CN113871037A - Reactor operation control method, reactor operation control device, computer equipment and storage medium - Google Patents

Reactor operation control method, reactor operation control device, computer equipment and storage medium Download PDF

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Publication number
CN113871037A
CN113871037A CN202111075449.0A CN202111075449A CN113871037A CN 113871037 A CN113871037 A CN 113871037A CN 202111075449 A CN202111075449 A CN 202111075449A CN 113871037 A CN113871037 A CN 113871037A
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China
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pipe section
heat pipe
temperature
section temperature
reactor
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Inventor
张薇
李炳文
卫丹靖
朱建敏
王凯
周洺稼
王炜如
王晓婷
刘亦然
陈天铭
王娜
胡友森
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China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
CGN Power Co Ltd
China Nuclear Power Institute Co Ltd
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China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
CGN Power Co Ltd
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Priority to CN202111075449.0A priority Critical patent/CN113871037A/en
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24—Promoting flow of the coolant
    • G21C15/257—Promoting flow of the coolant using heat-pipes
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/112—Measuring temperature
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The application relates to an operation control method and device of a reactor, computer equipment and a storage medium. The method comprises the following steps: acquiring the original heat pipe section temperature during the operation of a nuclear power plant; filtering the high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature; the signal frequency of the high-frequency small-amplitude disturbance part is greater than a preset frequency threshold value, and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than a preset amplitude threshold value; controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, and determining the reactor thermal power when the nuclear power plant operates according to the target heat pipe section temperature. By adopting the method, two problems of frequent control rod movement and thermal power fluctuation in the steady-state operation of the nuclear power plant can be solved simultaneously, and the algorithm and the control process are simple.

Description

Reactor operation control method, reactor operation control device, computer equipment and storage medium
Technical Field
The present application relates to the field of nuclear power plant control technologies, and in particular, to a method and an apparatus for controlling reactor operation, a computer device, and a storage medium.
Background
In recent years, in the steady-state operation process of a nuclear power unit, due to the steady-state fluctuation of state parameters, the problems of frequent control rod actions, remarkable fluctuation of reactor thermal power and the like are caused. The control rod action times of some units are up to hundreds of times per day, which greatly increases the abrasion of the control rod driving mechanism and shortens the service life of the control rod driving mechanism; when the thermal power of the reactor generates instantaneous fluctuation, the power of the unit must be adjusted by professional technicians, and if the fluctuation frequency of the thermal power is high, the control of the normal operation of the unit by operators is interfered.
In the prior art, aiming at the problem of frequent control rod actions, a parameter transformation method of a control rod control system is mainly adopted, namely a first-order filtering time constant and a lead-lag time constant in a control channel are modified. For the problem of large fluctuation amplitude of thermal power, the prior art mainly adopts a method of rolling average of parameters for calculating the thermal power, namely, the thermal power is calculated according to the rolling average value of sampling values of a plurality of times of measuring parameters.
However, in the prior art, two different methods are adopted to solve the problems of frequent control rod actions and large thermal power fluctuation range, so that the algorithm and the processing process of a control system are relatively complex.
Disclosure of Invention
In view of the above, there is a need to provide a method, an apparatus, a computer device and a storage medium for controlling operation of a reactor, which can solve the problems of complicated algorithm and processing procedure of the control system in the prior art.
A method of controlling operation of a reactor, the method comprising:
acquiring the original heat pipe section temperature during the operation of a nuclear power plant;
filtering the high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature; the signal frequency of the high-frequency small-amplitude disturbance part is greater than a preset frequency threshold value, and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than a preset amplitude threshold value;
controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, and determining the reactor thermal power when the nuclear power plant operates according to the target heat pipe section temperature.
In one embodiment, the filtering the high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature includes:
performing first-order filtering on the original heat pipe section temperature to obtain a first-order heat pipe section temperature;
extracting the temperature of the original heat pipe section by high-frequency fluctuation to obtain the fluctuation amount of the temperature of the heat pipe section;
and determining the target heat pipe section temperature according to the first-stage heat pipe section temperature and the heat pipe section temperature fluctuation amount.
In one embodiment, the determining the target thermal segment temperature according to the first-order thermal segment temperature and the amount of fluctuation of the thermal segment temperature includes:
processing the temperature fluctuation amount of the heat pipe section by adopting a preset temperature threshold value to obtain the temperature fluctuation amount of the nonlinear heat pipe section;
and determining the target heat pipe section temperature according to the first-stage heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation amount.
In one embodiment, the processing the heat pipe section temperature fluctuation amount by using a preset temperature threshold to obtain a nonlinear heat pipe section temperature fluctuation amount includes:
if the heat pipe section temperature fluctuation amount is not greater than a first temperature threshold and not less than the opposite number of the first temperature threshold, the nonlinear heat pipe section temperature fluctuation amount is 0; the first temperature threshold is greater than 0;
if the heat pipe section temperature fluctuation amount is larger than the first temperature threshold and smaller than a second temperature threshold, or the heat pipe section temperature fluctuation amount is larger than the opposite number of the second temperature threshold and smaller than the opposite number of the first temperature threshold, calculating the nonlinear heat pipe section temperature fluctuation amount according to the first temperature threshold, the second temperature threshold and the heat pipe section temperature fluctuation amount; the second temperature threshold is greater than the first temperature threshold;
if the heat pipe section temperature fluctuation amount is not smaller than the second temperature threshold or not larger than the opposite number of the second temperature threshold, the nonlinear heat pipe section temperature fluctuation amount is equal to the heat pipe section temperature fluctuation amount.
In one embodiment, the determining the target heat pipe section temperature according to the first-order heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation amount comprises:
determining a sum of the first-order heat pipe section temperature and the non-linear heat pipe section temperature fluctuation amount as the target heat pipe section temperature.
In one embodiment, if the amount of non-linear heat pipe segment temperature fluctuation is equal to the amount of heat pipe segment temperature fluctuation, then the sum of the first-order heat pipe segment temperature and the amount of non-linear heat pipe segment temperature fluctuation is equal to the original heat pipe segment temperature.
In one embodiment, the method further comprises:
acquiring the temperature of a cold pipe section, the load of a steam turbine and the nuclear power when the nuclear power plant operates;
the controlling control rods in a reactor of the nuclear power plant according to the target heat pipe section temperature comprises:
controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, the cold pipe section temperature, the steam turbine load, and the nuclear power.
In one embodiment, the method further comprises:
acquiring the temperature of a cold pipe section, the loop flow and the rotating speed of a main pump when the nuclear power plant operates;
the determining the reactor thermal power during the operation of the nuclear power plant according to the target heat pipe section temperature comprises the following steps:
and calculating the thermal power of the reactor according to the target heat pipe section temperature, the cold pipe section temperature, the loop flow and the main pump rotating speed.
