Verification of SOPHT for Parallel Channel Flow Stability

Abstract

As part of a continuing program to verify the thermalhydraulic computer code SOPHT, a number of experimental tests designed to study parallel channel flow instability were simulated. This phenomenon of flow instability could cause dryout of reactor fuel resulting in poor heat transfer to the coolant and increased fuel temperatures. Selected tests from two out reactor experimental programs are predicted with the SOPHT code. Both of these test programs were carried out at Westinghouse Canada Incorporated, Hamilton, Ontario, under contract to Atomic Energy of Canada. The first test facility consisted of a vertical heated channel in parallel with an unheated bypass connected between a common inlet and outlet header. The second test facility was similar to the first, however there were three parallel heated channels as well as an unheated bypass.SOPHT predictions of the power required to initiate flow instability and flow oscillation frequency are in good agreement with the experimental data.