EP-4742273-A1 - REACTOR POWER CONTROL METHOD AND APPARATUS, COMPUTER DEVICE AND READABLE STORAGE MEDIUM

EP4742273A1EP 4742273 A1EP4742273 A1EP 4742273A1EP-4742273-A1

Abstract

The present application relates to a reactor power control method and apparatus, a computer device and a readable storage medium. The method comprises: acquiring an initial load signal sent by a power grid; preprocessing the initial load signal to obtain an actual load signal; acquiring first feedforward information on the basis of the actual load signal and a preset load-rod position model; acquiring second feedforward information on the basis of the initial load signal, the actual load signal and a preset deviation intensity adjustment model; acquiring third feedforward information on the basis of the actual load signal and a preset amplitude limiting model; and generating a power control signal on the basis of the first feedforward information, the second feedforward information, the third feedforward information and an actual rod position value of a control rod of a reactor.

Inventors

ZHANG, RONGBIN
ZHOU, WENJUN
HE, XIAOMING
GUO, Yongfei
XIONG, GUOHUA
LI, TAO
LI, Guomin
LANG, Yukai
SHI, BO
DU, YANGYANG
LIN, Wenzhao

Assignees

China Nuclear Power Technology Research Institute Co., Ltd.
China General Nuclear Power Corporation
CGN Power Co., Ltd.

Dates

Publication Date: 20260513
Application Date: 20240625

Claims (10)

A reactor power control method, comprising: obtaining an initial load signal sent by a power grid; preprocessing the initial load signal to obtain an actual load signal; obtaining first feedforward information based on the actual load signal and a preset load-rod position model; obtaining second feedforward information based on the initial load signal, the actual load signal and a preset deviation intensity adjustment model; obtaining third feedforward information based on the actual load signal and a preset amplitude limit model; and generating a power control signal based on the first feedforward information, the second feedforward information, the third feedforward information, and an actual rod position value of a control rod of a reactor.
The method according to claim 1, wherein generating the power control signal based on the first feedforward information, the second feedforward information, the third feedforward information, and the actual rod position value of the control rod of the reactor comprises: calculating a rod position setting value of the control rod of the reactor based on the first feedforward information, the second feedforward information and the third feedforward information; and generating the power control signal based on the rod position setting value, the actual rod position value and a preset rod speed model.
The method according to claim 2, wherein generating the power control signal based on the rod position setting value, the actual rod position value and the preset rod speed model comprises: calculating rod position deviation information based on the rod position setting value and the actual rod position value; and processing the rod position deviation information based on the preset rod speed model to obtain the power control signal.
The method according to claim 1, wherein preprocessing the initial load signal to obtain the actual load signal comprises: performing a rate limiting processing on the initial load signal based on a preset load changing rate to obtain the actual load signal.
The method according to any one of claims 1 to 4, wherein obtaining the first feedforward information based on the actual load signal and the preset load-rod position model comprises: inputting the actual load signal to the preset load-rod position model; and obtaining the first feedforward information corresponding to the actual load signal via a match in the preset load-rod position model.
The method according to any one of claims 1 to 4, wherein the preset deviation intensity adjustment model comprises a first sub-model and a second sub-model, and obtaining the second feedforward information based on the initial load signal, the actual load signal and the preset deviation intensity adjustment model comprises: calculating reference load deviation information based on the initial load signal and the actual load signal; processing the reference load deviation information based on the first sub-model to obtain reference rod position feedforward information, wherein the reference rod position feedforward information is a rod position adjustment value, and the rod position adjustment value is obtained by adjusting the reference load deviation information according to a preset deviation intensity range; and performing a preset inertia processing on the reference rod position feedforward information based on the second sub-model to obtain the second feedforward information.
The method according to any one of claims 1 to 4, wherein obtaining the third feedforward information based on the actual load signal and the preset amplitude limit model comprises: performing a differential calculation on the actual load signal to obtain a change rate of the actual load signal; and limiting an amplitude of the change rate based on the preset amplitude limit model to obtain the third feedforward information.
A reactor power control apparatus, comprising: an initial signal obtaining module configured to obtain an initial load signal sent by a power grid; an actual signal obtaining module configured to preprocess the initial load signal to obtain an actual load signal; a first feedforward calculation module configured to obtain first feedforward information based on the actual load signal and a preset load-rod position model; a second feedforward calculation module configured to obtain second feedforward information based on the initial load signal, the actual load signal and a preset deviation intensity adjustment model; a third feedforward calculation module configured to obtain third feedforward information according to the actual load signal and a preset amplitude limit model; and a control signal generation module configured to generate a power control signal according to the first feedforward information, the second feedforward information, the third feedforward information, and an actual rod position value of a control rod of a reactor.
A computer device, comprising a memory and a processor, wherein the memory has a computer program stored thereon, and the processor, when executing the computer program, performs steps of the reactor power control method according to any one of claims 1 to 7.
A computer readable storage medium, having a computer program stored thereon, wherein the computer program, when executed by a processor, performs steps of the reactor power control method according to any one of claims 1 to 7.

