Void fraction distribution of vapor-water two-phase flow in vertical tube bundles using gamma densitometer

CHENG Jie; GUO Yajun; WANG Teng; GUI Miao; LIU Zhaohui; SUI Zhiqiang

doi:10.11949/j.issn.0438-1157.20181277

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Void fraction distribution of vapor-water two-phase flow in vertical tube bundles using gamma densitometer

Fluid dynamics and transport phenomena | 更新时间：2026-07-24

- Void fraction distribution of vapor-water two-phase flow in vertical tube bundles using gamma densitometer
- CIESC Journal Vol. 70, Issue 4, Pages: 1375-1382(2019)
- 作者机构：
  
  1.西安建筑科技大学建筑设备科学与工程学院，陕西西安 710055
  2.西安交通大学动力工程多相流国家重点实验室，陕西西安 710049
- 作者简介：
- 基金信息：
- DOI：10.11949/j.issn.0438-1157.20181277
  CLC： O 359;TK 124
- Received：31 October 2018，
  
  Revised：2019-01-08，
  
  Online First：15 June 2020，
  
  Published：12 April 2019
- 稿件说明：
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程洁, 郭亚军, 王腾, 桂淼, 刘朝辉, 随志强. γ射线法测量高压管束间气液两相流的截面含气率分布[J]. 化工学报, 2019, 70(4): 1375-1382

CHENG Jie, GUO Yajun, WANG Teng, GUI Miao, LIU Zhaohui, SUI Zhiqiang. Void fraction distribution of vapor-water two-phase flow in vertical tube bundles using gamma densitometer[J]. CIESC Journal, 2019, 70(4): 1375-1382
程洁, 郭亚军, 王腾, 桂淼, 刘朝辉, 随志强. γ射线法测量高压管束间气液两相流的截面含气率分布[J]. 化工学报, 2019, 70(4): 1375-1382 DOI： 10.11949/j.issn.0438-1157.20181277.

CHENG Jie, GUO Yajun, WANG Teng, GUI Miao, LIU Zhaohui, SUI Zhiqiang. Void fraction distribution of vapor-water two-phase flow in vertical tube bundles using gamma densitometer[J]. CIESC Journal, 2019, 70(4): 1375-1382 DOI： 10.11949/j.issn.0438-1157.20181277.

摘要

在立式蒸汽发生器垂直管束间的气液两相流中，截面含气率是其中一个重要参数。使用γ射线法对高温高压下垂直管束间气液两相流截面含气率的分布规律进行了实验研究。实验压力分别为5、7、9 MPa，质量流速为300 kg/(m

⋅s)，热力学干度的范围为0.003 ~ 0.4。实验得到了垂直管束间截面含气率随热力学干度、体积含气率和压力的变化关系；并与经典公式的计算结果对比发现，在低干度区域，实验结果与Miropolskii模型、Smith模型和Armand模型偏差较大，均大于30%，在高干度区域偏差较小；基于Armand理论，通过多元线性回归法拟合出本文工况下平均截面含气率的计算关联式，与日本核动力工程公司(NUPEC)的实验数据偏差小于15%。本研究对蒸汽发生器的结构设计和流动特性研究具有重要意义。

Abstract

In the vapor-water two-phase flow between vertical tube bundles of steam generators

void fraction is an important parameter. Gamma ray method was used to measure the void fraction distribution under high temperature and high pressure. The experimental pressures were 5

9 MPa

respectively，the mass flow was 300 kg/(m

∙s)

and the thermodynamic vapor quality ranged from 0.003 to 0.4. The distribution of the void fraction in vertical tube bundles was obtained and the effects of thermodynamic vapor quality and volume fraction were investigated. Compared with the classical formula calculation model

in the low-dry zone

the relative error between Miropolskii model

Smith model and Armand model with the experimental data are more than 30%

in areas with high dryness

error is small. Based on Armand model

a practical correlation of average void fraction and volume fraction on the section was calculated by multiple linear regression. It can be concluded that the correlations agree well with Japan Nuclear Power Engineering Corporation (NUPEC) experimental data

the relative error is less than 15%. The results show that a gamma ray method can be used to measure and predict the distribution of the void fraction in vertical tube bundles under high-temperature and high-pressure effectively. In general

it is of great significance to the structural design and flow characteristics of steam generator.

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references

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