Investigation on two-phase flow instability in steam generator of integrated nuclear reactor

Jing Jian-Gang，

Chen Ting-Kuan

Nuclear Science and Techniques

pp.73-80

Published in print 01 May 1996

20200

In the pressure range of 3〜18 MPa, high pressure steam-water two-phase flow density wave instability in vertical upward parallel pipes with inner diameter of 12 mm 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 perturbation 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.

Integrated nuclear reactorSteam generatorTwo phase instabilityDensity wave oscillation

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