Method and system for monitoring nuclear power plant axial power deviation, and terminal device

Abstract

A method and system for monitoring nuclear power plant axial power deviation, and a terminal device. The method for monitoring nuclear power plant axial power deviation comprises: acquiring real-time monitoring data (S10); wherein the real-time monitoring data is from a plurality of nuclear power plant monitoring systems, and the plurality of nuclear power plant monitoring systems comprise at least two of an operation monitoring system, a control rod control and position system, a nuclear sampling system and a reactor core measurement system; according to the real-time monitoring data, determining important display parameters and preset display parameters (S20); wherein the preset display parameters comprise a real-time axial power deviation, a continuous parameter, an axial power deviation influence parameter and an auxiliary function parameter; and outputting the preset display parameters and the important display parameters (S30).

Description

Axial power deviation monitoring method and system for nuclear power plant, and terminal device TECHNICAL FIELD

[0001] The present application relates to the technical field of reactor control and protection, and particularly relates to an axial power deviation monitoring method and system for a nuclear power plant, and a terminal device. BACKGROUND

[0002] The axial power deviation of a reactor core represents the uniformity of the axial power distribution and is a parameter that needs to be controlled during operation. There are many factors that affect the axial power deviation, and the amount of information that needs to be monitored by an operator is large. The information is scattered in multiple different nuclear power plant monitoring systems. In addition, there are many intervention methods for the axial power deviation, so many operation pages need to be called to adjust the axial power deviation, which makes the operation very cumbersome and inefficient. In the adjustment process, the operator also needs to manually collect and record some important data (such as the G-rod insertion operation time), and some important parameters that affect the axial power deviation need to be manually calculated by the operator, which requires the operator to spend a certain amount of time to complete the recording and calculation, and there is a risk of human error, which is not conducive to the stable operation of the reactor. SUMMARY

[0003] The technical problem to be solved by the present application is to provide an axial power deviation monitoring method and system for a nuclear power plant, and a terminal device.

[0004] The technical solution adopted by the present application to solve the technical problem is: constructing an axial power deviation monitoring method for a nuclear power plant, comprising:

[0005] obtaining real-time monitoring data; wherein the real-time monitoring data is from multiple nuclear power plant monitoring systems, and the multiple nuclear power plant monitoring systems include at least two of an operation monitoring system, a rod control rod position system, a nuclear sampling system, and a reactor core measurement system;

[0006] determining important display parameters and preset display parameters according to the real-time monitoring data; wherein the preset display parameters include real-time axial power deviation, continuous parameters, axial power deviation influence parameters, and auxiliary function parameters;

[0007] outputting the preset display parameters and the important display parameters.

[0008] Preferably, the real-time monitoring data includes a full-power reference axial power distribution value, and axial power deviation measurement values, left limit measurement values, and right limit measurement values measured by four measurement channels; and the important display parameters include a worst channel axial power deviation.

[0009] The determining of the important display parameters and the preset display parameters according to the real-time monitoring data comprises:

[0010] determining an axial power deviation coefficient corresponding to each of the measurement channels according to the full power reference axial power distribution value and each of the axial power deviation measurement values;

[0011] calculating a first difference absolute value between the axial power deviation coefficient and the left limit measurement value and a second difference absolute value between the axial power deviation coefficient and the right limit measurement value in each of the measurement channels respectively;

[0012] determining the measurement channel corresponding to the minimum difference absolute value among the first difference absolute values and the second difference absolute values as the worst channel, and determining the axial power deviation measurement value of the worst channel as the axial power deviation of the worst channel.

[0013] Preferably, the important display parameters further include a left limit value and a right limit value.

[0014] The method further comprises:

[0015] determining the left limit measurement value corresponding to the worst channel as the left limit value.

[0016] determining the right limit measurement value corresponding to the worst channel as the right limit value.

[0017] Preferably, the real-time monitoring data further include a preset left line compensation value, a preset right line compensation value and a current core power, and the important display parameters further include a left line value and a right line value.

[0018] The method further comprises:

[0019] calculating a running reference value according to the full power reference axial power distribution value and the axial power deviation of the worst channel.

[0020] determining the left line value as the difference between the running reference value and the left line compensation value.

[0021] determining the right line value as the sum of the running reference value and the right line compensation value.

