Method for identifying an anomaly of an excore neutron probe

Abstract

The embodiment of the application provides a kind of out-of-pile neutron detector's exception identification method, belong to nuclear power technology field.The method comprises: obtaining multiple original currents measured by multiple out-of-pile neutron detectors at the first time;Each original current is modified using the correction factor of the quadrant corresponding to the original current, to obtain the modified current;According to the modified current set of each section, the deviation monitoring parameter value of each section is calculated;If the deviation monitoring parameter value corresponding to the target section is greater than or equal to the target threshold of the target section, it is determined that the reactor core or the out-of-pile neutron detector has an abnormality at the target section;Determine whether the reactor core has an abnormality at the target section by the reactor core power distribution measurement method;If the reactor core does not have an abnormality at the target section, it is determined that the out-of-pile neutron detector has an abnormality at the target section.The embodiment of the application can accurately locate the abnormal position of the out-of-pile neutron detector.

Description

Technical Field

[0001] This application relates to the field of nuclear power technology, and in particular to an anomaly identification method for an external neutron detector. Background Technology

[0002] External neutron detectors are typically located outside the reactor core and evenly distributed around it. These detectors are used to measure core power. When measuring core power, the linear relationship between the axial power deviation of the reactor core and the external neutron detectors is established experimentally, and thermal power measurement experiments are used to obtain correction coefficients for the external detectors. The external nuclear power is then recovered from the corrected external detector signals to obtain the power in each quadrant of the reactor core. Algorithms are then used to determine whether the power in each radial quadrant of the reactor core is tilted or whether the signals from all external detectors in that quadrant are abnormal. Therefore, it is impossible to accurately locate the axial position of any abnormality in the reactor core or the axial position of any abnormality in any external neutron detector within a quadrant. Summary of the Invention

[0003] The main objective of this application is to propose an anomaly identification method for an external neutron detector, which accurately locates the axial position where an anomaly occurs by judging the core power at each axial height in the reactor core.

[0004] To achieve the above objectives, a first aspect of this application proposes an anomaly identification method for an external neutron detector. The external neutron detector is uniformly disposed outside the reactor core, which includes i cross-sections, each cross-section comprising k symmetrically distributed quadrants, where i is a positive integer and k is an integer greater than 1. The method includes:

[0005] Multiple raw currents are acquired at the first moment by multiple external neutron detectors, which are located outside the reactor. The multiple raw currents include the output currents measured by the external neutron detectors in each quadrant of each cross section.

[0006] Each original current is corrected using the correction coefficient of the quadrant corresponding to the pre-acquired original current to obtain the corrected current corresponding to each original current. The corrected currents corresponding to the original currents located in the same cross section belong to the same set of corrected currents.

[0007] Based on the corrected current set corresponding to each cross section, the parameter values ​​of the deviation monitoring parameters corresponding to each cross section are calculated;

[0008] If the parameter value of the deviation monitoring parameter corresponding to the target section is greater than or equal to the target threshold corresponding to the target section among the i sections, it is determined that there is an anomaly in the reactor core at the target section or that there is an anomaly in the external neutron detector at the target section;

[0009] The presence of anomalies in the reactor core at the target cross-section is determined by measuring the core power distribution.

[0010] If there is no anomaly in the reactor core at the target cross-section, then it is determined that there is an anomaly in the external neutron detector at the target cross-section.

[0011] In some embodiments, prior to acquiring multiple raw currents measured by multiple off-pile neutron detectors, the method further includes:

[0012] Multiple calibration currents are acquired at a preset calibration time by measuring multiple off-pile neutron detectors. The multiple calibration currents include the output currents measured by the off-pile neutron detectors in each quadrant of each cross section.

[0013] Perform the following processing on each section;

[0014] The average value of the calibration current corresponding to the cross section is calculated to obtain the first average current corresponding to the cross section;

[0015] For each quadrant of the cross section, the correction coefficient for that quadrant is calculated based on the mean current corresponding to the cross section and the calibration current corresponding to the quadrant.

[0016] In some embodiments, calculating the parameter value of the deviation monitoring parameter corresponding to each cross-section based on the correction current set corresponding to each cross-section includes:

[0017] The mean value of the corrected current in the corrected current set corresponding to each cross section is calculated to obtain the second mean current corresponding to the cross section;

[0018] For each corrected current in the corrected current set corresponding to the cross section, the following steps are performed: obtaining the absolute value of the difference between the corrected current and the second average current; taking the ratio of the absolute value to the second average current as a first value; and taking the product of the first value and the target power as a second value, where the target power is the thermal power measured on the reactor core at the first moment.