Description

CROSS-REFERENCE TO RELATED APPLICATION The present application claims priority to Chinese patent application No. 2023108178798, entitled "Reactor power control method and apparatus, computer device and readable storage medium", filed on July 5, 2023, the disclosure of which is hereby incorporated by reference in its entirety. TECHNICAL FIELD The present application relates to the field of nuclear power technology, and in particular to a reactor power control method, a reactor power control apparatus, a computer device and a readable storage medium. BACKGROUND With the continuous optimization and adjustment of energy structure, it has become an inevitable trend for nuclear power units to participate in grid frequency regulation and peak shaving, which puts forward higher requirements for the control ability of an automatic generation control (AGC) of a nuclear power unit. The operational effectiveness of the AGC function relies entirely on the regulation performance of a coordinated control system of a nuclear power unit. For the nuclear power unit, it is required to be able to quickly respond to a power command, and quickly stabilize system parameters of the nuclear power unit after the power command changes, so as to meet the requirements of frequent power changes of the nuclear power unit. At present, "reactor follow unit" operation mode, which is also called Mode-G, is generally adopted for the operation of pressurized water reactor (PWR) nuclear power unit. In such a mode, the turbine receives a load instruction signal and automatically adjusts the steam intake to change the turbine power, and the reactor changes the nuclear power according to the load change of the turbine. That is to say, under the normal operating condition of the nuclear power unit, the power setting value signal required for reactor power control is generated according to a load reference value of the steam turbine itself. When the load reference value increases, the power setting value also increases proportionally. In this mode, although the turbine can quickly respond to a command change of an external power grid, the reactor is prone to cause load mismatch of various circuits since the reactor follows the turbine load passively, which aggravates the fluctuation of main steam pressure and may trigger the action of the reactor protection system if the fluctuation is serious. SUMMARY According to various embodiments of the present application, a reactor power control method, a reactor power control apparatus, a computer device and a readable storage medium are provided. In a first aspect, the present application provides a reactor power control method including: obtaining an initial load signal sent by a power grid;preprocessing the initial load signal to obtain an actual load signal;obtaining first feedforward information based on the actual load signal and a preset load-rod position model;obtaining second feedforward information based on the initial load signal, the actual load signal and a preset deviation intensity adjustment model;obtaining third feedforward information based on the actual load signal and a preset amplitude limit model; andgenerating a power control signal based on the first feedforward information, the second feedforward information, the third feedforward information, and an actual rod position value of a control rod of a reactor. In an embodiment, generating the power control signal based on the first feedforward information, the second feedforward information, the third feedforward information, and the actual rod position value of the control rod of the reactor includes: calculating a rod position setting value of the control rod of the reactor based on the first feedforward information, the second feedforward information and the third feedforward information; andgenerating the power control signal based on the rod position setting value, the actual rod position value and a preset rod speed model. In an embodiment, generating the power control signal based on the rod position setting value, the actual rod position value and the preset rod speed model includes: calculating rod position deviation information based on the rod position setting value and the actual rod position value; andprocessing the rod position deviation information based on the preset rod speed model to obtain the power control signal. In an embodiment, preprocessing the initial load signal to obtain the actual load signal includes: performing a rate limiting processing on the initial load signal based on a preset load changing rate to obtain the actual load signal. In an embodiment, obtaining the first feedforward information based on the actual load signal and the preset load-rod position model includes: inputting the actual load signal to the preset load-rod position model; andobtaining the first feedforward information corresponding to the actual load signal via a match in the preset load-rod position model. In an embodiment, the prese