[0022] Preferably, the expression of the running reference value is:

[0023] ;

[0024] wherein, represents the running reference value, represents the full power reference axial power distribution value, represents the axial power deviation of the worst channel.

[0025] Preferably, the preset display parameter further comprises a control rod operation region.

[0026] The nuclear power plant axial power deviation monitoring method further comprises:

[0027] A rod operation instruction is acquired, and a rod control signal of a rod position is input to a rod control system according to the rod operation instruction.

[0028] Preferably, the continuous parameter comprises at least one of a nuclear power change graph, an R-rod position change graph, and an axial power deviation change graph.

[0029] The axial power deviation influence parameter comprises at least one of a current nuclear power, a primary and secondary loop temperature difference, a primary loop boron concentration, and a reactor core xenon poisoning.

[0030] The auxiliary function parameter comprises at least one of a G-rod insertion time, a rod action indication signal, a rod lock indication signal, an overrunning graph time, a control rod action parameter, and a control rod alarm parameter.

[0031] Preferably, the outputting of the preset display parameter and the important display parameter comprises:

[0032] The preset display parameter and the important display parameter are output to a human-computer interaction unit, so as to display the preset display parameter and the important display parameter through the human-computer interaction unit.

[0033] The present application also provides a terminal device, which comprises a memory, a processor, and a computer program stored in the memory and executable on the processor, and the processor implements the steps of the nuclear power plant axial power deviation monitoring method when executing the computer program.

[0034] The present application also provides a nuclear power plant axial power deviation monitoring system, which comprises:

[0035] The terminal device as described above; and

[0036] A human-computer interaction unit is configured to display the preset display parameter and the important display parameter.

[0037] The technical solution of the present application can optimize the axial power deviation monitoring and control operation mode, help the operator to automatically calculate the important parameters, effectively improve the operation efficiency, reduce the workload of the operator, reduce the risk of human error, and play a positive role in improving the stability of the reactor operation. BRIEF DESCRIPTION OF DRAWINGS

[0038] The present application will be further described below in combination with the drawings and embodiments, and the drawings show:

[0039] Fig. 1 is a program flow chart of a method for monitoring axial power deviation of a nuclear power plant according to some embodiments of the present application;

[0040] Fig. 2 is a display interface of preset display parameters and important display parameters according to some embodiments of the present application;

[0041] Fig. 3 is a running chart of axial power deviation of some measurement channels according to some embodiments of the present application;

[0042] Fig. 4 is a one-dimensional display chart of important display parameters according to some embodiments of the present application;

[0043] Fig. 5 is a structural schematic diagram of a terminal device according to some embodiments of the present application;

[0044] Fig. 6 is a structural schematic diagram of a nuclear power plant axial power deviation monitoring system according to some embodiments of the present application. DETAILED DESCRIPTION

[0045] In order to have a clearer understanding of the technical features, objectives and effects of the present application, the specific embodiments of the present application will be described in detail with reference to the accompanying drawings.

[0046] It should be noted that the flow chart shown in the accompanying drawings is only illustrative, and does not necessarily include all the contents and operations / steps, nor does it necessarily execute in the order described. For example, some operations / steps can be further divided, and some operations / steps can be combined or partially combined, so the actual execution order can be changed according to the actual situation.

[0047] The block diagram shown in the accompanying drawings is only a functional entity, and does not necessarily correspond to a physically independent entity. That is, the functional entity can be implemented in the form of software, or in one or more hardware modules or integrated circuits, or in different networks and / or processor devices and / or microcontroller devices.

[0048] Fig. 1 is a program flow chart of a method for monitoring axial power deviation of a nuclear power plant according to some embodiments of the present application. The method is used in a device terminal, and can optimize the monitoring and control operation mode of axial power deviation, and can help the operator to automatically calculate important parameters, effectively improve the operation efficiency, reduce the workload of the operator, reduce the risk of human error, and play a positive role in improving the stability of the reactor operation. The method includes steps S10, S20 and S30.