An operation control apparatus of a reactor, the apparatus comprising:
the first acquisition module is used for acquiring the original heat pipe section temperature when the nuclear power plant operates;
the processing module is used for filtering the high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature; the signal frequency of the high-frequency small-amplitude disturbance part is greater than a preset frequency threshold value, and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than a preset amplitude threshold value;
and the control module is used for controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature and determining the thermal power of the reactor when the nuclear power plant operates according to the target heat pipe section temperature.
A computer device comprising a memory and a processor, the memory storing a computer program, the processor implementing the following steps when executing the computer program:
acquiring the original heat pipe section temperature during the operation of a nuclear power plant;
filtering the high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature; the signal frequency of the high-frequency small-amplitude disturbance part is greater than a preset frequency threshold value, and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than a preset amplitude threshold value;
controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, and determining the reactor thermal power when the nuclear power plant operates according to the target heat pipe section temperature.
A computer-readable storage medium, on which a computer program is stored which, when executed by a processor, carries out the steps of:
acquiring the original heat pipe section temperature during the operation of a nuclear power plant;
filtering the high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature; the signal frequency of the high-frequency small-amplitude disturbance part is greater than a preset frequency threshold value, and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than a preset amplitude threshold value;
controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, and determining the reactor thermal power when the nuclear power plant operates according to the target heat pipe section temperature.
According to the operation control method, the device, the computer equipment and the storage medium of the reactor, the original heat pipe section temperature of the nuclear power plant during operation is obtained through the corresponding sensor, the sensor transmits the obtained original heat pipe section temperature data to the computer equipment, the computer equipment is utilized to filter a high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain the target heat pipe section temperature, a control rod in the reactor of the nuclear power plant is controlled according to the target heat pipe section temperature, and meanwhile the reactor thermal power of the nuclear power plant during operation is determined according to the target heat pipe section temperature. Because the signal frequency of the high-frequency small-amplitude disturbance part is greater than the preset frequency threshold value, and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than the preset amplitude threshold value, the high-frequency small-amplitude disturbance part in the temperature of the heat pipe section is filtered, namely the high-frequency small-amplitude disturbance does not have much influence on the control rod, and the frequent disturbance of the control rod is avoided. In addition, the thermal power of the reactor calculated by utilizing the temperature of the target heat pipe section cannot be greatly fluctuated by a high-frequency small-amplitude disturbance part in the temperature of the target heat pipe section, so that the thermal power of the reactor in the operation process of the nuclear power plant cannot be interfered. Moreover, through the filtering treatment of the temperature of the heat pipe section, two problems of frequent fluctuation of the control rod and instantaneous fluctuation of the heat power can be solved at the same time, and the algorithm and the control process are simple.
Drawings
FIG. 1 is a diagram illustrating an exemplary embodiment of a method for controlling the operation of a reactor;
FIG. 2 is a schematic flow chart showing an operation control method of a reactor according to an embodiment;
FIG. 3 is a technical roadmap of a method for controlling the operation of a reactor according to an embodiment;
FIG. 4 is a schematic flow chart showing an operation control method of a reactor in another embodiment;
FIG. 5 is a schematic flow chart showing an operation control method of a reactor in still another embodiment;
FIG. 6 is a schematic flow diagram of heat pipe section temperature processing in one embodiment;
FIG. 7 is a schematic flow chart showing an operation control method of a reactor in still another embodiment;
FIG. 8 is a schematic flow chart showing an operation control method of a reactor in still another embodiment;
FIG. 9 is a block diagram showing an arrangement of an operation control apparatus of a reactor according to an embodiment;
FIG. 10 is a block diagram showing the construction of an operation control apparatus for a reactor in another embodiment;
FIG. 11 is a block diagram showing the construction of an operation control apparatus for a reactor in still another embodiment;
FIG. 12 is a block diagram showing the construction of an operation control apparatus for a reactor in still another embodiment;
FIG. 13 is a diagram illustrating an internal structure of a computer device according to an embodiment.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more apparent, the present application is described in further detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the present application and are not intended to limit the present application.
The reactor operation control method provided by the application can be applied to a nuclear power plant environment, as shown in fig. 1, the application environment can include a reactor 1, a sensor 2, an actuator 3 and a computer device 4, the sensor is used for acquiring the temperature of a heat pipe section, the temperature of a cold pipe section and the like of the reactor, transmitting the acquired temperature to the computer device, the computer device can filter the temperature of the heat pipe section, then control the movement of a control rod in the reactor according to the filtered temperature of the heat pipe section, and calculate the thermal power according to the filtered temperature of the heat pipe section.
In an embodiment, an operation control method of a reactor is provided, fig. 2 is a schematic flow chart of the operation control method of the reactor in an embodiment, which is described by taking the method applied to the computer device in fig. 1 as an example, and specific steps are as follows:
s201, acquiring the original heat pipe section temperature when the nuclear power plant operates.
In the nuclear power plant equipment, a coolant pipeline of a reactor primary circuit is a part of a main pipeline of the nuclear power plant, one end of the reactor is connected with a cold pipe section, and the other end of the reactor is connected with a heat pipe section, wherein the heat pipe section is a very important part, and high-temperature and high-speed coolant from a nuclear reactor passes through the heat pipe section, so that the temperature of the heat pipe section is a very important parameter in the operation process of the nuclear power plant.
In this embodiment, the computer device may obtain the original heat pipe section temperature in the operation process of the nuclear power plant in real time, or may periodically obtain the original heat pipe section temperature at the current time. For example, a temperature sensor may be disposed on the heat pipe segments, the temperature of the heat pipe segments is obtained by the temperature sensor, when the reactor includes a plurality of heat pipe segments, a temperature sensor may be disposed on each heat pipe segment, and the temperature of the heat pipe segments collected by each sensor is averaged to obtain the original heat pipe segment temperature. Or, on the premise of the operation of the nuclear power plant, when the computer device specifically acquires the original heat pipe section temperature, the heat pipe section temperature may be measured multiple times by using the corresponding temperature sensor, and the average value of the measured data is taken as the original heat pipe section temperature.
S202, filtering a high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature; the signal frequency of the high-frequency small-amplitude disturbance part is larger than a preset frequency threshold value, and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than a preset amplitude threshold value.
Specifically, according to historical experience, the temperature of the heat pipe section can be subjected to frequent small-amplitude disturbance at variable times during the operation of the nuclear power plant, and the disturbance is called high-frequency small-amplitude disturbance. The preset frequency threshold and the preset amplitude threshold in the embodiment both belong to empirical values, the preset frequency threshold can be obtained by counting the temperature of the original heat pipe section during the operation of the nuclear power plant, and the preset amplitude threshold can also be obtained by counting the temperature of the original heat pipe section during the operation of the nuclear power plant.