[0019] The average value of the deviation monitoring parameter corresponding to the cross section is obtained by calculating the mean value of the second value corresponding to each of the corrected currents.

[0020] In some embodiments, after correcting each original current using a correction coefficient for the quadrant corresponding to the pre-acquired original current to obtain a corrected current for each original current, and before determining that the reactor core has an anomaly if the parameter value of the deviation monitoring parameter corresponding to the cross-section is greater than or equal to the target threshold corresponding to the cross-section, the method further includes:

[0021] The sum of the corrected currents corresponding to each of the original currents is taken as the third value;

[0022] The ratio of the third value to the fourth value is taken as the fifth value, where the fourth value is the product of i and k;

[0023] For each of the aforementioned sections, the following processing is performed:

[0024] The target threshold corresponding to the cross section is determined based on the ratio of the fifth value to the second average current, wherein the second average current is the average value of each corrected current in the corrected current set corresponding to the cross section.

[0025] In some embodiments, after calculating the parameter value of the deviation monitoring parameter corresponding to each cross-section based on the correction current set corresponding to each cross-section, the method further includes:

[0026] If the deviation monitoring parameter value corresponding to each of the i cross sections is less than the target threshold corresponding to the cross section, then it is determined that there is no abnormality in the reactor core and the external neutron detector.

[0027] In some embodiments, after determining that an anomaly exists in the reactor core at the target cross-section or an anomaly exists in the external neutron detector at the target cross-section if the parameter value of the deviation monitoring parameter corresponding to the target cross-section is greater than or equal to the target threshold corresponding to the target cross-section, the method further includes:

[0028] An early warning is issued based on the target cross-section, and the deviation monitoring parameters corresponding to the target cross-section are output.

[0029] To achieve the above objectives, a second aspect of this application provides an anomaly detection device for an external neutron detector. The external neutron detector is uniformly disposed outside the reactor core, which includes i cross-sections, each cross-section comprising k symmetrically distributed quadrants, where i is a positive integer and k is an integer greater than 1. The device includes:

[0030] A current acquisition module is used to acquire multiple raw currents measured by multiple external neutron detectors at a first moment. The external neutron detectors are located outside the reactor. The multiple raw currents include the output current measured by the external neutron detectors in each quadrant of each cross section.

[0031] The current correction module is used to correct each original current using a correction coefficient of the quadrant corresponding to the pre-acquired original current, so as to obtain the corrected current corresponding to each original current. The corrected currents corresponding to the original currents located in the same cross section belong to the same set of corrected currents.

[0032] The parameter calculation module is used to calculate the parameter value of the deviation monitoring parameter corresponding to each cross section based on the correction current set corresponding to each cross section.

[0033] The first judgment module is used to determine whether there is an anomaly in the reactor core at the target cross-section or an anomaly in the external neutron detector at the target cross-section if the parameter value of the deviation monitoring parameter corresponding to the target cross-section is greater than or equal to the target threshold corresponding to the target cross-section.

[0034] The second judgment module is used to determine whether there is an anomaly in the reactor core at the target section by measuring the core power distribution.

[0035] The third judgment module is used to determine that the external neutron detector has an anomaly at the target cross-section if there is no anomaly in the reactor core.

[0036] To achieve the above objectives, a third aspect of this application provides an electronic device, which includes a memory and a processor. The memory stores a computer program, and the processor executes the computer program to implement the anomaly identification method for an external neutron detector described in the first aspect.

[0037] To achieve the above objectives, a fourth aspect of the present application provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the anomaly identification method for an external neutron detector described in the first aspect.

[0038] This application proposes an anomaly identification method, apparatus, electronic equipment, and medium for an external neutron detector. It acquires multiple raw currents measured by multiple external neutron detectors and corrects these raw currents according to the correction coefficients of the quadrants corresponding to the pre-acquired raw currents to obtain corrected currents. This eliminates measurement errors caused by detector location or environmental factors, thereby improving the accuracy of subsequent reactor core anomaly identification. The corrected currents corresponding to raw currents at the same cross-section belong to the same corrected current set. The deviation monitoring parameter value for each cross-section is calculated based on the corrected current set for each cross-section. If the deviation monitoring parameter value for a target cross-section is greater than or equal to the target threshold, it indicates an anomaly in the reactor core at the target cross-section or an anomaly in the external neutron detector at the target cross-section. Further determination of whether an anomaly exists in the reactor core at the target cross-section is made through core power distribution measurement. If no anomaly exists in the reactor core at the target cross-section, the external neutron detector at the corresponding cross-section is determined to be abnormal. In this way, the cross-section where the reactor core anomaly occurs and the corresponding external neutron detector can be accurately located. Attached Figure Description