[0049] The step S10 comprises: acquiring real-time monitoring data; wherein the real-time monitoring data is from a plurality of nuclear power plant monitoring systems, and the plurality of nuclear power plant monitoring systems comprises at least two of an operation monitoring system, a rod control and rod position system, a nuclear sampling system and a reactor core measurement system. In this step, the device terminal can obtain the real-time monitoring data by interacting with the plurality of nuclear power plant monitoring systems. Further, the real-time monitoring data can include current nuclear power, full power reference axial power distribution value, over operating graph time, preset left line compensation value, preset right line compensation value, primary and secondary loop temperature difference, real-time position of R rod, G rod insertion time, rod action indication signal, rod locking indication signal and control rod alarm parameter, primary loop boron concentration, reactor core xenon poison concentration, and axial power deviation measurement value, left limit measurement value and right limit measurement value measured by four measurement channels, etc.

[0050] The operation monitoring system (i.e., OSS system) can interact with the terminal device to enable the terminal device to obtain current nuclear power, full power reference axial power distribution value, over operating graph time, preset left line compensation value, preset right line compensation value, and axial power deviation measurement value, left limit measurement value and right limit measurement value measured by four measurement channels, etc. It should be noted that in a certain nuclear power plant, the OSS system is provided with four axial power measurement channels to respectively detect the axial power deviation of the reactor, and the axial power deviation measurement value, left limit measurement value and right limit measurement value corresponding to each channel are calculated by using existing algorithms. Among them, the full power reference axial power distribution value, the preset left line compensation value and the preset right line compensation value can be set by the operator based on the actual operation requirements of the nuclear power plant by operating the OSS system, and can be generally considered as constants. In addition, the over operating graph time refers to the cumulative time of the reactor power exceeding a certain set power zone within 12 consecutive hours, which is a parameter for evaluating whether the reactor is stably operated.

[0051] The rod control and rod position system (i.e., RGL system) can interact with the terminal device to enable the terminal device to obtain primary and secondary loop temperature difference, real-time position of R rod, G rod insertion time, rod action indication signal, rod locking indication signal and control rod alarm parameter, etc. It should be noted that the control rod includes a temperature control rod (i.e., R rod) and a power control rod (i.e., G rod). Among them, the primary and secondary loop temperature difference is used to evaluate the temperature difference between the primary loop and the secondary loop; the rod action indication signal is used to indicate whether the control rod is in action; and the rod locking indication signal is used to indicate that the control rod has been locked.

[0052] The nuclear sampling system (i.e., REN system) can interact with the terminal device to enable the terminal device to obtain primary loop boron concentration, etc.

[0053] The core measurement system (i.e., the RIC system) can realize information interaction with the terminal device, so that the terminal device obtains the core xenon poisoning concentration and other data. The core xenon poisoning concentration is a parameter for evaluating the degree of xenon poisoning of the reactor.

[0054] Step S20 includes determining important display parameters and preset display parameters according to the real-time monitoring data; wherein, the preset display parameters include real-time axial power deviation, continuous parameters, axial power deviation influence parameters, auxiliary function parameters and control rod operation area. In this step, the preset display parameters can be determined by recording the real-time monitoring data, and the important display parameters can also be calculated based on the real-time monitoring data, so that the operator does not need to perform manual calculation, which not only improves the efficiency, but also reduces the risk of human error.

[0055] In some embodiments, the continuous parameters include at least one of a nuclear power change graph, an R-rod position change graph and an axial power deviation change graph; the axial power deviation influence parameters include at least one of current nuclear power, primary-secondary loop temperature difference, primary loop boron concentration and core xenon poisoning; and at least one of G-rod insertion time, super run graph time, control rod action parameter and control rod alarm parameter. In addition, the control rod alarm parameter includes but is not limited to R-rod group low-low-low insertion limit alarm and R-rod group low travel limit alarm and other alarm information.

[0056] Specifically, the nuclear power change graph can be presented in the form of a curve graph. Understandably, by recording the historical data of nuclear power, the nuclear power change graph can be fitted based on the historical data; the R-rod position change graph can be presented in the form of a line graph, and the R-rod position change graph can be obtained by fitting the historical data of the real-time position of the R-rod position; the axial power deviation change graph includes four axial power deviation change curves corresponding to four measurement channels respectively, and each axial power deviation change curve can be obtained by fitting the historical data of the axial power deviation measurement values of the corresponding channel.

[0057] This embodiment summarizes the parameters from different control systems such as nuclear power, R-rod position and axial power deviation, and represents the historical data in the form of a graph, which not only avoids the operator to operate multiple systems in turn, but also facilitates the operator to analyze the working condition of the reactor according to the change trend of the continuous parameters, and the operator can also obtain the parameters from different control systems such as current nuclear power, primary loop boron concentration, core xenon poisoning, super run graph time and control rod action parameter without operating multiple systems, which reduces the work burden of the operator and helps to improve the operation efficiency.

