One of the main accidents is steam generator tube rupture (SGTR), in the field of nuclear safety.
The main function of the Steam Generator Pressure Control (SGPC) Program is to match the power (heat) generation in the reactor core with the heat removal in the steam generators (SGs).
The main part placed in the steam generator is the robot vehicle.
It is intended to analyze and calculate physical processes of the reactor core, the main loop system and the steam generator, etc., as well as to simulate the normal operational and transient accidents.
The designed control algorithm is applied to fixed-time stabilization of two mechatronic systems, a cart inverted pendulum and a single machine infinite bus turbo generator with main steam valve control.
The hot GT flue gases are sent to Heat Recovery Steam Generator (HRSG) for steam generation.
These models mainly include the core, once-through steam generator, nitrogen pressurizer, main coolant pump, and flow and heat transfer models.
These models mainly include the core, once-through steam generator, nitrogen pressurizer, main coolant pump, flow and heat transfer and ocean motion models.
The pinch point temperature difference in the evaporator is used as the main variable as it changes the steam generator design and the operating conditions of the plant, such as the inlet temperature of the receiver and the salt mass flow.
Numerous fretting damages exist at various parts of nuclear power systems [7], such as reactor fuel assembly, control rod assembly [8], reactor component, steam generator, pressure vessel [9], main pump, and coolant pump.