In the process that the computer device carries out filtering processing on the high-frequency small-amplitude disturbance part in the original heat pipe section temperature, optionally, a neural network model is established through a corresponding algorithm, the original heat pipe section temperature is used as an input signal, and the high-frequency small-amplitude disturbance part in the original heat pipe section temperature is filtered through the neural network model to obtain the target heat pipe section temperature. Optionally, the filtering process may also be performed by a filter, and similarly, the original heat pipe section temperature is used as a filter input signal, and a high-frequency small-amplitude disturbance signal in the input signal is filtered by the filter, so as to obtain the target heat pipe section temperature. In this embodiment, a specific manner of processing the original heat pipe section temperature through what filtering manner is not limited, and the computer device may obtain the target heat pipe section temperature.
S203, controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, and determining the reactor thermal power when the nuclear power plant operates according to the target heat pipe section temperature.
The control rod in the control system mainly has the function of controlling the reaction rate, in the control process of the nuclear power plant, the coolant average temperature control system measures the average temperature of the coolant in a loop, compares the average temperature with the coolant average temperature setting value, and generates an adjusting signal through the adjuster if the difference value between the average temperature and the coolant average temperature is larger than a preset threshold value, and the control rod driving mechanism drives the position of the control rod in the reactor core to realize the automatic adjustment of the temperature of the coolant in the reactor, so that the power of the reactor can track the power generation load demand in real time. If the difference value of the two is not greater than the preset threshold value, the system is stable in running state and does not need to be adjusted. The preset threshold may be obtained by counting an average temperature of the primary circuit during operation of the nuclear power plant. The thermal power of the reactor is a core parameter for representing the operation state of the unit, and in the operation technical specification of the nuclear power plant, a clear requirement is required for controlling the thermal power of the unit, for example, the thermal power is prohibited from exceeding 102% FP. Transient fluctuations in thermal power can cause an operator to have to adjust the power level of the unit in response to fluctuations in thermal power, which can interfere with the operator's normal operational control of the unit.
In this embodiment, after the original heat pipe section temperature is subjected to high-frequency small-amplitude disturbance filtering, a target heat pipe section temperature is obtained, and a control rod in a reactor of the nuclear power plant is controlled according to the target heat pipe section temperature, for example, a temperature threshold value may be set, when the target heat pipe section temperature is less than the temperature threshold value, the control rod keeps the current position unchanged, and when the target heat pipe section temperature is greater than or equal to the temperature threshold value, the position of the control rod in the reactor core is driven to change, so as to achieve automatic adjustment of the reactor coolant temperature. And, the thermal power of the reactor is calculated according to the target heat pipe section temperature, and whether instantaneous fluctuation occurs or not can be checked through the thermal power.
For example, as shown in fig. 3, the temperature power controller corresponds to a computer device, and may measure the raw heat pipe section temperature through a temperature sensor, and filter the raw heat pipe section temperature to obtain the target heat pipe section temperature. The average temperature of the coolant is obtained according to the target heat pipe section temperature and the cold pipe section temperature, the power controller can control the position of a temperature control rod group in the reactor according to the average temperature of the coolant, the purpose of adjusting the temperature of the coolant of the reactor is achieved, and meanwhile the thermal power of the reactor can be calculated according to the target heat pipe section temperature and other parameters.
In the operation control method for the reactor provided in this embodiment, the computer device obtains the temperature of the original heat pipe section of the nuclear power plant during operation, performs filtering processing on the high-frequency small-amplitude disturbance part in the temperature of the original heat pipe section to obtain the target temperature of the heat pipe section, controls the control rod in the reactor of the nuclear power plant according to the target temperature of the heat pipe section, and determines the thermal power of the reactor of the nuclear power plant during operation according to the target temperature of the heat pipe section. Because the signal frequency of the high-frequency small-amplitude disturbance part is greater than the preset frequency threshold value and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than the preset amplitude threshold value, the high-frequency small-amplitude disturbance part in the temperature of the original heat pipe section is filtered, which is equivalent to filtering the high-frequency small-amplitude disturbance part in the temperature of the heat pipe section, namely the high-frequency small-amplitude disturbance does not have more influence on the control rod, and the frequent disturbance of the control rod is avoided. In addition, the thermal power of the reactor calculated by utilizing the temperature of the target heat pipe section cannot be greatly fluctuated by a high-frequency small-amplitude disturbance part in the temperature of the target heat pipe section, so that the thermal power of the reactor in the operation process of the nuclear power plant cannot be interfered. Moreover, through the filtering treatment of the temperature of the heat pipe section, two problems of frequent fluctuation of the control rod and instantaneous fluctuation of the heat power can be solved at the same time, and the algorithm and the control process are simple.
Based on the embodiment shown in fig. 2, a specific implementation process for obtaining the target heat pipe section temperature is described in detail below by taking fig. 4 as an example, and as shown in fig. 4, the method includes the following steps:
s301, performing first-order filtering on the original heat pipe temperature to obtain a first-order heat pipe section temperature.
Specifically, the temperature of the original heat pipe section measured by the sensor is set as T0The original heat pipe section temperature T0As an input signal, the original heat pipe section temperature signal is processed by a transfer function to obtain a filtered signal T1. Wherein the transfer function can be expressed as:
Figure BDA0003261966640000081
in the formula, τ1Expressed as a time constant in units of s.
S302, extracting the high-frequency fluctuation of the original heat pipe temperature to obtain the temperature fluctuation quantity of the heat pipe section.
In particular, the sensor is also used to measure the obtained temperature T of the original heat pipe section0As an input signal, a differential hysteresis link is used for processing a temperature measurement signal of the heat pipe section, and a high-frequency fluctuation signal in the temperature measurement signal is extracted to obtain a filtered signal delta T. The differential hysteresis link can also adopt a high-pass filter, the high-pass filter can adopt a transfer function form to realize the extraction of high-frequency fluctuation signals, and the original heat pipe section temperature measurement signal T0The transfer function form to the heat pipe section temperature fluctuation amount Δ T can be expressed as:
Figure BDA0003261966640000082
in the formula, τ2Expressed as a time constant in units of s.
S303, determining the target heat pipe section temperature according to the first-stage heat pipe section temperature and the heat pipe section temperature fluctuation amount.
In this example, the heat pipe section temperature fluctuation amount may be processed or screened to obtain a processed heat pipe section temperature fluctuation amount, and then the target heat pipe section temperature may be determined according to the first-stage heat pipe section temperature and the processed heat pipe section temperature fluctuation amount. For example, a temperature threshold range may be set, and different processing may be performed on the heat pipe section temperature fluctuation amounts in different temperature threshold ranges, for example, when the heat pipe section temperature fluctuation amount is small, the heat pipe section temperature fluctuation amount may be directly processed to be zero, when the heat pipe section temperature fluctuation amount is large, the heat pipe section temperature fluctuation amount is not processed, or when the heat pipe section temperature fluctuation amount is within a preset range, part of the amplitude fluctuation in the heat pipe section temperature fluctuation amount may be extracted.