[0058] In some embodiments, the important display parameter comprises a worst channel axial power deviation; accordingly, the worst channel axial power deviation can be determined by: determining an axial power deviation coefficient corresponding to each measurement channel according to the full power reference axial power distribution value and each axial power deviation measurement value; respectively calculating a first difference absolute value of the axial power deviation coefficient and the left limit measurement value and a second difference absolute value of the axial power deviation coefficient and the right limit measurement value in each measurement channel; determining the measurement channel corresponding to the minimum difference absolute value among each first difference absolute value and each second difference absolute value as the worst channel, and determining the axial power deviation measurement value of the worst channel as the worst channel axial power deviation.

[0059] Specifically, the axial power deviation coefficient of each measurement channel can be calculated by the following formula: wherein, represents the axial power deviation coefficient of the kth measurement channel, represents the full power reference axial power distribution value, represents the axial power deviation measurement value of the kth measurement channel. After calculating the axial power deviation coefficients of the four measurement channels, the axial power deviation coefficient of each measurement channel is respectively subtracted from the left limit measurement value and the right limit measurement value corresponding to the measurement channel and the absolute value is calculated, i.e. the first difference absolute value and the second difference absolute value of each measurement channel are obtained. Taking the 1st measurement channel as an example, assuming that the axial power deviation coefficient of the 1st measurement channel is A1, the left limit measurement value is B1, and the right limit measurement value is C1, then the first difference absolute value of the 1st measurement channel can be calculated as |A1-B1|, and the second difference absolute value can be calculated as |A1-C1|. For example, the 2nd measurement channel, the axial power deviation coefficient of the 2nd measurement channel is A2, the left limit measurement value is B2, and the right limit measurement value is C2, then the first difference absolute value of the 1st measurement channel can be calculated as |A2-B2|, and the second difference absolute value can be calculated as |A2-C2|. After determining the first difference absolute value and the second difference absolute value of each measurement channel, the absolute values of all first difference absolute values and second difference absolute values are compared, the measurement channel corresponding to the first difference absolute value or the second difference absolute value with the smallest absolute value is determined as the worst channel, and finally the axial power deviation measurement value measured by the worst channel is determined as the worst channel axial power deviation.

[0060] In this embodiment, the terminal device automatically calculates the axial power deviation measurement value of each measurement channel by software, so that the operator does not need to manually record and calculate to determine which measurement channel is the worst channel, effectively improving the work efficiency and reducing the risk of human error.

[0061] In some embodiments, the important display parameter further comprises a left limit value and a right limit value; correspondingly, the left limit value and the right limit value can be determined in the following manner: determining the left limit value as the left limit measurement value corresponding to the worst channel; determining the right limit value as the right limit measurement value corresponding to the worst channel.

[0062] Specifically, the left limit value represents the minimum allowable value of the real-time axial power deviation of each measurement channel, and the closer the real-time axial power deviation is to the left limit value, the more serious the deviation of the real-time axial power deviation is. The operator needs to observe the difference between the real-time axial power deviation and the left limit value and perform corresponding response measures to avoid the real-time axial power deviation falling below the left limit value. The right limit value represents the maximum allowable value of the real-time axial power deviation, and the closer the real-time axial power deviation is to the right limit value, the more serious the deviation of the real-time axial power deviation is. The operator needs to observe the difference between the real-time axial power deviation and the right limit value and perform corresponding response measures to avoid the real-time axial power deviation rising above the right limit value.

[0063] In this embodiment, the left limit value and the right limit value are started by software, so that the operator can determine the left limit value and the right limit value of the worst channel without operating the operation monitoring system, so as to quickly judge how much the real-time axial power deviation deviates from the limit value, and to make corresponding processing measures to maintain the stable operation of the reactor.

[0064] In some embodiments, the important display parameter further comprises a left line value and a right line value; correspondingly, the left line value and the right line value can be determined in the following manner: calculating an operation reference value according to the full-power reference axial power distribution value and the worst channel axial power deviation; determining the left line value as the difference between the operation reference value and the left line compensation value; determining the right line value as the sum of the operation reference value and the right line compensation value.

