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

Description

[0001] The present invention relates to the technical field of reactor control and protection, in particular to a method and system for monitoring nuclear power plant axial power deviation, and a terminal device. DESCRIPTION OF RELATED ART

[0002] The core axial power deviation represents the uniformity of axial power distribution, and is a key parameter to be controlled during operation. There are many factors affecting the axial power deviation. At present, the amount of information that operators need to pay attention to is large, and all kinds of information are scattered in many different nuclear power plant monitoring systems. Because there are many interventions for the axial power deviation, there are many operation pages that need to be called for the adjustment of axial power deviation, which leads to very complicated operation and low operation efficiency. The operator also needs to manually collect and record some important data (such as G-rod insertion time, etc.), and some important parameter affecting the axial power deviation need to be calculated manually by the operator, resulting in that the operator needs to spend a certain amount of time to complete the recording and calculation, and there may be recording errors or calculation errors, resulting in a greater risk of human error, which is not conducive to the stable operation of the reactor. BRIEF SUMMARY OF THE INVENTION

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

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

[0005] 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 position indication system, a nuclear sampling system, and a reactor core measurement system;

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

[0007] Outputting the preset display parameter and the important display parameter.

[0008] Preferably, the real-time monitoring data comprises a full-power reference axial power distribution value, and an axial power deviation measurement value, a left limit measurement value and a right limit measurement value respectively measured by the four measurement channels; the important display parameter comprises the worst channel axial power deviation;

[0009] The determining the important display parameter and the preset display parameter 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] Respectively 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 measurement channel;

[0012] Determining the measurement channel corresponding to the minimum one of 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 worst channel axial power deviation.

[0013] Preferably, the important display parameter further comprise a left limit value and a right limit value;

[0014] The determining the important display parameter and the preset display parameter according to the real-time monitoring data 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 comprises a preset left line compensation value, a preset right line compensation value and current nuclear power, and the important display parameter further comprise a left line value and a right line value;

[0018] The determining the important display parameter and the preset display parameter according to the real-time monitoring data further comprises:

[0019] Calculating an operating reference value according to the full-power reference axial power distribution value and the worst channel axial power deviation;

[0020] Determining a difference between the operating reference value and the preset left line compensation value as the left line value;

[0021] Determining a sum of the operating reference value and the preset right line compensation value as the right line value.

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

[0023] x = (Dpaxref — 0.02) * (0.005 * y + 0.5);

[0024] Where x represents the operating reference value, Dpaxref represents the full-power reference axial power distribution value, and y represents the worst channel axial power deviation.

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

[0026] The method for monitoring nuclear power plant axial power deviation further comprises the following steps:

[0027] Obtaining a rod operation instruction to input a rod control signal for controlling a rod position to a rod control and position indication system according to the rod operation instruction.

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

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

[0030] The auxiliary function parameter comprises at least one of G-rod insertion time, rod action indication signal, rod locking indication signal, exceed scheduled time, control rod action parameter, and control rod alarm parameter.

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

[0032] Outputting the preset display parameter and the important display parameter 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 invention also constructs a terminal device comprising a memory, a processor and a computer program which is stored in the memory and can be operated on the processor, and the processor realizes the steps of the method for monitoring nuclear power plant axial power deviation when executing the computer program.

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

[0035] A 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] By implementing the technical scheme of the invention, the operation mode of monitoring and controlling the axial power deviation can be optimized, an operator can be helped to automatically calculate the important parameter, the operation efficiency can be effectively improved, the workload of the operator is reduced, the human error risk is reduced, and the reactor operation stability is positively improved. BRIEF DESCRIPTION OF THE SEVERAL VIEWS OF THE DRAWINGS

[0038] The present invention will be further described below with reference to the accompanying drawings and embodiments, in which:

[0039] FIG. 1 is a process flow chart of a method for monitoring nuclear power plant axial power deviation in accordance with some embodiments of that present invention;

[0040] FIG. 2 is a display interface of preset display parameter and important display parameter in some embodiments of the present invention;

