原子能科学技术 ›› 2020, Vol. 54 ›› Issue (9): 1582-1588.DOI: 10.7538/yzk.2020.youxian.0066

• 第十六届全国反应堆热工流体学术会议优秀论文选 • 上一篇    下一篇

基于OpenFOAM的铅基快堆流体通道内两相流研究

杨晟;张有鹏   

  1. 复旦大学 现代物理研究所,上海200433
  • 出版日期:2020-09-20 发布日期:2020-09-20

Study on Two-phase Flow in Fluid Channel of Lead-based Fast Reactor Based on OpenFOAM

YANG Sheng;ZHANG Youpeng   

  1. Institute of Modern Physics, Fudan University, Shanghai 200433, China
  • Online:2020-09-20 Published:2020-09-20

摘要:

为研究铅基快堆中铅/铅铋的特殊热物性导致的在两相流情况下的热工水力特性,模拟流体通道中空泡存在对堆芯的输热能力以及安全性的影响,本文采用开源的CFD计算软件OpenFOAM,应用基于VOF方法的数值模拟,构建了铅基快堆中常见的三角形通道模型,通过与子通道程序的验证和单相条件下实验的校核,检验了所用代码的准确性,并对堆内冷却剂通道的两相流进行了模拟。模拟结果表明:随着两相流流速的增大,冷却剂出口温度降低。气液两相流在内通道流动过程中,气相基本在通道内部流动。随着轴向高度的升高,气泡会在内通道的中心区域聚合;燃料组件的角通道是气泡含量多的区域,会造成局部传热恶化,导致组件烧毁。

关键词: 铅基快堆, 两相流, OpenFOAM, VOF模型

Abstract:

In order to study the thermal-hydraulic characteristics of two-phase flow caused by the special thermal properties of lead/lead-bismuth in lead-based fast reactors, the influence of bubble in fluid channel on the heat transfer capacity and safety of the core was simulated. In this paper the open source CFD calculation software OpenFOAM was adopted, and the numerical simulation was applied based on VOF method to construct a common triangular channel model in lead-based fast reactor. By simulating the two-phase flow of the coolant channel, it is found that as the flow rate increases, the outlet temperature of the coolant decreases. In the flow process of the gas-liquid two-phase flow in the channel, it can be found that the gas phase basically flows inside the channel. In the simulation of the fuel assembly, the corner channel is an area with a large amount of bubbles, which will cause the local heat transfer to deteriorate and cause the fuel assembly to burn out.

Key words: lead-based fast reactor, two-phase fluid, OpenFOAM, VOF model