4.5 Article

Experimental investigation on flow oscillation of boiling two-phase flow in a single rod channel

期刊

ANNALS OF NUCLEAR ENERGY
卷 158, 期 -, 页码 -

出版社

PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.anucene.2021.108281

关键词

Visualization; Experiment; Flow boiling; Flow oscillation; Bubble

资金

  1. National Natural Science Foundation of China [U1867219]
  2. Science and Technology on Reactor System Design Technology Laboratory

向作者/读者索取更多资源

This paper investigates the mechanism of flow oscillations in a single rod channel through visual experimental study, identifying different types of flow oscillations and their characteristics in relation to bubble behavior. Furthermore, the analysis and discussion on the effect of thermal conditions on flow oscillation are discussed in detail.
Flow oscillation of two-phase flow has significant effect on the safety of relative industrial application, such as nuclear reactor. Oscillation of mass flux can induce undesirable such as boiling crisis. In this paper, a visual experimental study is carried out in a single rod channel to investigate the mechanism of flow oscillations. The system pressure is from 0.1 MPa to 1.0 MPa with different mass flux and inlet subcooling. According to the characteristics of the flow oscillation combined with bubble behavior, the flow oscillation is divided into slightly flow oscillation with high subcooled and high mass flux condition, boiling onset flow oscillation with bubbly flow and flow patterns transition oscillation with flow pattern transition. In this paper, the effect of thermal conditions on flow oscillation is also analyzed and discussed in detail. (C) 2021 Elsevier Ltd. All rights reserved.

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