Mechanism study on passive siphon break of a low-pressure system

被引：0

作者：

Zheng Y. ^{[1
,2
]}

Huang S. ^{[1
]}

Guo X. ^{[1
]}

Wang N. ^{[1
]}

Pang T. ^{[1
]}

Jiang B. ^{[1
]}

Qin X. ^{[1
]}

Xia S. ^{[1
]}

Li M. ^{[2
]}

机构：

[1] Department of Engineering Physics, Tsinghua University, Beijing

[2] Institute of Nuclear Engineering and Science, National Tsing Hua University, Xinzhu, Taiwan, 030013, 030013, Taiwan

来源：

Huang, Shanfang (sfhuang@mail.tsinghua.edu.cn) | 1600年 / Atomic Energy Press卷 / 37期

关键词：

Downward; Loss of coolant accident; Nuclear safety; Passive loop; Siphon break; two-phase flow;

D O I：

10.13832/j.jnpe.2016.02.0156

中图分类号：

学科分类号：

摘要：

Siphon break has great influence on the Loss of Coolant-Accident (LOCA) for the nuclear safety. Experimental researches were carried out to study the siphon breaking process in a passive air-water two-phase flow loop. Flow processes were observed and important parameters were measured including pressure drops, water flowrate, and water level. Flow pattern in downward flow pipe is found to be bubbly flow, slug flow and falling film flow in turn. Experimental results show that the passive siphon breaking system could significantly increase pressure drop and reduce water flowrate. Therefore, under the LOCA condition, the goal to reduce the exposing risk of the reactor core can be realized by the siphon breaking effect. © 2016, Yuan Zi Neng Chuban She. All right reserved.

引用

页码：156 / 159

页数：3