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Control method of nuclear power steam generator

A technology of steam generator and control method, applied in general control system, electrical testing/monitoring, control/regulation system, etc., can solve the problems of expensive equipment, control deviation, unstable controlled variable of steam generator, etc. Model and test the effects of noise

Inactive Publication Date: 2015-12-09
黄红林
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AI Technical Summary

Problems solved by technology

[0003] The stability of the controlled variable of the steam generator is of great significance to the safe operation of the nuclear power plant. When the sensor in the steam generator fails, it will affect the control signal, resulting in instability of the controlled variable of the steam generator, control deviation, and even series of security issues
[0004] At present, nuclear power plants mainly use hardware redundancy to prevent sensor failure; due to the expensive equipment of nuclear power plants, this hardware redundancy method greatly increases the equipment cost and space of nuclear power plants

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  • Control method of nuclear power steam generator
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  • Control method of nuclear power steam generator

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Embodiment Construction

[0021] refer to Figure 1 ~ Figure 3 , the specific steps of the present invention include:

[0022] Step 1. Establish a steam generator model according to the principle of thermal hydrodynamics. The opening of the water supply valve and the opening of the steam outlet valve are used as operating variables, and the water level in the water supply chamber, the flow rate of the feed water, and the flow rate of the steam outlet are used as controlled variables;

[0023] Step 2, for different controlled variables, obtain measured values ​​through various sensors;

[0024] Step 3. Using the Unscented Kalman Filter (UKF) method, each UKF monitors a sensor, and takes the remaining sensor measurement value subset after removing the monitored sensor as input to obtain the state estimation value and residual error, specifically , which is UKF1 used to monitor the feed water pressure sensor. Its input value Y1 does not include the output signal of the temperature sensor, but only the ou...

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Abstract

The invention discloses a control method of a nuclear power steam generator. The control method comprises the steps of (a) mechanism modeling in which a high-temperature gas-cooled-reactor steam generator model is established according to thermotechnical waterpower principle; (b) data collection; (c) state estimation; (d) fault diagnosis and reconstruction; and (e) control according to reconstructed values. Tolerance control design is carried out on the steam generator based on a traceless Kalman filter; and on the basis of a lumped parameter model, tolerance control with stable water level and flow of the steam generator is achieved by detecting and separating sensor faults in real time and reconstructing output values of the sensor. Even if detection faults occur in the sensor, the control effect is good, the cost of hardware redundancy is reduced, tracking control for a multivariable nonlinear system can be realized, the possibility of nuclear power safety accidents caused by detection faults is effectively reduced, the safety level is high, the control effect is good, and computers are easy to control.

Description

【Technical field】 [0001] The invention relates to the field of high-temperature gas-cooled reactor nuclear power plant steam generators, in particular to the technical field of a nuclear power steam generator control method combined with unscented Kalman filtering and fault-tolerant control. 【Background technique】 [0002] The steam generator is the power component of the high-temperature gas-cooled reactor nuclear power plant. It is one of the three major equipments in the nuclear island. It is the boundary of the primary and secondary circuits of the pressurized water reactor nuclear power plant. It transfers the heat generated by the reactor to the steam generation On the secondary side of the device, the steam generated is dried by the primary and secondary steam-water separators to drive the turbogenerator to generate electricity. The coolant flowing out of the reactor enters the water chamber from the inlet of the lower head of the steam generator through the heat pipe...

Claims

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Application Information

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IPC IPC(8): G05B23/02
CPCG05B23/0218
Inventor 杨海霞黄红林
Owner 黄红林
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