Experimental Study on Boiling Two-Phase Flow Instability in a Single Helically Coiled Tube

被引：0

作者：

Zheng, Pengde ^{[1
,2
]}

Tang, Qifen ^{[2
]}

Li, Zhenzhong ^{[1
]}

Wang, Ningyuan ^{[1
]}

Chen, Deqi ^{[1
]}

机构：

[1] Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing

[2] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2024年 / 45卷 / 04期

关键词：

Density wave oscillations; Flow boiling; Flow instability; Helically coiled tube;

D O I：

10.13832/j.jnpe.2024.04.0061

中图分类号：

学科分类号：

摘要：

The boiling phase change happened in the heating channel will induce flow instability. Thus, studying the two-phase flow instability in helically coiled tubes is of great significance in the design and operation of helical-coil one-through steam generators. In this paper, the boiling two-phase flow experiment in a single helically coiled tube is carried out on the thermal experimental platform, and the flow instability phenomenon when boiling two-phase flow occurs in the helically coiled tube is studied. In the experiment, the boiling two-phase flow instability is classified by analyzing the variation and spectral characteristics of parameters such as flow rate and pressure drop in the helically coiled tube at different times during the rise of heating power. The results show that when the experimental parameters are in the range of 0.1~3 MPa for pressure, 300~1200 kg/h for flow rate, 20~100℃ for inlet subcooling and 0~200 kW for heating power in the experimental section, the helically coiled tube heating channel exhibits flow drift instability as the power increases. Once the flow drifts to another flow value, low-amplitude high-frequency density wave oscillations occur under low steam quality conditions, while high-amplitude low-frequency density wave oscillations occur under high steam quality conditions. In addition, the increase of inlet subcooling, inlet flow rate and system pressure will improve the stability of the system. © 2024 Atomic Energy Press. All rights reserved.

引用

页码：61 / 68

页数：7

共 6 条

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