[0041] FIG. 3 is an operating diagram of axial power deviation for a portion of a measurement channel in some embodiments of that present invention;

[0042] FIG. 4 is a one-dimensional display plot of important display parameter in some embodiments of that invention;

[0043] FIG. 5 is a structural diagram of a terminal device in some embodiments of the present invention;

[0044] FIG. 6 is a block diagram of a system for monitoring nuclear power plant axial power deviation according to some embodiments of that present invention. DETAILED DESCRIPTION OF THE INVENTION

[0045] For a clearer understanding of the technical features, objects, and effects of the present invention, embodiments of the present invention will now be described in detail with reference to the accompanying drawings.

[0046] It should be noted that the flow graphs shown in the figures are only exemplary and do not necessarily include all of the elements and operations / steps, nor are they necessarily performed in the order described. For example, some operations / steps can also be decomposed, while others can be combined or partially combined, so the actual order of execution may change according to the actual situation.

[0047] The block diagrams shown in the figures are merely functional entities and do not necessarily correspond to physically separate entities. That is, these functional entities may be implemented in the form of software, or in one or more hardware modules or integrated circuits, or in different network and / or processor devices and / or microcontroller devices.

[0048] FIG. 1 is a process flow chart of a method for monitoring nuclear power plant axial power deviation according to some embodiments of that present invention. The method is use for an equipment terminal, can optimize an operation mode of monitoring and control that axial power deviation, can help an operator to automatically calculate important parameter, can 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 operation stability of a reactor. The method includes step S10, step S20, and step S30.

[0049] Step S10 includes: 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 include at least two of an operation monitoring system, a rod control and position indication system, a nuclear sampling system and a reactor core measurement system. In this step, the equipment terminal can acquire real-time monitoring data through information interaction with a plurality of nuclear power plant monitoring systems. Further, the real-time monitoring data may include current nuclear power, full-power reference axial power distribution value, exceed scheduled time, preset left line compensation value, preset right line compensation value, temperature difference between the primary loop and the secondary loop, real-time position of the R-rod position, G-rod insertion time, rod action indication signal, rod locking indication signal and control rod alarm parameter, boron concentration of the primary loop, and core xenon poisoning. And the axial power deviation measurement value, the left limit measurement value, the right limit measurement value and other data respectively measured by the four measurement channels.

[0050] The operation monitoring system (that is, the OSS system) can implement information interaction with a terminal device, so that the terminal device acquires the current nuclear power, the full-power reference axial power distribution value, the exceed scheduled time, the preset left line compensation value, and the preset right line compensation value. And the axial power deviation measurement value, the left limit measurement value, the right limit measurement value and other data respectively measured by the four measurement channels. It should be noted that in a nuclear power plant, the OSS system is provided with four axial power measurement channels to detect the axial power deviation of the reactor respectively, and calculate the axial power deviation measurement value, the left limit measurement value and the right limit measurement value corresponding to each channel through an existing algorithm. 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 by operating the OSS system based on the actual operation requirements of the nuclear power plant, and can be generally considered as constants. In addition, the exceed scheduled time refers to the cumulative time that the reactor power exceeds a certain set power area within 12 consecutive hours, which is a parameter used to evaluate whether the reactor operates stably.

[0051] The rod control and position indication system (i.e. RGL system) can realize information interaction with a terminal device, so that the terminal device can obtain the data such as the temperature difference between the primary loop and the secondary loop, the real-time position of the R-rod position, the G-rod insertion time, the rod action indication signal, the rod locking indication signal and the control rod alarm parameter. It should be noted that the control rods include temperature control rod (i.e., R-rod) and power control rod (i.e., G-rod).The temperature difference between the primary loop and the secondary loop 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 acting; the rod locking indication signal is used to indicate that the control rod is locked.

[0052] The nuclear sampling system (i.e. REN system) can realize information exchange with a terminal device, so that the terminal device can obtain the data such as the boron concentration of the primary loop.

