Abstract
An experimental programme has been carried out to investigate parallel-channel instability in a full-scale simulated nuclear reactor channel operating in vertical high-pressure boiling-water upflow. Experimental data have been obtained using a vertically mounted test section containing two 19-rod electrically heated bundles with a total heated length of 195 in. The test section was operated in parallel with an unheated by-pass between common inlet and outlet headers. The characteristics of the observed test-section and by-pass flow oscillations are described in detail. Data are presented showing the effect upon test section flow stability of bundle electrical power, inlet subcooling, operating pressure, feeder pressure loss coefficients and the ratio of by-pass flow-rate to test-section flow-rate.
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