control method

The PHV-1000 steam generator is one of the main heat exchangers in the primary circuit of the power unit of nuclear power plants with a WWER-1000 reactor. The efficiency of its operation directly affects the thermal power and overall electricity generation of the power unit. The reliability of the heat exchange tubes forming the main heat exchange area is critical not only for thermal performance but also for the safety characteristics of the steam generator.

The synthesis of the structure of the automatic control system of direct current motors is carried out, and the methodology of the study of the duration of the transient process during the control of the direct current motor is presented. A study of the influence of the regulator parameters on the duration of the transition process was carried out, which allowed to choose the optimal ones for the criterion of the minimum duration of the transition process