[0053] The reactor core measurement system (i.e., RIC system) can realize information interaction with a terminal device, so that the terminal device can obtain the data such as the core xenon poisoning. The core xenon poisoning is a parameter to evaluate the degree of xenon poisoning in the reactor.

[0054] Step S20 includes: determining important display parameter and preset display parameter according to the real-time monitoring data, wherein the preset display parameter includes real-time axial power deviation, continuous parameter, axial power deviation influence parameter, auxiliary function parameter and control rod operating region. In this step, the preset display parameter can be determined by recording the real-time monitoring data, and the important display parameter can be calculated based on the real-time monitoring data, so that the operator does not need to perform manual calculation, thereby not only improving the efficiency, but also reducing the risk of human error.

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

[0056] Specifically, the nuclear power variation graph can be presented in the form of a curve graph, and it is understandable that the nuclear power variation graph can be obtained by fitting based on the historical data by recording the historical data of the nuclear power; the R-rod position variation graph can be presented in the form of a line graph, and the R-rod position variation graph can be obtained by fitting the historical data of the real-time position of the R-rod; The axial power deviation variation graph contains four axial power deviation variation curves corresponding to the four measurement channels one by one, and each axial power deviation variation curve can be obtained by fitting the historical data of the axial power deviation measurement value of the corresponding channel.

[0057] In this embodiment, the parameter from different control systems, such as the nuclear power, the R-rod position and the axial power deviation, are summarized, and the historical data thereof is represented in the form of a graph, so that not only can an operator be prevented from operating a plurality of systems in turn, but also the operator can conveniently analyze the working condition of the reactor according to the change variation of the continuous parameter. The operator can obtain the parameter from different control systems, such as the current nuclear power, the boron concentration of the primary loop, the core xenon poisoning, the exceed scheduled time and the control rod action parameter, without operating multiple systems, which reduces the workload of the operator and helps to improve the operation efficiency.

[0058] In some embodiments, the important display parameter includes a worst channel axial power deviation. Accordingly, the worst channel axial power deviation can be determined by the following methods: determining the axial power deviation coefficient corresponding to each measurement channel respectively according to a full-power reference axial power distribution value and each axial power deviation measurement value; Respectively 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 measurement channel; Determining the measurement channel corresponding to the minimum difference absolute value in 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 for each of the measurement channels can be calculated by the following formula: Dpax(ref)[k] = Dpaxref * Prk / 100 ;Where Dpax(ref)[k] is the axial power deviation coefficient of the kth measurement channel, Dpaxref is the full-power reference axial power distribution value, and Prk is the axial power deviation measurement value of the kth measurement channel. After the axial power deviation coefficients of the four measurement channels are calculated, the axial power deviation coefficients of each measurement channel are respectively deviated from the left limit measurement value and the right limit measurement value of the corresponding measurement channel, and the absolute values are calculated to obtain a first difference absolute value and a second difference absolute value of each measurement channel. Taking the first measurement channel as an example, Assuming that the axial power deviation coefficient of the first measurement channel is Al, the left limit measurement value is Bl, and the right limit measurement value is Cl, it can be calculated that the first difference absolute value of the first measurement channel is | Al-Bl |, and the second difference absolute value is | Al-Cl |.If the axial power deviation coefficient of the second measurement channel is A2, the left limit measurement value is B2, and the right limit measurement value is C2, then it can be calculated that the first difference absolute value of the second measurement channel is | A2-B2 |, and the second difference absolute value is | A2-C2 |;After the first difference absolute value and the second difference absolute value of each measurement channel are determined, Compare the magnitudes of all the first difference absolute values and the second difference absolute values, and 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, Finally, the axial power deviation measured value of 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 values of each measurement channel through software, so that an operator can determine which measurement channel is the worst channel without taking notes or calculating, thereby effectively improving the work efficiency and reducing the risk of human error.

[0061] In some embodiments, the important display parameter further includes a left limit value and a right limit value; accordingly, the left limit value and the right limit value may be determined by determining the left limit measurement value corresponding to the worst channel as the left limit value and determining the right limit measurement value corresponding to the worst channel as the right limit value.

