Research on Void Fraction Models for Vertically Upward Two-Phase Cross-Flow in Horizontal Tube Bundle

JIANG Nai-bin; ZANG Feng-gang; ZHANG Yi-xiong; GUAN Hui

Mar. 2025

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Article Navigation > Nuclear Power Engineering > 2013 > 34(3): 67-70

JIANG Nai-bin, ZANG Feng-gang, ZHANG Yi-xiong, GUAN Hui. Research on Void Fraction Models for Vertically Upward Two-Phase Cross-Flow in Horizontal Tube Bundle[J]. Nuclear Power Engineering, 2013, 34(3): 67-70.

Citation:

JIANG Nai-bin, ZANG Feng-gang, ZHANG Yi-xiong, GUAN Hui. Research on Void Fraction Models for Vertically Upward Two-Phase Cross-Flow in Horizontal Tube Bundle[J]. Nuclear Power Engineering, 2013, 34(3): 67-70.

Citation:

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Research on Void Fraction Models for Vertically Upward Two-Phase Cross-Flow in Horizontal Tube Bundle

1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China;
2. National Energy Pressurized Water Reactor Technology Research Center, Chengdu, 610041, China

Received Date: 2012-02-07
Rev Recd Date: 2012-08-08

Available Online: 2025-03-08

Abstract

Abstract

Compared with the void fraction models of two-phase flow in tubes,the research on void fraction models for vertically upward two-phase cross-flow in horizontal tube bundle are not enough.With experimental data,the existing void fraction models of vertically upward two-phase cross-flow in horizontal tube bundle are compared.Moreover,two existing void fraction models are modified.The modified void fraction models are validated by some other experimental data.The result shows the modified void fraction models give better prediction than the original models.
- Void fraction,
- Two-phase flow,
- Tube bundle,
- Cross-flow