Research Of Parameter Correction For Power Control In Reactor Based On Thermal Balance Theory

Economic and safety of nuclear power plants is always a question that people areconcerned about. With the development of information technology, nuclear power plantcontrol adapted from the original analog instruments into digital computer control, which ismainly embodied by the application of DCS (distributed control system). Introduction ofDCS system facilitated the correction of control parameters in plant enormously. Nuclearpower plant control system is a multi-interface, multi-variable complex system, thereforehow to realize the power homeostasis of primary and secondary loop under various operatingmodes on the premises of safety, and how to ensure bump-less control system under variousmodes is becoming a hot study topic. Based on the features and correlation of process andequipment in nuclear power plant, the thesis master the control characteristic of the reactor,establish the control object model by theory study and experiment statistics, so as to study theG Model control strategy of power and temperature control system in nuclear power plantand propose the relevant functions to correct power and temperature control according to thecalculation result of heat balance principle. PWR nuclear power calculation formulasincluding: steam generator outlet steam enthalpy, enthalpy of water supply, enthalpy of blowdown steam as well as feed water flow is deprived according to the heat balance principleand process control requirements of PWR. On the basis of results from the thermal powerbalance test platform, the reactor control functions are corrected by linear load changes, theresults indicate that the parameters correction in thermal balance test ensure G core rod canbe inserted into the proper position under various operating modes, and to ensure that R rodsin regulation zone.The amplitude fluctuation of G rods and steam turbine bypass system (GCT-A) didappear in the process of parameter correction in this case. Perturbed test and parameteroptimization are conducted on GCT-A PID, and then perform calculation and study on thisparameter in transient condition by usage of nuclear power plant transient analysis as well asCATIA2(control system correction design program) to justify the rationality of theparameters. In addition, the root cause has been analyzed and identified after the valve testwith flow scanner combined with the historical data of control instructions. The solution hasbeen proposed as well. Aiming at G rods fluctuations, root cause analysis and methodsverification have been carried out as well. The results show that solution on these problemsgreatly improves the reliability and safety of nuclear power plant control system.