CN-116759124-B - Nuclear power plant reactor power control system input signal correction method

CN116759124BCN 116759124 BCN116759124 BCN 116759124BCN-116759124-B

Abstract

The invention belongs to the technical field of nuclear power plant instrument control systems, and particularly relates to a method for correcting an input signal of a nuclear power plant reactor power control system. The method comprises the following steps of S1, collecting N S from a nuclear instrument system and N core from a reactor core measuring system by a reactor power control system, S2, comparing a neutron fluence rate signal N core in a real-time reactor core with a nuclear power measuring signal N S in an adder to obtain a power deviation initial signal N E1 , S3, entering a power deviation logic processor to perform logic processing on the power deviation initial signal N E1 , outputting N E2 , S4, selecting a correction mode in a nuclear power correction selector according to running conditions and regulations, outputting N E , and S5, calculating a nuclear power measuring value signal N S and a nuclear power correction signal N E in the adder to obtain a nuclear power signal N C for control. The invention can more accurately reflect the real condition of the reactor core power, and the corrected nuclear power signal is used for a reactor power control system, thereby improving the safety and the economical efficiency of the operation of a power plant.

Inventors

ZHANG YING
XIAO KAI
ZHAO MENGWEI
CHEN KE
DUAN FENG
ZHENG YANQIU
CHEN ZHI
WANG HUAJIN
CUI HUAIMING
LI WENPING
QING XIANGUO
ZHANG RUI
LI YILIANG
YOU KAI

Assignees

中国核动力研究设计院

Dates

Publication Date: 20260512
Application Date: 20230511

Claims (5)

1. The method for correcting the input signal of the reactor power control system of the nuclear power plant is characterized by comprising the following steps of: s1, a reactor power control system collects a nuclear power measurement signal from a nuclear instrument system Real-time core neutron fluence rate signal from core measurement system ; S2, the real-time reactor core neutron fluence rate signal And nuclear power measurement signal Comparing in adder to obtain initial power deviation signal The power deviation initial signal , ; S3, the power deviation initial signal The power deviation logic processor is entered to perform logic processing and output The power deviation initial signal Through a dead zone function F (x) which sets the dead zone value to E, the power deviation signal When the absolute value of (2) is greater than E, the method enters a proportional coefficient K link to operate and then outputs Otherwise, outputting to be 0; s4, selecting a correction mode in the nuclear power correction selector according to the running condition and the rules, and outputting ; Judging whether the reactor core power is stable or not, and selecting by a reactor core power correction mode when the reactor core power is unstable Control the core power correction selector to select no correction, the core power correction selector output =0; When the reactor core power is stable, the input signal of the reactor power control system of the nuclear power plant is corrected, The input signal of the reactor power control system of the nuclear power plant is modified, and the method comprises two modes: When the auto-correction mode is selected, the core power correction selector outputs = ; When the manual correction mode is selected, the core power correction selector outputs = ; S5, nuclear power measurement signal And a core power correction signal The control core power signal is obtained by calculation in an adder 。
2. The method of claim 1, wherein the dead zone value E = 2% fp.
3. The method according to claim 2, wherein the scaling factor K is selected from the group consisting of the nuclear power measurement signal Entering a power deviation logic processor, wherein K takes different values according to the high and low power ranges of the nuclear power plant, At >30% fp, k=0; at less than or equal to 30% fp, k=1.05.
4. A method according to claim 3, wherein the scaling factor K is selected from the group consisting of 。
5. The method of claim 4, wherein the The determination method is that according to the nuclear power measuring signal from the nuclear instrument system Real-time core neutron fluence rate signal from core measurement system And the actual running state of the power plant by manually inputting the correction value 。

Description

Nuclear power plant reactor power control system input signal correction method Technical Field The invention belongs to the technical field of nuclear power plant instrument control systems, and particularly relates to a method for correcting an input signal of a nuclear power plant reactor power control system. Background In the prior art, key parameters of a self-powered neutron detector of a system for measuring the neutron fluence rate of a reactor core in China are researched and analyzed by key parameters of the nuclear and electrical properties of the self-powered neutron detector (SPND) selected by a Hua-Dran-I reactor core neutron fluence rate measuring instrument, a design scheme of the SPND is provided, problems in practical application of the system for measuring the reactor core neutron fluence rate are analyzed, relations among the neutron fluence rate detector, driving equipment and selection equipment of the neutron fluence rate detector are analyzed by blocking the neutron fluence rate detector and unavailable channels, so that a solution for defects of the neutron fluence rate detector and related equipment is obtained, a reactor core instrument system of a nuclear power plant is used for measuring the three-dimensional neutron fluence rate of the reactor core in real time on line by adopting an equal difference neutron self-powered detector, and the system has stronger calculation and graphic display capacity by adopting digital processing and display equipment, and thus measured data are processed in real time and three-dimensional power distribution map of the reactor core is generated on line. The practical application problem analysis of the neutron fluence rate measurement system of the reactor core in China is that the document is a solution for the defects of the neutron fluence rate detector and related equipment, which is provided for ensuring the reliability of the neutron fluence rate measurement equipment, by considering that the neutron fluence rate of the reactor core has important significance for researching the distribution and the size of the axial power of the reactor core and calibrating each item of data of the reactor core, that is, the document focuses on improving the reliability of the core neutron fluence rate measurement system, i.e., improving the availability of neutron fluence rate signals to some extent, by addressing the drawbacks of the detectors and associated processing equipment itself. The utility model provides a nuclear power plant reactor core instrument system, this system can measure the three-dimensional neutron fluence rate of reactor core on line in real time to real-time processing the data that measure and online generation reactor core three-dimensional power distribution map, this document is through adopting new measuring method and adopting digital processing and display device, makes the three-dimensional neutron fluence rate of reactor core can be measured and handled in real time. None of the above documents, however, mention the use of neutron fluence rate signals for correction of nuclear power signals of a reactor power control system. The reactor core neutron fluence rate signal from the reactor core measuring system can more accurately reflect the actual condition of the reactor core power, so that the reactor core power signal is corrected by using the signal, thereby more accurately reflecting the actual condition of the reactor core power. However, because the signals in the reactor have certain time delay, the compensation power is accurate only at the moment when the reactor core power is relatively stable, and once the power fluctuation condition is large, the correction power cannot accurately reflect the instant fluctuation condition, so that the hysteresis exists. Therefore, whether the nuclear power signal is corrected or not and what way the nuclear power signal is corrected can be considered according to the actual operation condition of the power plant. The reactor power control system is an important control system for the safety of the nuclear power plant, and the performance of the reactor power control system is directly related to whether the nuclear power plant can safely and economically operate. The basic function of the reactor power control system is to adjust the reactor power to match the turbine load, so the nuclear power signal is an important input signal in the reactor power control system. Disclosure of Invention The technical problem solved by the invention is to provide a method for correcting an input signal of a reactor power control system of a nuclear power plant, which corrects a nuclear power signal of a nuclear instrument system by introducing a core neutron fluence rate signal of a core measurement system so as to more accurately reflect the actual condition of the core power, wherein the corrected nuclear power signal is used for the reactor power control system, and the safety and the eco