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机构地区:[1]中国核动力研究设计院中核核反应堆热工水力技术重点实验室,成都610041
出 处:《核动力工程》2011年第3期82-86,共5页Nuclear Power Engineering
摘 要:采用2个相同的矩形加热通道和1个不受热大旁通通道构成实验段,在高温高压实验台架上对并联多通道流动不稳定性进行系统的实验研究。主要研究系统压力、质量流速和入口过冷度对流动不稳定性的影响。以并联多通道发生流动不稳定时矩形通道热工参数为基准绘制过冷度数-相变数(Nsub-Npch)边界图,并将其与矩形双通道流动不稳定边界进行对比。结果表明,相近工况参数条件下,并联多通道脉动界限热流密度相对较高。The test section consisted of two heated rectangular channels connected in parallel and paral-leled by an unheated by-pass.Density wave oscillation in parallel rectangular channels was systematically observed on a two phase flow test rig operated at system pressures ranging from 1 to 10 Mpa.The oscillatory behavior is analyzed as well as the effects brought on the threshold of instability by changes in the operating system pressure,inlet subcooling number and mass flow.Moreover,this experimental data was compared with that inform the two parallel rectangular channels by using dimensionless subcooling number Nsub and phase change number Npch.The comparison indicates that the existence of by-pass makes the system more stable.
分 类 号:TL33[核科学技术—核技术及应用]
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