[0062] Specifically, the left limit value represents the minimum allowable value of the real-time axial power deviation of each measurement channel. As the real-time axial power deviation approaches the left limit, its deviation becomes more severe. The operator needs to observe the difference between the real-time axis power deviation and the left limit value and implement corresponding countermeasures to prevent the real-time axis power deviation from decreasing to the left limit value. The right limit value represents the maximum allowable value of the real-time axial power deviation. As the real-time axial power deviation approaches the right limit, its deviation becomes more severe. The operator needs to observe the difference between the real-time axis power deviation and the right limit value and take corresponding countermeasures to prevent the real-time axle power deviation from rising to the right limit value.

[0063] In the embodiment, the left limit value and the right limit value are started by software, so that an operator can determine the left limit value and the right limit value of the worst channel without operating an operation monitoring system, so that the operator can quickly judge how close the real-time axial power deviation is to the limit value, and can take corresponding treatment measures to maintain the stable operation of the reactor.

[0064] In some embodiments, the important display parameter further include a left line value and a right line value; accordingly, the left line value and the right line value may be determined by the following methods: calculating an operating reference value based on the full-power reference axial power distribution value and the worst channel axial power deviation, determining a difference between the operating reference value and a preset left line compensation value as the left line values, and determining a sum of the operating reference value and a preset right line compensation value as the right line value.

[0065] Specifically, the expression of the operating reference value may be x = (Dpaxref — 0.02) * (0.005 * y + 0.5) , where X represents the operating reference value, Dpaxref represents the full-power reference axial power distribution value, and y represents the worst channel axial power deviation. The left line value is the decreasing warning line of the real-time axial power deviation. When the real-time axial power deviation decreases to be less than the left line value, it indicates that the real-time axial power deviation has entered the early warning area. At this time, the operator needs to be alert and perform corresponding operations to increase the real-time axial power deviation so as to get out of the early warning area. The right line value is the rising early warning line of the real-time axial power deviation. When the real-time axial power deviation is reduced to be greater than the right line value, it indicates that the real-time radial power deviation has entered the early warning area. At this time, the operator needs to be alert and perform corresponding operations to reduce the real-time radial power deviation so as to get out of the early warning area.

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

[0067] Step S30 includes: outputting a preset display parameter and an important display 12 parameter. In the step, the terminal device can output the preset display parameter and the important display parameter to a display equipment, a human-computer interaction unit or a mobile terminal, so that an operator can obtain the preset display parameter and the important display parameter without operating interfaces of a plurality of control systems, thereby effectively improving the operation efficiency and reducing the workload of the operator.

[0068] In some embodiments, in step S30, the preset display parameter and the important display parameter may also be displayed in the following manner: outputting the preset display parameter and the important display parameter to a human-computer interaction unit, so as to display the preset display parameter and important display parameter through the human-computer interaction unit .Specifically, the human-computer interaction unit may include a device capable of displaying data parameter, such as a display screen, which can visually display preset display parameter and important display parameter for the operator.

[0069] Further, in order to make the display of the preset display parameter and the important display parameter more organized and convenient for the operator to observe, in some embodiments, step S30 further includes: displaying the display parameters in different areas, so that each parameter in the preset display parameter is allocated to different areas for display based on different categories. And set the important display parameter in a preset area. Specifically, as shown in FIG. 2, the continuous parameter may be displayed on the left area of the display screen, the important display parameter may be displayed in the middle position of the display screen, and the axial power deviation influence parameter and the auxiliary function parameter are evenly distributed on the screen above, below and to the right of the important display parameter display area, so that the important display parameter in the middle position are more noticeable, The change can be more easily observed by the operator.

