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Investigation on two-phase flow instability in steam generator of integrated nuclear reactor
引用本文:荆建刚,陈听宽. Investigation on two-phase flow instability in steam generator of integrated nuclear reactor[J]. 核技术(英文版), 1996, 7(2): 73-80
作者姓名:荆建刚  陈听宽
作者单位:Xi'an Jiaotong University,Xi'an 710049
摘    要:In the pressure range of 3-18MPa,high pressure steam-water two-phase flow density wave instability in vertical upward parallel pipes with inner diameter of 12mm is studied experimentally.The oscillation curves of two-phase flow instability and the effects of several parameters on the oscillation threshold of the system are obtained.Based on the small pertubation linearization method and the stability principles of automatic control system,a mathematical model is developed to predict the characteristics of density wave instability threshold.The predictions of the model are in good agreement with the experimental results.

关 键 词:二相流 核反应堆 蒸汽发生器

Investigation on two-phase flow instability in steam generator of integrated nuclear reactor
Jing Jian-Gangand Chen Ting-Kuan. Investigation on two-phase flow instability in steam generator of integrated nuclear reactor[J]. , 1996, 7(2): 73-80
Authors:Jing Jian-Gangand Chen Ting-Kuan
Abstract:
Keywords:Integrated nuclear reactor   Steam generator   Two phase instability   Density wave oscillation
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