The operation control method for the reactor provided in this embodiment performs first-order filtering on the original heat pipe temperature to obtain a first-order heat pipe section temperature, and performs high-frequency fluctuation extraction on the original heat pipe temperature to obtain a heat pipe section temperature fluctuation amount, the target heat pipe section temperature is determined according to the first-stage heat pipe section temperature and the heat pipe section temperature fluctuation amount, the heat pipe section temperature causing the frequent control rod action and the steady-state reactor thermal power fluctuation is identified in the embodiment, the first-stage heat pipe section temperature and the heat pipe section temperature fluctuation quantity are obtained through the filtering processing of the heat pipe section temperature, the target heat pipe section temperature is determined according to the first-order heat pipe section temperature and the heat pipe section temperature fluctuation amount, namely, the heat pipe section temperature is subjected to high-frequency and low-frequency processing, the obtained target heat pipe section temperature is more accurate, high-frequency steady state fluctuation can be eliminated, large transient fluctuation can be reflected in time, and safe and stable operation of the nuclear power plant is guaranteed.
In the embodiment shown in fig. 4, the target heat pipe section temperature may be determined according to the first-order heat pipe section temperature and the heat pipe section temperature fluctuation amount, and in the process, the heat pipe section temperature fluctuation amount may be further processed to obtain a non-linear heat pipe section temperature fluctuation amount, as shown in fig. 5, which includes the following steps:
s401, processing the temperature fluctuation amount of the heat pipe section by adopting a preset temperature threshold value to obtain the temperature fluctuation amount of the nonlinear heat pipe section.
Specifically, the heat pipe section temperature fluctuation amount Δ T obtained through the differential hysteresis link is used as an input signal of a function generator, the function generator is used for ensuring that signal filtering only takes effect on high-frequency small-amplitude disturbance and retaining signals with other characteristics, and an output signal passing through the function generator is the nonlinear heat pipe section temperature fluctuation amount Δ T1. Using a predetermined temperature threshold to heat a section temperature waveIn the process of processing the momentum delta T, the preset temperature threshold value is mainly compared with the temperature fluctuation delta T of the heat pipe section to obtain the temperature fluctuation delta T of the nonlinear heat pipe section after high-frequency small-amplitude disturbance is filtered1The specific comparison process can be expressed as:
if the temperature fluctuation amount of the heat pipe section is not greater than a first temperature threshold and not smaller than the opposite number of the first temperature threshold, wherein the first temperature threshold is greater than 0, the temperature fluctuation amount of the nonlinear heat pipe section is 0; if the heat pipe section temperature fluctuation amount is larger than a first temperature threshold and smaller than a second temperature threshold, or the heat pipe section temperature fluctuation amount is larger than the opposite number of the second temperature threshold and smaller than the opposite number of the first temperature threshold, calculating the nonlinear heat pipe section temperature fluctuation amount according to the first temperature threshold, the second temperature threshold and the heat pipe section temperature fluctuation amount, wherein the second temperature threshold is larger than the first temperature threshold; if the fluctuation amount of the temperature of the heat pipe section is not less than the second temperature threshold or not more than the opposite number of the second temperature threshold, the temperature fluctuation amount of the nonlinear heat pipe section is equal to the temperature fluctuation amount of the heat pipe section.
The comparison process can be implemented by the following formula:
function generator output
Figure BDA0003261966640000101
In the formula, Δ T of function generator output1A non-linear heat pipe section temperature fluctuation amount; d1Representing a first temperature threshold; d2Represents a second temperature threshold; -D1An inverse number representing a first temperature threshold; -D2An inverse number representing a second temperature threshold; Δ T represents the amount of heat pipe section temperature fluctuation.
S402, determining the target heat pipe section temperature according to the first-stage heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation amount.
Specifically, the sum of the first-stage heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation amount is determined as the target heat pipe section temperature. Because the temperature fluctuation amount of the nonlinear heat pipe section is divided into three cases, the corresponding target heat pipe section temperature also needs to be described by being divided into three cases, and the specific case can be expressed as follows:
if the temperature fluctuation amount of the heat pipe section is not greater than the first temperature threshold and not less than the opposite number of the first temperature threshold, the temperature fluctuation amount of the nonlinear heat pipe section is delta T10, the target heat pipe section temperature T2Equal to a first-stage heat pipe temperature T1And the temperature fluctuation amount Delta T of the nonlinear heat pipe section1Sum, i.e. T2＝T1+ΔT1＝T1；
If the temperature fluctuation amount of the heat pipe section is larger than a first temperature threshold and smaller than a second temperature threshold, or the temperature fluctuation amount of the heat pipe section is larger than the opposite number of the second temperature threshold and smaller than the opposite number of the first temperature threshold, calculating the temperature fluctuation amount of the nonlinear heat pipe section according to the first temperature threshold, the second temperature threshold and the temperature fluctuation amount of the heat pipe section, wherein the second temperature threshold is larger than the first temperature threshold, the temperature fluctuation amount of the nonlinear heat pipe section is
Figure BDA0003261966640000102
Finally output target heat pipe section temperature value T2Equal to a first-stage heat pipe temperature T1And the temperature fluctuation amount Delta T of the nonlinear heat pipe section1Sum, i.e.
Figure BDA0003261966640000111
Target heat pipe section temperature value T2Amplitude fluctuations in the temperature superposition section of the heat pipe section, which may be expressed as first order filtering.
If the temperature fluctuation amount of the heat pipe section is not less than the second temperature threshold or not greater than the opposite number of the second temperature threshold, the temperature fluctuation amount of the nonlinear heat pipe section is equal to the temperature fluctuation amount of the heat pipe section, and the temperature fluctuation amount of the nonlinear heat pipe section is delta T1The final output target heat pipe section temperature value T is equal to delta T2Equal to a first-stage heat pipe temperature T1And the temperature fluctuation amount Delta T of the nonlinear heat pipe section1Sum, i.e. T2＝T1+ Δ T, the final output target heat pipe section temperature value is the original heat pipe section temperature measurement signal.
Optionally, if the amount of temperature fluctuation of the nonlinear heat pipe section is equal to the amount of temperature fluctuation of the heat pipe section, the sum of the first-order heat pipe section temperature and the amount of temperature fluctuation of the nonlinear heat pipe section is equal to the original heat pipe section temperature.