[0070] In the related art, important display parameter is generally displayed through a plurality of operating diagrams as shown in FIG. 3, and sometimes an operator even needs to observe more than 20 operating diagrams to understand the important display parameter. 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 parameter may also be displayed in the following manner: the important display parameter is displayed in a one-dimensional coordinate manner, wherein the important display parameter includes the worst channel axial power deviation, a left limit value, a right limit value, a left line value, and a 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 mark 5 represents the worst channel axial power deviation. It can be understood that when the operator observes that the mark 5 is located in the interval between the cursor 2 and the cursor 3, it can be determined that the worst channel axial power deviation is normal, when the mark 5 is located in the interval between the cursor 1 and the cursor 2, it can be determined that the worst channel axial power deviation has entered a lower early warning area, and it is necessary to control the axial power to increase moderately, when the mark 5 lies on the left side of the cursor l,It can be determined that the worst channel axial power deviation has deviated from the control, and relevant measures need to be implemented immediately to increase the axial power. When the mark 5 is located in the interval between the cursor 3 and the cursor 4, it can be determined that the worst channel axial power deviation has entered the upper early warning area, and the axial power needs to be controlled to decrease moderately. When the mark 5 is located on the right side of the cursor 4,It can be determined that the axial power deviation of the worst channel has deviated from the control, and emergency measures need to be implemented immediately to reduce the axial power as soon as possible to ensure the safety of the reactor.

[0072] This embodiment can further assist the operator to observe the relationship between the important display parameter more intuitively and conveniently in the form of a one-dimensional display diagram and a cursor, so that when the worst channel axial power deviation is abnormal, the operator can quickly implement relevant countermeasures, which is helpful to improve the safety and stability of the reactor.

[0073] In some embodiments, the important display parameter may also be displayed in the following manner: generating an operating diagram based on the dynamic data of the important display parameter. Specifically, the operating diagram generated according to the dynamic data of the important display parameter is similar to the operating diagram shown in FIG. 3, on one hand, to adapt to the observation habits of some operators, and on the other hand, to enable the operators to conveniently and intuitively observe the historical change variation of each parameter in the important display parameter. It is convenient for the operator to combine the historical change variation of the parameter to analyze the change variation of reactor conditions, which provides important data support for preventive measures to avoid abnormal changes in axial power deviation and helps to improve the stability of the reactor.

[0074] In some embodiments, as shown in FIG. 1, the preset display parameter further includes a control rod operation region; accordingly, the method for monitoring nuclear power plant axial power deviation further includes: S40, acquiring a rod operation instruction to input a rod control signal for controlling the rod position to the rod control and position indication system according to the rod operation instruction.

[0075] Specifically, the human-computer interaction unit also displays control rod operation regions, so that the operator can determine the real-time states of the G-rod and the R-rod by observing the control rod operation region, thereby inputting relevant rod operation instruction to control the States of the control rod. Furthermore, the human-computer interaction unit can also includes components such as a mouse, a keyboard, a key and the like, and an operator can perform preset operation on the rod operation region through the human-computer interaction unit so as to input a corresponding rod operation instruction, and can input a rod control signal for controlling the rod position to the rod control and position indication system according to the rod operation instruction obtained from the terminal device, After receiving the rod control signal, the rod control and position indication system controls the number of steps or the control mode of the control rod based on the rod control signal. In addition, the control rod operation region can be allocated at the upper right and lower right of the screen according to the type of control rod, for example, the G-rod operation region is allocated at the upper right of the screen, and the R-rod operation region is allocated at the lower right of the display, and a certain distance (such as 2 ~ 4 cm) is kept to avoid misoperation.

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

[0077] As shown in FIG. 5, the present invention provides a terminal device, including a memory, a processor, and a computer program stored in the memory and operable on the processor, wherein the processor executes the computer program to implement the method for monitoring nuclear power plant axial power deviation in an embodiment of the present invention.

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

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

[0080] Those skilled in the art will further appreciate that the elements and algorithm steps of the various examples described in connection with the embodiments disclosed herein can be implemented as electronic hardware, computer software, or a combination of both, and that the components and steps of the various examples have been described generally in terms of function in the foregoing description for the purpose of clearly illustrating the interchangeability of hardware and software. Whether these functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. Skilled artisans may implement the described functionality using different methods for each particular application, but such implementations should not be construed as exceeding the scope of the invention.

