガレ ノ リュウリョウ ハイブン ケイサン

In the subchannel analysis of nuclear reactor rod bundles it is necessary to predict the flow distributions among different regions of the bundle. In this paper, the fully developed two-phase flow distributions in two interconnected subchannels of different cross-sectional area were calculated. The mathematical model consists of four equations: the two continuity equations for gas and liquid phases, the equation of equal pressure drop of both subchannels and the empirical correlation of the flow distribution of the gas phase. The experimental data presented in the previous reports of this series have been used for this empirical correlation. Comparisons are made between the calculations and the experimental data reported by other investigators as well as by the present authors. Good agreements are obtained

フクゴウ リュウロ ニ オケル キエキ ニソウリュウタイ ノ リュウドウ ダイ3ポウ ハッタツ シタ ナガレ ノ リュウリョウ ハイブン ケイサン

In the subchannel analysis of nuclear reactor rod bundles it is necessary to predict the flow distributions among different regions of the bundle. In this paper, the fully developed two-phase flow distributions in two interconnected subchannels of different cross-sectional area were calculated. The mathematical model consists of four equations: the two continuity equations for gas and liquid phases, the equation of equal pressure drop of both subchannels and the empirical correlation of the flow distribution of the gas phase. The experimental data presented in the previous reports of this series have been used for this empirical correlation. Comparisons are made between the calculations and the experimental data reported by other investigators as well as by the present authors. Good agreements are obtained