摘要
运用ANSYS平台下的CFX软件,对超临界水自然循环回路进行了数值模拟计算,得出超临界水自然循环流量和换热系数随功率的变化趋势。在研究范围内,随着功率的增加,自然循环流量和换热系数先逐渐增大,然后达到一个最大循环流量和换热系数。此后随着功率的继续增加,自然循环流量和换热系数将逐渐减小。流动换热进入密度波不稳定状态。在最大循环流量和换热系数附近时,加热器的出口温度接近拟临界温度点附近。通过数值模拟计算结果和国内已有的实验结果的比较,两者对比符合良好。
On the basis of supercritical water natural circulation test bench,using ANSYS CFD software,the computational fluid dynamics simulation calculation were carried out. Through the calculation the trend of the natural circulation rate and the heat transfer coefficient（HTC）with the change of the heating power was got. With the increase of the heating power,the mass flow and HTC increase gradually. Then the mass flow and the HTC reach a peak value. Since then,with the increase of power,natural circulation flow rate and HTC reduced gradually. The heat transfer and flow went into the density wave instability state. When the mass flow and HTC are approaching the peak value,the heater outlet temperature is close to the pseudo-critical temperature. Through the contrast of the numerical simulation results with the experiment,comparative results are in good agreement.
作者
马栋梁
周涛
齐实
肖泽军
MA Dong-liang1,2,3;ZHOU Tao1,2,3;QI Shi1,2,3;XIAO Ze-jun4(1. School of Nuclear science and Engineering,North China Electric Power University,Beijing 102026,China; 2. Institute of nuclear thermal-hydraulic safety and standardization,North China Electric Power University,Beijing 102206,China;3. Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy, North China Electric Power University,Beijing 102206,China; 4. Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,Sichuan 610041,Chin)
出处
《核科学与工程》
CAS
CSCD
北大核心
2018年第3期359-366,共8页
Nuclear Science and Engineering
基金
中核核反应堆热工水力技术重点实验室基金(20130901)
核反应堆系统设计技术重点实验室基金资助(2015BJ0151)
关键词
超临界水
自然循环
数值模拟
换热系数
不稳定性
密度波
Supercritical water
Natural circulation
Numerical simulation
Heat transfer coefficient（HTC）
Instability
Density wave
