Thermohydraulic characteristics of the BN-600 reactor at the Beloyarsk nuclear power station

During the period of startup and adjustment of the BN-600 reactor, when its rated power was reached, the hydraulic characteristic of the primary circuit was determined by measuring the flow rate of the sodium coolant through the fuel assemblies and the control-rod assemblies. A flow-measuring device was used, consisting of a built-in magnetic flowmeter with a calibration characteristic obtained on a sodium test stand. Processing of the measurement data indicated that the hydraulic characteristic of the primary circuit and the distribution of coolant flow rate over the throttling zones are in good agreement with the design data. Repeatability of the results is observed for flow-rate measurements through the fuel assemblies in the same cells during different microperiods of operation