In this embodiment, if the fluctuation amount of the temperature of the heat pipe section is not less than the second temperature threshold or not greater than the opposite number of the second temperature threshold, it is indicated that the temperature of the heat pipe section has a large jump in the operation process of the reactor of the nuclear power plant, and in this case, other fault states may occur in the nuclear power plant.
In this embodiment, the raw heat pipe section temperature T is measured as shown in FIG. 60As input signals for module 1 and module 2, module 1 uses a transfer function
Figure BDA0003261966640000112
For original heat pipe section temperature T0The middle low frequency signal is subjected to first-order filtering processing to obtain first-order heat pipe section temperature T1. While using transfer functions via the module 2
Figure BDA0003261966640000113
For original heat pipe section temperature T0And (5) carrying out differential hysteresis link processing on the medium-high frequency signal to obtain the temperature fluctuation quantity delta T of the heat pipe section. Filtering the obtained heat pipe section temperature fluctuation quantity delta T by a function generator in the module 3 to obtain the nonlinear heat pipe section temperature fluctuation quantity delta T after high-frequency small-amplitude disturbance is filtered1. By obtaining a first-stage heat pipe temperature T1And nonlinear heat pipe section temperature fluctuation amount delta T1Adding to obtain the output target heat pipe section temperature T2。
According to the operation control method of the reactor provided by the embodiment, the temperature fluctuation amount of the heat pipe section is filtered by adopting the preset temperature threshold value to obtain the temperature fluctuation amount of the non-linear heat pipe section, and the target heat pipe section temperature is determined according to the sum of the first-order heat pipe section temperature and the temperature fluctuation amount of the non-linear heat pipe section, so that the target heat pipe section temperature is more accurate, the temperature condition under a real-time scene can be reflected more effectively, the problems of frequent movement of a control rod and steady fluctuation of the thermal power of the reactor can be solved more effectively, the dynamic performance of a nuclear power unit in response to transient change can not be weakened, the change of the thermal power of the reactor of the nuclear power plant can be reflected in time, and the safe and stable operation of the nuclear power plant can be reasonably ensured.
In some scenarios, when the control rod is controlled, the control rod may also be comprehensively controlled by referring to other operating parameters of the nuclear power plant, as shown in fig. 7, the method may be divided into the following steps:
s501, obtaining the temperature of a cold pipe section, the load of a steam turbine and the nuclear power when the nuclear power plant operates.
Specifically, parameters such as the average temperature of the coolant, the load of a turbine, the nuclear power and the like can be referred to when the control rod of the nuclear power plant is controlled, wherein the average temperature of the coolant can be obtained according to the average value of the temperature of the heat pipe section and the temperature of the cold pipe section, and the load of the turbine can be used for obtaining the setting value of the temperature of the coolant and determining the deviation of the temperature of the turbine and the power of the reactor.
Controlling control rods in a reactor of a nuclear power plant according to a target heat pipe section temperature in step S203 in fig. 2 includes:
and S502, controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, the target cold pipe section temperature, the turbine load and the nuclear power.
Specifically, the control process of the control rod is completed based on the target heat pipe section temperature, the cold pipe section temperature, the steam turbine load and the nuclear power, wherein the target heat pipe section temperature has the largest influence on the control rod, and changes of other parameters have relatively small influence on the control rod, so that the control rod is controlled by combining the cold pipe section temperature, the steam turbine load, the nuclear power and the target heat pipe section temperature.
In this embodiment, parameters such as target hot pipe section temperature, cold pipe section temperature, turbine load, and nuclear power can be comprehensively considered to control the position of the control rods in the reactor, thereby controlling the reaction rate. The target heat pipe section temperature is a main factor influencing the frequent fluctuation of the control rod, so that the movement of the control rod is controlled through the target heat pipe section temperature, the problem of frequent fluctuation of the control rod is solved from the source, and the running process of a nuclear power plant can be more stable.
In some scenarios, other operating parameters of the nuclear power plant may also be referenced when calculating the thermal power, as shown in fig. 8, the method may further comprise the steps of:
s601, obtaining the temperature of a cold pipe section, the loop flow and the rotating speed of a main pump when the nuclear power plant operates.
Specifically, the thermal power can be calculated by comprehensively referring to the cold pipe section temperature, the loop flow, the main pump rotating speed and other parameters when the nuclear power plant operates, besides the heat pipe section temperature is mainly considered when the thermal power is calculated.
Determining the reactor thermal power when the nuclear power plant operates according to the target heat pipe section temperature in step S203 in fig. 2 includes:
and S602, calculating the thermal power of the reactor according to the target heat pipe section temperature, the cold pipe section temperature, the loop flow and the main pump rotating speed.
Specifically, the thermal power of the reactor is calculated based on the temperature of the hot pipe section, the temperature of the cold pipe section, the loop flow, the rotating speed of the main pump and the like. In the measurement parameters, the influence of the heat pipe section temperature fluctuation on the thermal power of the reactor is the largest, so that in the calculation process, the original heat pipe section temperature is filtered to obtain the target heat pipe section temperature, and the thermal power of the reactor during the operation of the nuclear power plant can be determined according to the target heat pipe section temperature, the cold pipe section temperature, the loop flow and the main pump rotating speed.
In this embodiment, parameters such as a target heat pipe section temperature, a cold pipe section temperature, a loop flow rate, a main pump rotating speed and the like can be comprehensively considered, the target heat pipe section temperature has a large influence on thermal power due to reaction, and because the influence of a high-frequency small-amplitude disturbance signal has been filtered out from the target heat pipe section temperature, the thermal power of the reactor calculated according to the target heat pipe section temperature is not influenced by the high-frequency small-amplitude disturbance signal, so that safe and stable operation of the nuclear power plant is guaranteed.
It should be understood that although the various steps in fig. 2, 4-5, and 7-8 are shown in order as indicated by the arrows, the steps are not necessarily performed in order as indicated by the arrows. The steps are not performed in the exact order shown and described, and may be performed in other orders, unless explicitly stated otherwise. Moreover, at least some of the steps of fig. 2, 4-5, and 7-8 may include multiple steps or multiple stages that are not necessarily performed at the same time, but may be performed at different times, and the order of execution of the steps or stages is not necessarily sequential, but may be alternated or performed with other steps or at least some of the other steps or stages.
In one embodiment, as shown in fig. 9, there is provided an operation control device of a reactor, including: a first obtaining module 11, a processing module 12 and a control module 13, wherein:
the first acquisition module 11 is used for acquiring the original heat pipe section temperature when the nuclear power plant operates;
the processing module 12 is configured to perform filtering processing on a high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature; the signal frequency of the high-frequency small-amplitude disturbance part is greater than a preset frequency threshold value, and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than a preset amplitude threshold value;
and the control module 13 is used for controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature and determining the thermal power of the reactor when the nuclear power plant operates according to the target heat pipe section temperature.
