Dynamics of once-through steam generator control for a nuclear power plant with a gas cooled reactor

Studied is the mathematical model of once-through steam generator for power plant with high-temperature gas cooled reactor. The objective of the work is: determination of dynamic performances of the plant, investigation of the primary and secondary circuit interconnections, choice of rational structure for the plant automatic control systems. The analogue computers are used for realization of the mathematical model. The block diagram of the above model and the plant control system schemes both for uncontrolled and controlled load are presented. The studies have shown that steam generators for high-temperature gas cooled plants possess low time lag. There is the interconnection between the coolant parameters for the primary and secondary circuits and so small variations in the plant regime give rise to considerable and quick deviations in vapor parameters. Such peculiarities of steam generators require an application of quick-operating control system. Investigations of control circuits showed that if at small load variations (up to 20 %) permissible fluctuations of cold gas temperature constitute 30 deg C, the operation of the plant with uncontrolled temperature of cold gas is possible