Velocity-temperature correlation in strongly heated channel flow

1995 ◽  
Vol 18 (6) ◽  
pp. 454-461 ◽  
Author(s):  
I. N. G. Wardana ◽  
T. Ueda ◽  
M. Mizomoto
2011 ◽  
Vol 333 ◽  
pp. 012014 ◽  
Author(s):  
Jacek Pozorski ◽  
Maria Knorps ◽  
Mirosław Łuniewski

Author(s):  
J. Pozorski ◽  
M. Wacławczyk ◽  
J.P. Minier
Keyword(s):  

Author(s):  
M. B. Carver

Experiments on parallel-channel hydrodynamic stability frequently use one heated channel operating in parallel with an unheated by-pass. This arrangement is designed to simulate the operation of a particular channel in a boiling water reactor; the by-pass providing the essentially constant pressure drop which the remaining channels impose on the channel in question. If the ratio of by-pass flow to channel flow is large the changes in channel flow do not significantly affect the overall pressure drop; however, particularly in experiments using full-scale reactor fuel channels, loop capacity may limit this by-pass ratio. In this case the pressure drop is no longer constant. This paper shows, analytically, that a low by-pass ratio, resulting in a variable overall pressure drop, significantly affects the dynamic behaviour of the heated channel. Both the power at threshold of flow oscillation and the natural frequency of the system are shown to depend on by-pass characteristics. In particular, a heated channel operating with a low by-pass ratio is normally stable to much higher powers than it is with a high by-pass ratio. A linearized analysis is presented which illustrates the effect of by-pass resistance and inertia on the threshold power and natural frequency of flow oscillations. The analysis is incorporated in a computer code, and resulting threshold powers and oscillation frequencies are compared to data from experiments using a full-scale simulated reactor channel in parallel with a by-pass. It is concluded that the finite unheated by-pass does not accurately simulate the dynamic effect of the remaining reactor channels on a particular channel. However, the methods of this paper should prove useful in interpreting results from a flow-limited test loop and extrapolating to the full reactor case.


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