The operation control device for a reactor provided in this embodiment may implement the above method embodiments, and the implementation principle and technical effect are similar, and are not described herein again.
On the basis of the foregoing embodiment, optionally, as shown in fig. 10, the processing module 12 includes: a filtering unit 121, an extracting unit 122, and a determining unit 123, wherein:
the filtering unit 121 is configured to perform first-order filtering on the original heat pipe section temperature to obtain a first-order heat pipe section temperature;
the extracting unit 122 is configured to perform high-frequency fluctuation extraction on the temperature of the original heat pipe section to obtain a heat pipe section temperature fluctuation amount;
a determining unit 123, configured to determine a target heat pipe section temperature according to the first-order heat pipe section temperature and the heat pipe section temperature fluctuation amount.
The operation control device for a reactor provided in this embodiment may implement the above method embodiments, and the implementation principle and technical effect are similar, and are not described herein again.
On the basis of the foregoing embodiment, optionally, the determining unit 123 is specifically configured to process the heat pipe section temperature fluctuation amount by using a preset temperature threshold, so as to obtain a nonlinear heat pipe section temperature fluctuation amount; and determining the target heat pipe section temperature according to the first-order heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation quantity.
The operation control device for a reactor provided in this embodiment may implement the above method embodiments, and the implementation principle and technical effect are similar, and are not described herein again.
On the basis of the foregoing embodiment, optionally, the determining unit 123 is specifically configured to, if the amount of fluctuation of the temperature of the heat pipe section is not greater than the first temperature threshold and is not less than an opposite number of the first temperature threshold, set the amount of fluctuation of the temperature of the nonlinear heat pipe section to be 0; the first temperature threshold is greater than 0; if the temperature fluctuation amount of the heat pipe section is larger than a first temperature threshold and smaller than a second temperature threshold, or the temperature fluctuation amount of the heat pipe section is larger than the opposite number of the second temperature threshold and smaller than the opposite number of the first temperature threshold, calculating the temperature fluctuation amount of the nonlinear heat pipe section according to the first temperature threshold, the second temperature threshold and the temperature fluctuation amount of the heat pipe section; the second temperature threshold is greater than the first temperature threshold; if the fluctuation amount of the temperature of the heat pipe section is not less than the second temperature threshold or not more than the opposite number of the second temperature threshold, the temperature fluctuation amount of the nonlinear heat pipe section is equal to the temperature fluctuation amount of the heat pipe section.
The operation control device for a reactor provided in this embodiment may implement the above method embodiments, and the implementation principle and technical effect are similar, and are not described herein again.
On the basis of the foregoing embodiment, optionally, the determination unit 123 is specifically configured to determine a sum of the first-order heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation amount as the target heat pipe section temperature.
Optionally, if the temperature fluctuation amount of the nonlinear heat pipe section is equal to the temperature fluctuation amount of the heat pipe section, the sum of the temperature of the first-order heat pipe section and the temperature fluctuation amount of the nonlinear heat pipe section is equal to the temperature of the original heat pipe section.
The operation control device for a reactor provided in this embodiment may implement the above method embodiments, and the implementation principle and technical effect are similar, and are not described herein again.
On the basis of the above embodiment, optionally, as shown in fig. 11, the apparatus further includes: a second obtaining module 14, wherein:
the second obtaining module 14 is configured to obtain a cold pipe section temperature, a steam turbine load, and a nuclear power when the nuclear power plant operates;
the control module 12 is configured to control a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, cold pipe section temperature, turbine load, and nuclear power.
The operation control device for a reactor provided in this embodiment may implement the above method embodiments, and the implementation principle and technical effect are similar, and are not described herein again.
On the basis of the above embodiment, optionally, as shown in fig. 12, the apparatus further includes: a third obtaining module 15, wherein:
the third obtaining module 15 is configured to obtain a cold pipe section temperature, a loop flow and a main pump rotation speed when the nuclear power plant operates;
the control module 12 is configured to calculate the thermal power of the reactor according to the target heat pipe section temperature, the cold pipe section temperature, the loop flow, and the main pump rotation speed.
The operation control device for a reactor provided in this embodiment may implement the above method embodiments, and the implementation principle and technical effect are similar, and are not described herein again.
For specific limitations of the reactor operation control device, reference may be made to the above limitations of the reactor operation control method, which are not described herein again. The respective modules in the operation control apparatus of the reactor described above may be wholly or partially implemented by software, hardware, and a combination thereof. The modules can be embedded in a hardware form or independent from a processor in the computer device, and can also be stored in a memory in the computer device in a software form, so that the processor can call and execute operations corresponding to the modules.
In one embodiment, a computer device is provided, which may be a terminal, and its internal structure diagram may be as shown in fig. 13. The computer device includes a processor, a memory, a communication interface, a display screen, and an input device connected by a system bus. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device comprises a nonvolatile storage medium and an internal memory. The non-volatile storage medium stores an operating system and a computer program. The internal memory provides an environment for the operation of an operating system and computer programs in the non-volatile storage medium. The communication interface of the computer device is used for carrying out wired or wireless communication with an external terminal, and the wireless communication can be realized through WIFI, an operator network, NFC (near field communication) or other technologies. The computer program is executed by a processor to implement a method of controlling the operation of a reactor. The display screen of the computer equipment can be a liquid crystal display screen or an electronic ink display screen, and the input device of the computer equipment can be a touch layer covered on the display screen, a key, a track ball or a touch pad arranged on the shell of the computer equipment, an external keyboard, a touch pad or a mouse and the like.
Those skilled in the art will appreciate that the architecture shown in fig. 13 is merely a block diagram of some of the structures associated with the disclosed aspects and is not intended to limit the computing devices to which the disclosed aspects apply, as particular computing devices may include more or less components than those shown, or may combine certain components, or have a different arrangement of components.
In one embodiment, a computer device is provided, comprising a memory and a processor, the memory having a computer program stored therein, the processor implementing the following steps when executing the computer program:
acquiring the original heat pipe section temperature during the operation of a nuclear power plant;
filtering the high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature; the signal frequency of the high-frequency small-amplitude disturbance part is greater than a preset frequency threshold value, and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than a preset amplitude threshold value;
controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, and determining the reactor thermal power when the nuclear power plant operates according to the target heat pipe section temperature.
In one embodiment, the processor, when executing the computer program, further performs the steps of:
filtering the high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature, wherein the method comprises the following steps:
performing first-order filtering on the original heat pipe section temperature to obtain a first-order heat pipe section temperature;
extracting the temperature of the original heat pipe section by high-frequency fluctuation to obtain the fluctuation amount of the temperature of the heat pipe section;
and determining the target heat pipe section temperature according to the first-stage heat pipe section temperature and the heat pipe section temperature fluctuation amount.