[0065] Specifically, the expression of the operation reference value can be wherein, represents the operation reference value, represents the full-power reference axial power distribution value, represents the worst channel axial power deviation. The left line value is the downward early warning line of the real-time axial power deviation, and when the real-time axial power deviation falls below the left line value, it means that the real-time axial power deviation has entered the early warning zone. At this time, the operator needs to be vigilant and perform related operations to make the real-time axial power deviation rise to get out of the early warning zone. The right line value is the upward early warning line of the real-time axial power deviation, and when the real-time axial power deviation falls above the right line value, it means that the real-time axial power deviation has entered the early warning zone. At this time, the operator needs to be vigilant and perform related operations to make the real-time axial power deviation fall to get out of the early warning zone.

[0066] In the embodiment, the terminal device automatically calculates the left line value and the right line value by software, so that the operator can intuitively observe the distance between the real-time axial power and the line value, so as to make intervention in advance, which plays a positive role in maintaining the stable operation of the reactor.

[0067] The step S30 comprises outputting the preset display parameters and the important display parameters. In the step, the terminal device can output the preset display parameters and the important display parameters to the display device, the human-computer interaction unit or the mobile terminal, so that the operator can obtain the preset display parameters and the important display parameters without operating the interfaces of multiple control systems, thereby effectively improving the operation efficiency and reducing the workload of the operator.

[0068] In some embodiments, in the step S30, the preset display parameters and the important display parameters can also be displayed by outputting the preset display parameters and the important display parameters to the human-computer interaction unit to display the preset display parameters and the important display parameters through the human-computer interaction unit. Specifically, the human-computer interaction unit can comprise a display screen or other device capable of displaying data parameters, which can intuitively display the preset display parameters and the important display parameters for the operator.

[0069] Further, in order to make the display of the preset display parameters and the important display parameters more organized and convenient for the operator to observe, in some embodiments, the step S30 further comprises regionally displaying each display parameter, so that each parameter in each preset display parameter is allocated to a different region based on different categories, and the important display parameters are set in a preset region. Specifically, as shown in FIG. 2, the continuous parameters can be displayed on the left region of the display screen, the important display parameters are displayed in the middle position of the display screen, and the axial power deviation influence parameters and the auxiliary function parameters are uniformly distributed on the screen above, below and to the right of the important display parameter display region. In this way, the important display parameters in the middle position are more eye-catching, and can be more easily observed by the operator.

[0070] In the related art, the important display parameters are generally displayed through multiple operating graphs as shown in FIG. 3, and sometimes the operator needs to observe up to 20 or more operating graphs to understand the important display parameters. In order to enable the operator to more intuitively observe the relationship between the worst channel axial power deviation and the left limit value, the right limit value, the left line value and the right line value, in some embodiments, the important display parameters can also be displayed by displaying the important display parameters through a one-coordinate manner; wherein the important display parameters comprise the worst channel axial power deviation, the left limit value, the right limit value, the left line value and the right line value.

[0071] Specifically, referring to FIG. 4, cursor 1 represents the left limit value, cursor 2 represents the left line value, cursor 3 represents the right line value, cursor 4 represents the right limit value, and reference numeral 5 represents the worst channel axial power deviation. Understandably, when the operator observes that reference numeral 5 is located in the interval between cursor 2 and cursor 3, it can be determined that the worst channel axial power deviation is normal, when reference numeral 5 is located in the interval between cursor 1 and cursor 2, it can be determined that the worst channel axial power deviation has entered the early warning interval of being too small, and the axial power needs to be moderately increased, when reference numeral 5 is located to the left of cursor 1, it can be determined that the worst channel axial power deviation has deviated from the control, and relevant measures need to be immediately taken to increase the axial power, when reference numeral 5 is located in the interval between cursor 3 and cursor 4, it can be determined that the worst channel axial power deviation has entered the early warning interval of being too large, and the axial power needs to be moderately decreased, and when reference numeral 5 is located to the right of cursor 4, it can be determined that the worst channel axial power deviation has deviated from the control, and emergency measures need to be immediately taken to decrease the axial power as soon as possible to ensure the safety of the reactor.

[0072] The embodiment further helps the operator to more intuitively and conveniently observe the relationship between the important display parameters in the form of the one-dimensional display graph and the cursor, so that when the worst channel axial power deviation is abnormal, the operator can quickly execute relevant response measures, which helps to improve the safety and stability of the reactor.

