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Model parameter acquisition method for primary loop system of pressurized water reactor

A loop system and model parameter technology, which is applied in general control systems, control/regulation systems, instruments, etc., can solve the problem of high requirements for input and output signals and models to be identified, unsatisfactory identification effects of nonlinear systems, and poor identification effects. Noise impact and other issues, to achieve clear physical meaning, fast parameter acquisition method, simple and effective test data

Active Publication Date: 2017-05-31
CHINA ELECTRIC POWER RES INST +3
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Problems solved by technology

Common model parameter identification methods include least squares identification, Kalman filter identification, Volterra series identification, etc. These identification methods have high requirements on input and output signals and the model to be identified, and the identification effect on some nonlinear systems is not ideal
The current identification method for nuclear power plant model parameters has high requirements for initial values, and the identification effect is affected by noise

Method used

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  • Model parameter acquisition method for primary loop system of pressurized water reactor
  • Model parameter acquisition method for primary loop system of pressurized water reactor
  • Model parameter acquisition method for primary loop system of pressurized water reactor

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Embodiment Construction

[0033] The present invention will be further specifically described below through the embodiments and in conjunction with the accompanying drawings. Figure 1~3 Among them, SG stands for steam generator; f 1 is the plant power bus frequency; U 1 is the plant power bus voltage; D sp is the coolant main pump flow rate; N r is the neutron flux density; T avg is the measured value of the average temperature of the primary circuit; T cav is the average temperature of the reactor coolant; T F is the core fuel temperature; T c1 and T c2 are the inlet and outlet temperatures of the core coolant, respectively; T HL and T CL are the inlet and outlet temperatures of the primary circuit coolant of the steam generator; h s is the specific enthalpy of steam at the outlet of the secondary circuit of the steam generator; G s is the steam generator flow rate; P s Main vapor pressure; ρ ext Reactivity introduced for the control rods; ρ T is the reactivity caused by the temperature ...

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Abstract

The invention relates to a parameter acquisition method for a primary loop system of a pressurized water reactor. The model parameter acquisition method comprises the steps of combining the characteristic that the pressurized water reactor is complicated in model structure, provided with nonlinear links, long in stable transition time, great in number of model parameters and variables, mutual coupling and the like, recognizing model parameters by adopting submodules, and checking the parameters by adopting an overall model; selecting input and output variables of each module to perform testing; reducing influences imposed on a recognition effect by noise signals through preprocessing; initializing the variables based on a differential equation of each module and a program setting method, and enabling the model to be stable in initialization; recognizing parameters of each module based on a parameter perturbation theory and an intelligent optimization method; checking the parameters and the model under various conditions by combining the submodules and the overall module; and acquiring nuclear power unit system mathematic model parameters applicable to electric power system analysis. The modules are fine and clear in structure, the model parameters are definite in meaning, the variables required by recognition are easy to acquire, the parameter acquisition method is quick, efficient and accurate, and the practicability is high.

Description

technical field [0001] The invention relates to the technical field of modeling of nuclear power units, in particular to a method for acquiring model parameters for the primary circuit system of a pressurized water reactor. Background technique [0002] Nuclear power has the characteristics of large single-unit capacity, high nuclear safety requirements, sensitivity to power grid disturbances, and long start-up and shutdown refueling times. At present, in the analysis of large-scale power systems, the established models are mainly aimed at second-generation half-sized nuclear power units. Under the background of the great development of the third-generation nuclear power, there is a lack of accurate and applicable simulation models of the third-generation pressurized water reactor units, and the parameters of the reactor and the primary circuit system are still difficult to obtain through actual measurement. Accurate parameters of the primary circuit model of the nuclear pow...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G05B13/04
CPCG05B13/042
Inventor 刘涤尘吴国旸宋新立赵洁王力叶小晖刘涛赵语苏志达仲悟之刘庆
Owner CHINA ELECTRIC POWER RES INST
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