In one embodiment, the processor, when executing the computer program, further performs the steps of:
determining a target heat pipe section temperature according to the first-order heat pipe section temperature and the heat pipe section temperature fluctuation quantity, wherein the step comprises the following steps:
processing the temperature fluctuation amount of the heat pipe section by adopting a preset temperature threshold value to obtain the temperature fluctuation amount of the nonlinear heat pipe section;
and determining the target heat pipe section temperature according to the first-order heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation quantity.
In one embodiment, the processor, when executing the computer program, further performs the steps of:
the method comprises the following steps of processing the temperature fluctuation amount of the heat pipe section by adopting a preset temperature threshold value to obtain the temperature fluctuation amount of the nonlinear heat pipe section, and comprises the following steps:
if the temperature fluctuation amount of the heat pipe section is not greater than the first temperature threshold and not less than the opposite number of the first temperature threshold, the temperature fluctuation amount of the nonlinear heat pipe section is 0; the first temperature threshold is greater than 0;
if the temperature fluctuation amount of the heat pipe section is larger than a first temperature threshold and smaller than a second temperature threshold, or the temperature fluctuation amount of the heat pipe section is larger than the opposite number of the second temperature threshold and smaller than the opposite number of the first temperature threshold, calculating the temperature fluctuation amount of the nonlinear heat pipe section according to the first temperature threshold, the second temperature threshold and the temperature fluctuation amount of the heat pipe section; the second temperature threshold is greater than the first temperature threshold;
if the fluctuation amount of the temperature of the heat pipe section is not less than the second temperature threshold or not more than the opposite number of the second temperature threshold, the temperature fluctuation amount of the nonlinear heat pipe section is equal to the temperature fluctuation amount of the heat pipe section.
In one embodiment, the processor, when executing the computer program, further performs the steps of:
determining a target heat pipe section temperature according to the first-order heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation quantity, wherein the step comprises the following steps:
and determining the sum of the first-stage heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation amount as a target heat pipe section temperature.
In one embodiment, the processor, when executing the computer program, further performs the steps of:
if the temperature fluctuation amount of the nonlinear heat pipe section is equal to the temperature fluctuation amount of the heat pipe section, the sum of the temperature of the first-stage heat pipe section and the temperature fluctuation amount of the nonlinear heat pipe section is equal to the original temperature of the heat pipe section.
In one embodiment, the processor, when executing the computer program, further performs the steps of:
acquiring the temperature of a cold pipe section, the load of a steam turbine and the nuclear power when a nuclear power plant operates;
controlling control rods in a reactor of a nuclear power plant according to a target heat pipe section temperature, comprising:
and controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, the cold pipe section temperature, the steam turbine load and the nuclear power.
In one embodiment, the processor, when executing the computer program, further performs the steps of:
acquiring the temperature of a cold pipe section, the loop flow and the rotating speed of a main pump when a nuclear power plant operates;
determining the reactor thermal power during the operation of the nuclear power plant according to the temperature of the target heat pipe section, and the method comprises the following steps:
and calculating the thermal power of the reactor according to the target heat pipe section temperature, the cold pipe section temperature, the loop flow and the main pump rotating speed.
The implementation principle and technical effect of the computer device provided by the above embodiment are similar to those of the above method embodiment, and are not described herein again.
In one embodiment, a computer-readable storage medium is provided, having a computer program stored thereon, which when executed by a processor, performs the steps of:
acquiring the original heat pipe section temperature during the operation of a nuclear power plant;
filtering the high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature; the signal frequency of the high-frequency small-amplitude disturbance part is greater than a preset frequency threshold value, and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than a preset amplitude threshold value;
controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, and determining the reactor thermal power when the nuclear power plant operates according to the target heat pipe section temperature.
In one embodiment, the computer program when executed by the processor further performs the steps of:
filtering the high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature, wherein the method comprises the following steps:
performing first-order filtering on the original heat pipe section temperature to obtain a first-order heat pipe section temperature;
extracting the temperature of the original heat pipe section by high-frequency fluctuation to obtain the fluctuation amount of the temperature of the heat pipe section;
and determining the target heat pipe section temperature according to the first-stage heat pipe section temperature and the heat pipe section temperature fluctuation amount.
In one embodiment, the computer program when executed by the processor further performs the steps of:
determining a target heat pipe section temperature according to the first-order heat pipe section temperature and the heat pipe section temperature fluctuation quantity, wherein the step comprises the following steps:
processing the temperature fluctuation amount of the heat pipe section by adopting a preset temperature threshold value to obtain the temperature fluctuation amount of the nonlinear heat pipe section;
and determining the target heat pipe section temperature according to the first-order heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation quantity.
In one embodiment, the computer program when executed by the processor further performs the steps of:
the method comprises the following steps of processing the temperature fluctuation amount of the heat pipe section by adopting a preset temperature threshold value to obtain the temperature fluctuation amount of the nonlinear heat pipe section, and comprises the following steps:
if the temperature fluctuation amount of the heat pipe section is not greater than the first temperature threshold and not less than the opposite number of the first temperature threshold, the temperature fluctuation amount of the nonlinear heat pipe section is 0; the first temperature threshold is greater than 0;
if the temperature fluctuation amount of the heat pipe section is larger than a first temperature threshold and smaller than a second temperature threshold, or the temperature fluctuation amount of the heat pipe section is larger than the opposite number of the second temperature threshold and smaller than the opposite number of the first temperature threshold, calculating the temperature fluctuation amount of the nonlinear heat pipe section according to the first temperature threshold, the second temperature threshold and the temperature fluctuation amount of the heat pipe section; the second temperature threshold is greater than the first temperature threshold;
if the fluctuation amount of the temperature of the heat pipe section is not less than the second temperature threshold or not more than the opposite number of the second temperature threshold, the temperature fluctuation amount of the nonlinear heat pipe section is equal to the temperature fluctuation amount of the heat pipe section.
In one embodiment, the computer program when executed by the processor further performs the steps of:
determining a target heat pipe section temperature according to the first-order heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation quantity, wherein the step comprises the following steps:
and determining the sum of the first-stage heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation amount as a target heat pipe section temperature.
In one embodiment, the computer program when executed by the processor further performs the steps of:
if the temperature fluctuation amount of the nonlinear heat pipe section is equal to the temperature fluctuation amount of the heat pipe section, the sum of the temperature of the first-stage heat pipe section and the temperature fluctuation amount of the nonlinear heat pipe section is equal to the original temperature of the heat pipe section.
In one embodiment, the computer program when executed by the processor further performs the steps of:
acquiring the temperature of a cold pipe section, the load of a steam turbine and the nuclear power when a nuclear power plant operates;
controlling control rods in a reactor of a nuclear power plant according to a target heat pipe section temperature, comprising:
and controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, the cold pipe section temperature, the steam turbine load and the nuclear power.