[0073] In some embodiments, the important display parameters can also be displayed by generating a running graph according to the dynamic data of the important display parameters. Specifically, the running graph generated according to the dynamic data of the important display parameters is similar to the running graph shown in FIG. 3, which is adapted to the observation habits of some operators, and enables the operator to conveniently and intuitively observe the historical change trend of each parameter in the important display parameters, so that the operator can analyze the working condition change trend of the reactor in combination with the historical change trend of these parameters, provide important data support for the preventive measures to avoid abnormal changes of the axial power deviation, and help to improve the stability of the reactor.

[0074] In some embodiments, as shown in FIG. 1, the preset display parameters further include a control rod operation area; accordingly, the nuclear power plant axial power deviation monitoring method further includes: S40, acquiring a rod operation instruction, and inputting a rod control signal of a rod position to a rod control rod position system according to the rod operation instruction.

[0075] Specifically, the human-computer interaction unit also displays a control rod operation area, so that the operator can determine the real-time state of the G rod and the R rod by observing the control rod operation area, and input relevant rod operation instructions to control the state of the control rod. Further, the human-computer interaction unit can also include a mouse, a keyboard, a button, and the like, and the operator can preset the operation of the rod operation area through the human-computer interaction unit, so as to input corresponding rod operation instructions. When the terminal device obtains the rod operation instructions, the rod control rod position system inputs the rod control signal of the control rod position according to the rod operation instructions. After receiving the rod control signal, the rod control rod position system controls the step number or control mode of the control rod based on the rod control signal. In addition, the control rod operation area can be allocated at the upper right and lower right of the screen according to the type of the control rod, for example, the G rod operation area is allocated at the upper right of the screen, and the R rod operation area is allocated at the lower right of the screen, and a certain distance (such as 2-4 cm) is maintained to avoid misoperation.

[0076] In some embodiments, the display interface of the control rod operation area can also be designed to be consistent with the original display interface of the rod control rod position system, and of course, the operation logic of the control rod operation area can also be designed to be consistent with the original display interface of the rod control rod position system. In this way, the operator can control the control rod as if operating the original rod control rod position system, so that the operator does not need to be familiar with a new operation interface, which helps to reduce the risk of misoperation and misreading of the operator.

[0077] As shown in FIG. 5, the present application provides a terminal device, which includes a memory, a processor, and a computer program stored in the memory and executable on the processor. When the processor executes the computer program, the steps of the nuclear power plant axial power deviation monitoring method in the embodiment of the present application are implemented.

[0078] As shown in FIG. 6, the present application provides a nuclear power plant axial power deviation monitoring system, which includes a human-computer interaction unit and a terminal device provided by the embodiment of the present application. The human-computer interaction unit is used to display preset display parameters and important display parameters.

[0079] The embodiments in the specification are described in a progressive manner, and each embodiment focuses on the difference from other embodiments. The same or similar parts of each embodiment can be referred to each other. For the device disclosed in the embodiments, since it corresponds to the method disclosed in the embodiments, the description is relatively simple, and the related parts can be referred to the method part.

[0080] Those skilled in the art will further appreciate that the units and algorithm steps of the examples described in connection with the embodiments disclosed herein can be implemented in electronic hardware, computer software, or any combination thereof. To clearly illustrate this interchangeability of hardware and software, various examples have been described generally in terms of their functionality. Whether such functionality is implemented as hardware or software depends upon the particular application and design constraints imposed on the overall system. Skilled artisans can implement the described functionality in varying ways for each particular application, but such implementation decisions should not be interpreted as causing a departure from the scope of the present application.

[0081] The steps of a method or algorithm described in connection with the embodiments disclosed herein can be embodied directly in hardware, in a software module executed by a processor, or in a combination of the two. A software module can reside in RAM, flash memory, ROM, electrically programmable ROM (EPROM), electrically erasable programmable ROM (EEPROM), registers, hard disk, a removable disk, a CD-ROM, or any other form of storage medium known in the art.

