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Chen, Y.S.; Fischer, S.R.; Sullivan, L.H.
Idaho National Engineering Lab., Idaho Falls (USA)1979
Idaho National Engineering Lab., Idaho Falls (USA)1979
AbstractAbstract
[en] RELAP4/MOD6 is an analytical computer code which can be used for best-estimate analysis of LWR reactor system blowdown and reflood response to a postulated LOCA. In this study, flow oscillations in the PKL reflood test K5A were investigated using RELAP4/MOD6. Both calculated and measured oscillations exhibited transient characteristics of density-wave and pressure-drop oscillations. The calculated average core mixture level rising rate agrees closely with the test data. Several mechanisms which appear to be responsible for initiation and continuation of calculated or experimental reflood flow oscillations are (a) the coupling between the vapor generation in the core channel and the U-tube geometrical arrangement of a downcomer and a heated core; (b) the inherent low core inlet resistance and the high system outlet resistance; (c) the dependence of heat transfer rate on mass flow rate especially in the dispersed flow ially in the dispersed flow regime; (d) the amount of the liquid entrainment fraction of the heated core channel
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1979; 18 p; 2. multiphase flow and heat transfer symposium workshop; Miami Beach, FL, USA; 16 - 18 Apr 1979; Available from NTIS., PC A02/MF A01
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Conference
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