In one embodiment, the computer program when executed by the processor further performs the steps of:
acquiring the temperature of a cold pipe section, the loop flow and the rotating speed of a main pump when a nuclear power plant operates;
determining the reactor thermal power during the operation of the nuclear power plant according to the temperature of the target heat pipe section, and the method comprises the following steps:
and calculating the thermal power of the reactor according to the target heat pipe section temperature, the cold pipe section temperature, the loop flow and the main pump rotating speed.
The implementation principle and technical effect of the computer-readable storage medium provided by the above embodiments are similar to those of the above method embodiments, and are not described herein again.
It will be understood by those skilled in the art that all or part of the processes of the methods of the embodiments described above can be implemented by hardware related to instructions of a computer program, which can be stored in a non-volatile computer-readable storage medium, and when executed, can include the processes of the embodiments of the methods described above. Any reference to memory, storage, database or other medium used in the embodiments provided herein can include at least one of non-volatile and volatile memory. Non-volatile Memory may include Read-Only Memory (ROM), magnetic tape, floppy disk, flash Memory, optical storage, or the like. Volatile Memory can include Random Access Memory (RAM) or external cache Memory. By way of illustration and not limitation, RAM can take many forms, such as Static Random Access Memory (SRAM) or Dynamic Random Access Memory (DRAM), among others.
The technical features of the above embodiments can be arbitrarily combined, and for the sake of brevity, all possible combinations of the technical features in the above embodiments are not described, but should be considered as the scope of the present specification as long as there is no contradiction between the combinations of the technical features.
The above examples only express several embodiments of the present application, and the description thereof is more specific and detailed, but not construed as limiting the scope of the invention. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the concept of the present application, which falls within the scope of protection of the present application. Therefore, the protection scope of the present patent shall be subject to the appended claims.

Claims (11)

1. A method for controlling the operation of a reactor, the method comprising:
acquiring the original heat pipe section temperature during the operation of a nuclear power plant;
filtering the high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature; the signal frequency of the high-frequency small-amplitude disturbance part is greater than a preset frequency threshold value, and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than a preset amplitude threshold value;
controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, and determining the reactor thermal power when the nuclear power plant operates according to the target heat pipe section temperature.
2. The method of claim 1, wherein the filtering the high frequency small amplitude disturbance component of the original thermal segment temperature to obtain a target thermal segment temperature comprises:
performing first-order filtering on the original heat pipe section temperature to obtain a first-order heat pipe section temperature;
extracting the temperature of the original heat pipe section by high-frequency fluctuation to obtain the fluctuation amount of the temperature of the heat pipe section;
and determining the target heat pipe section temperature according to the first-stage heat pipe section temperature and the heat pipe section temperature fluctuation amount.
3. The method of claim 2, wherein the determining the target thermal segment temperature from the first-order thermal segment temperature and the amount of thermal segment temperature fluctuation comprises:
carrying out nonlinear processing on the temperature fluctuation amount of the heat pipe section by adopting a preset temperature threshold value to obtain the temperature fluctuation amount of the nonlinear heat pipe section;
and determining the target heat pipe section temperature according to the first-stage heat pipe section temperature and the nonlinear heat pipe section temperature fluctuation amount.
4. The method of claim 3, wherein the processing the amount of temperature fluctuation of the heat pipe section with a preset temperature threshold to obtain an amount of temperature fluctuation of a non-linear heat pipe section comprises:
if the heat pipe section temperature fluctuation amount is not greater than a first temperature threshold and not less than the opposite number of the first temperature threshold, the nonlinear heat pipe section temperature fluctuation amount is 0; the first temperature threshold is greater than 0;
if the heat pipe section temperature fluctuation amount is larger than the first temperature threshold and smaller than a second temperature threshold, or the heat pipe section temperature fluctuation amount is larger than the opposite number of the second temperature threshold and smaller than the opposite number of the first temperature threshold, calculating the nonlinear heat pipe section temperature fluctuation amount according to the first temperature threshold, the second temperature threshold and the heat pipe section temperature fluctuation amount; the second temperature threshold is greater than the first temperature threshold;
if the heat pipe section temperature fluctuation amount is not smaller than the second temperature threshold or not larger than the opposite number of the second temperature threshold, the nonlinear heat pipe section temperature fluctuation amount is equal to the heat pipe section temperature fluctuation amount.
5. The method of claim 3 or 4, wherein the determining the target thermal segment temperature from the first-order thermal segment temperature and the amount of non-linear thermal segment temperature fluctuation comprises:
determining a sum of the first-order heat pipe section temperature and the non-linear heat pipe section temperature fluctuation amount as the target heat pipe section temperature.
6. The method of claim 5 wherein the sum of the first-order thermal stage temperature and the amount of nonlinear thermal stage temperature fluctuation is equal to the original thermal stage temperature if the amount of nonlinear thermal stage temperature fluctuation is equal to the amount of thermal stage temperature fluctuation.
7. The method according to any one of claims 1-4, further comprising:
acquiring the temperature of a cold pipe section, the load of a steam turbine and the nuclear power when the nuclear power plant operates;
the controlling control rods in a reactor of the nuclear power plant according to the target heat pipe section temperature comprises:
controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature, the cold pipe section temperature, the steam turbine load, and the nuclear power.
8. The method according to any one of claims 1-4, further comprising:
acquiring the temperature of a cold pipe section, the loop flow and the rotating speed of a main pump when the nuclear power plant operates;
the determining the reactor thermal power during the operation of the nuclear power plant according to the target heat pipe section temperature comprises the following steps:
and calculating the thermal power of the reactor according to the target heat pipe section temperature, the cold pipe section temperature, the loop flow and the main pump rotating speed.
9. An operation control device of a reactor, characterized by comprising:
the first acquisition module is used for acquiring the original heat pipe section temperature when the nuclear power plant operates;
the processing module is used for filtering the high-frequency small-amplitude disturbance part in the original heat pipe section temperature to obtain a target heat pipe section temperature; the signal frequency of the high-frequency small-amplitude disturbance part is greater than a preset frequency threshold value, and the signal amplitude of the high-frequency small-amplitude disturbance part is smaller than a preset amplitude threshold value;
and the control module is used for controlling a control rod in a reactor of the nuclear power plant according to the target heat pipe section temperature and determining the thermal power of the reactor when the nuclear power plant operates according to the target heat pipe section temperature.
10. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor, when executing the computer program, implements the steps of the method of any of claims 1 to 8.
11. A computer-readable storage medium, on which a computer program is stored, which, when being executed by a processor, carries out the steps of the method of any one of claims 1 to 8.
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