[0081] The steps of a method or algorithm described in connection with the embodiments disclosed herein may be embodied directly in hardware, in a software module executed by a processor, or in a combination of the two. The software module may be placed in a random access memory (RAM), a memory, a read only memory (ROM), an electrically programmable ROM, an electrically erasable programmable ROM, a register, a 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 represent the preferred embodiments of the present invention, and the description is more specific and detailed, but it should not be understood as limiting the patent scope of the present invention; It should be noted that, for those of ordinary skill in the art, the above technical features can be freely combined, and several modifications and improvements can be made without departing from the concept of the present invention, which all fall within the scope of protection of the present invention; Accordingly, it is intended that all changes and modifications which come within the scope of the appended claims shall be construed accordingly.

Claims

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

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

3. The method for monitoring nuclear power plant axial power deviation according to claim 2, wherein the important display parameter further comprise a left limit value and a right limit value;the determining the important display parameter and the preset display parameter according to the real-time monitoring data further comprises:determining a left limit measurement value corresponding to the worst channel as the left limit value;determining the right limit measurement value corresponding to the worst channel as the right limit value.

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

5. The method for monitoring nuclear power plant axial power deviation according to claim4, wherein the expression of the operating reference value is:x = (Dpaxref — 0.02) * (0.005 * y + 0.5);Where X represents the operating reference value, Dpaxref represents the full-power reference axial power distribution value, and y represents the worst channel axial power deviation.

6. The method for monitoring nuclear power plant axial power deviation of claim 1, wherein the preset display parameter further comprise a control rod operating region;the method for monitoring nuclear power plant axial power deviation further comprises the following steps:obtaining a rod operation instruction to input a rod control signal for controlling a rod position to a rod control and position indication system according to the rod operation instruction.

7. The method for monitoring nuclear power plant axial power deviation according to any one of claims 1 to 6, wherein the continuous parameter comprises at least one of a nuclear power variation graph, an R-rod position variation graph, and an axial power deviation variation graph;the axial power deviation influence parameter comprises at least one of a current nuclear power, a temperature difference between the primary loop and the secondary loop, a boron concentration of the primary loop and a core xenon poisoning ;the auxiliary function parameter comprises at least one of G-rod insertion time, rod action indication signal, rod locking indication signal, schedule exceed scheduled time, control rod action parameter, and control rod alarm parameter.

8. The method for monitoring nuclear power plant axial power deviation according to claim 7, wherein the outputting the preset display parameter and the important display parameter comprises:outputting the preset display parameter and the important display parameter to a human-computer interaction unit so as to display the preset display parameter and the importantdisplay 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 operable on the processor, wherein the processor, when executing the computer program, implements the steps of the method for monitoring nuclear power plant axial power deviation according to claim 1.