[0082] It can be understood that the above embodiments only express the preferred embodiments of the present application, and the description is more specific and detailed, but it should not be understood as a limitation to the scope of the patent of the present application. It should be noted that for ordinary skilled in the art, the above technical features can be freely combined without departing from the concept of the present application, and several modifications and improvements can be made, which all belong to the protection scope of the present application. Therefore, any equivalent transformation and modification within the scope of the claims of the present application should belong to the scope of the claims of the present application.

Claims

1. A method of monitoring axial power bias in a nuclear power plant, characterized by, The method comprises the following steps: acquiring real-time monitoring data, wherein the real-time monitoring data is from a plurality of nuclear power plant monitoring systems, and the plurality of nuclear power plant monitoring systems comprise at least two of an operation monitoring system, a rod control and rod position system, a nuclear sampling system and a reactor core measurement system; determining important display parameters and preset display parameters according to the real-time monitoring data, wherein the preset display parameters comprise a real-time axial power deviation, a continuous parameter, an axial power deviation influence parameter and an auxiliary function parameter; outputting the preset display parameters and the important display parameters.

2. The method of claim 1, wherein, The real-time monitoring data comprises a full-power reference axial power distribution value, and axial power deviation measurement values, left limit measurement values and right limit measurement values measured by four measurement channels respectively, and the important display parameters comprise a worst channel axial power deviation; The method of determining important display parameters and preset display parameters according to real-time monitoring data comprises the following steps: determining axial power deviation coefficients corresponding to each measurement channel according to the full-power reference axial power distribution value and each axial power deviation measurement value; calculating first difference absolute values of the axial power deviation coefficients and the left limit measurement values in each measurement channel and second difference absolute values of the axial power deviation coefficients and the right limit measurement values in each measurement channel respectively; determining a measurement channel corresponding to a minimum difference absolute value among each first difference absolute value and each second difference absolute value as a worst channel, and determining an axial power deviation measurement value of the worst channel as the worst channel axial power deviation.

3. The method of claim 2, wherein, The important display parameters further comprise left limit values and right limit values; The method of determining important display parameters and preset display parameters according to real-time monitoring data further comprises the following steps: determining a left limit measurement value corresponding to the worst channel as the left limit value; determining a right limit measurement value corresponding to the worst channel as the right limit value.

4. The method of claim 2, wherein, The real-time monitoring data further comprises preset left line compensation values, preset right line compensation values and a current nuclear power, and the important display parameters further comprise left line values and right line values; The method of determining important display parameters and preset display parameters according to real-time monitoring data further comprises the following steps: calculating an operation reference value according to the full-power reference axial power distribution value and the worst channel axial power deviation; determining a difference between the operation reference value and the left line compensation value as the left line value; determining a sum of the operation reference value and the right line compensation value as the right line value.

5. The method of claim 4, wherein, An expression of the operation reference value is: ； wherein, denotes the operating reference value, representing the full power reference axial power profile value, wherein the worst channel axial power deviation is represented.

6. The method of monitoring axial power bias in a nuclear power plant of claim 1, wherein, The preset display parameters further comprise a control rod operation region; The method of monitoring axial power deviation of a nuclear power plant further comprises the following steps: acquiring a rod operation instruction, and inputting a rod control signal of a control rod position to the rod control and rod position system according to the rod operation instruction.

7. The method of monitoring axial power bias of a nuclear power plant according to any one of claims 1 to 6, characterized in that, The continuous parameter comprises at least one of a nuclear power change graph, a R rod position change graph and an axial power deviation change graph; The axial power deviation influence parameter comprises at least one of a current nuclear power, a primary and secondary loop temperature difference, a primary loop boron concentration and a reactor core xenon poison. The auxiliary function parameter includes at least one of a G-rod insertion time, a rod motion indication signal, a rod lock indication signal, an overrunning graph time, a control rod motion parameter, and a control rod alarm parameter.

8. The method of monitoring axial power bias of a nuclear power plant of claim 7, wherein, The outputting the preset display parameter and the important display parameter comprises: The preset display parameter and the important display parameter are output to a human-computer interaction unit to display the preset display parameter and the important display parameter through the human-computer interaction unit.

9. A terminal device comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, characterized in that, The processor implements the steps of the nuclear power plant axial power deviation monitoring method according to any one of claims 1 to 8 when executing the computer program.

10. A nuclear power plant axial power offset monitoring system, characterized by, Comprise: The terminal device according to claim 9; And A human-computer interaction unit is configured to display the preset display parameter and the important display parameter.

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