Abstract
As key equipment in nuclear power plant, the reactor power control system is adopted to strictly control and regulate the reactor power of a PWR (pressurized water reactor) in a nuclear power plant. A well-optimized predictive control algorithm based on SDMC (stepped dynamic matrix controller) is developed and introduced in this paper and applied to the power regulation of a reactor power model. In addition, the test and verification of this application is conducted by two different methods and devices: the virtual verification platform and the physical DCS (digital control system). The result of the verification suggests that the application of SDMC gains a better performance in the maximum dynamic deviation, adjustment time, overshoot, and so on.
Highlights
In the load tracking operation mode of a PWR nuclear power plant, the reactor power needs to be dynamically adjusted to track the load demand. e reactor power is highly correlated with the neutron flux in the reactor core. e material of control rod has a large neutron absorption cross section, which means that the control rod has a strong neutron absorption capacity. e proportion of neutrons absorbed by the control rod depends on the depth of the control rod inserted into the core
In a PWR nuclear power plant, the reactor power is controlled by the reactor power control system and the average coolant temperature control system, in which the former one is the main research object in this paper. e function of reactor power control system is to acquire and process related process signals of process system of plant, the state parameter signals of field devices, and the operational command signals from operators. en, the operation and calculation of logical calculation is conducted in the reactor power control system, from which the output command drives the control rods to regulate the reactor power
If the prerequisites of automatic mode are met, the reactor power control system is operating in automatic mode; otherwise, it is running in manual mode
Summary
In the load tracking operation mode of a PWR (pressurized water reactor) nuclear power plant, the reactor power needs to be dynamically adjusted to track the load demand. e reactor power is highly correlated with the neutron flux in the reactor core. e material of control rod has a large neutron absorption cross section, which means that the control rod has a strong neutron absorption capacity. e proportion of neutrons absorbed by the control rod depends on the depth of the control rod inserted into the core. In the load tracking operation mode of a PWR (pressurized water reactor) nuclear power plant, the reactor power needs to be dynamically adjusted to track the load demand. Erefore, by changing the insertion depth of the control rods, the neutron flux can be adjusted and regulated, and so the reactor power can be controlled. In a PWR nuclear power plant, the reactor power is controlled by the reactor power control system and the average coolant temperature control system, in which the former one is the main research object in this paper. En, the operation and calculation of logical calculation is conducted in the reactor power control system, from which the output command drives the control rods to regulate the reactor power. Input signals (reactor power, temperature of reactor input coolant, temperature of reactor output coolant, etc.)
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