10. A system for monitoring nuclear power plant axial power deviation, comprising:a terminal device according to claim 9, andand a human-computer interaction unit is configured to display the preset display parameter and the important display parameter.PCT / CN2025 / 101843A. CLASSIFICATION OF SUBJECT MATTER G21C17 / 00(2006.01)i; G21C17 / 10(2006.01)i According to International Patent Classification (IPC) or to both national classification and IPC B. FIELDS SEARCHED Minimum documentation searched (classification system followed by classification symbols) IPC: G21C17 / - Documentation searched other than minimum documentation to the extent that such documents are included in the fields searched Electronic data base consulted during the international search (name of data base and, where practicable, search terms used) CNTXT, ENTXTC, DWPI, CNKI: Si*, IHSe, ilit, JEM nuclear power, axial, power, deviation, channel, monitor + C. DOCUMENTS CONSIDERED TO BE RELEVANT Category* Citation of document, with indication, where appropriate, of the relevant passages Relevant to claim No. PX CN 118711857 A (SHENZHEN CHINA NUCLEAR POWER DESIGN CO., LTD. et al.) 27 September 2024 (2024-09-27) claims 1-10, description, paragraphs 0048-0078, and figures 1-6 1-10 X A CN 103871511 A (CHINA NUCLEAR POWER ENGINEERING CO., LTD. et al.) 18 June 2014 (2014-06-18) description, paragraphs 0038-0091, and figures 1-3 CN 111724920 A (LINGDONG NUCLEAR POWER CO., LTD. et al.) 29 September 2020 (2020-09-29) entire document 1,6-10 1-10 A CN 112597631 A (CHINA NUCLEAR POWER ENGINEERING CO., LTD. et al.) 02 April 2021 (2021-04-02) entire document 1-10 A CN 108172312 A (GUANGDONG NUCLEAR POWER JOINT VENTURE et al.) 15 June 2018 (2018-06-15) entire document 1-10 | | Further documents are listed in the continuation of Box C. | J | See patent family annex. * Special categories of cited documents: “T” later document published after the international filing date or priority “A” document defining the general state of the art which is not considered date and not in conflict with the application but cited to understand the to be of particular- relevance principle or theory underlying the invention “D” document cited by the applicant in the international application “X” document of particular- relevance; the claimed invention cannot be “E” earlier application orpatent but published on or after the international considered novel or cannot be considered to involve an inventive step filing date when the document is taken alone “L” document which may throw doubts on priority claim(s) or which is “Y” document of particular relevance; the claimed invention cannot be cited to establish the publication date of another citation or other considered to involve an inventive step when the document is special reason (as specified) combined with one or more other such documents, such combination “O” document referring to an oral disclosure, use, exhibition or other being obvious to a person skilled in the art means document member of the same patent family “P” document published prior to the international filing date but later than the priority date claimed Date of the actual completion of the international search 18 September 2025 Date of mailing of the international search report 19 September 2025 Name and mailing address of the ISA / CN China National Intellectual Property Administration (ISA / CN) China No. 6, Xitucheng Road, Jimenqiao, Haidian District, Beijing 100088 Authorized officer Telephone No.PCT / CN2025 / 101843C. DOCUMENTS CONSIDERED TO BE RELEVANTCategory* Citation of document, with indication, where appropriate, of the relevant passages Relevant to claim No. A CN 1043032 A (FRAMATOME SA.) 13 June 1990 (1990-06-13) entire document 1-10 A US 4774049 A (WESTINGHOUSE ELECTRIC CORP.) 27 September 1988 (1988-09-27) entire document 1-10 A (SONG, Jiayu). "KMWMMOgfiW (Non-official translation: Axial Power Deviation and Operational Control of Reactors)" (Science &Technology Vision), 05 May 2015 (2015-05-05), entire document 1-10INTERNATIONAL SEARCH REPORT Information on patent family membersInternational application No.PCT / CN2025 / 101843Patent document cited in search report Publication date (day / month / year) Patent family member, s) Publication date (day / month / year) CN 118711857 A 27 September 2024 None CN 103871511 A 18 June 2014 None CN 111724920 A 29 September 2020 None CN 112597631 A 02 April 2021 None CN 108172312 A 15 June 2018 None CN 1043032 A 13 June 1990 DE 68906244 DI 03 June 1993 DE 68906244 T2 12 August 1993 US 5158738 A 27 October 1992 JPH 02198392 A 06 August 1990 ZA 898639 B 26 June 1991 ZA 8908639 B 26 June 1991 EP 0369865 Al 23 May 1990 EP 0369865 Bl 28 April 1993 FR 2639141 Al 18 May 1990 FR 2639141 Bl 01 February 1991 KR 900008536 A 04 June 1990 KR 100180718 Bl 15 May 1999 US 4774049 A 27 September 1988 JPS 62245997 A 27 October 1987 ES 2026907 T3 16 May 1992 EP 0243049 A2 28 October 1987 EP 0243049 A3 29 June 1988 EP 0243049 Bl 16 October 1991 KR 870010561 A 30 November 1987 KR 950013236 Bl 26 October 1995

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