[0039] Figure 1 This is a flowchart illustrating the anomaly identification method for an external neutron detector provided in an embodiment of this application;

[0040] Figure 2 This is a schematic diagram of the structure of a typical pressurized water reactor nuclear power unit provided in the embodiments of this application;

[0041] Figure 3 This is a schematic diagram of a reactor core provided in an embodiment of this application;

[0042] Figure 4 This is a typical operational margin effect diagram of a hydraulic pressurized reactor in one implementation of an embodiment of this application;

[0043] Figure 5 This is a typical anomaly identification effect diagram of an operating hydraulic pressurized reactor in one implementation of an embodiment of this application;

[0044] Figure 6 This is a schematic diagram of the anomaly identification device for an external neutron detector provided in an embodiment of this application;

[0045] Figure 7 This is a schematic diagram of the hardware structure of the electronic device provided in the embodiments of this application. Detailed Implementation

[0046] To make the objectives, technical solutions, and advantages of this application clearer, the following detailed description is provided in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the scope of this application.

[0047] It should be noted that although functional modules are divided in the device schematic diagram and a logical order is shown in the flowchart, in some cases, the steps shown or described may be performed in a different order than the module division in the device or the order in the flowchart. The terms "first," "second," etc., in the specification, claims, and the aforementioned drawings are used to distinguish similar objects and are not necessarily used to describe a specific order or sequence.

[0048] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this application belongs. The terminology used herein is for the purpose of describing embodiments of this application only and is not intended to limit this application.

[0049] The safe and stable operation of nuclear power plants requires extremely high uniformity of core power distribution. Core radial non-uniformity (such as quadrant power tilt) can be caused by a variety of factors, including local rod position loss of synchronization, fuel element failure, and uneven coolant flow. Therefore, effective monitoring of core radial non-uniformity is crucial to ensuring the safe operation of nuclear power plants.

[0050] External neutron detectors are typically located outside the reactor core and evenly distributed around it. These detectors are used to measure core power. When measuring core power, the linear relationship between the axial power deviation of the reactor core and the external neutron detectors is established experimentally, and thermal power measurement experiments are used to obtain correction coefficients for the external detectors. The external nuclear power is then recovered from the corrected external detector signals to obtain the power in each quadrant of the reactor core. Algorithms are then used to determine whether the power in each radial quadrant of the reactor core is tilted or whether the signals from all external detectors in that quadrant are abnormal. Therefore, it is impossible to accurately locate the axial position of any abnormality in the reactor core or the axial position of any abnormality in any external neutron detector within a quadrant.

[0051] Based on this, this application provides an anomaly identification method for an external neutron detector, aiming to solve the problems that existing anomaly identification methods for external neutron detectors cannot accurately locate the anomaly position of the external neutron detector, and that existing methods for calibrating the correction coefficients of external neutron detectors are complex and inefficient. Figure 1This is an optional flowchart of an anomaly identification method for an external neutron detector provided in this application embodiment. This application embodiment mainly acquires multiple raw currents measured by multiple external neutron detectors, and corrects the raw currents according to the correction coefficients of the quadrants corresponding to the pre-acquired raw currents to obtain corrected currents. This eliminates measurement errors caused by factors such as detector location or environment, thereby improving the accuracy of subsequent reactor core anomaly identification. The corrected currents corresponding to the raw currents located at the same cross-section belong to the same corrected current set. The parameter value of the deviation monitoring parameter corresponding to each cross-section is calculated based on the corrected current set corresponding to each cross-section. If the parameter value of the deviation monitoring parameter corresponding to the target cross-section is greater than or equal to the target threshold corresponding to the target cross-section, it indicates that there is an anomaly in the reactor core at the target cross-section or that the external neutron detector at the target cross-section is abnormal. Then, the reactor core power distribution measurement method is used to further determine whether there is an anomaly in the reactor core at the target cross-section. If there is no anomaly in the reactor core at the target cross-section, it is determined that the external neutron detector at the corresponding cross-section is abnormal. In this way, the cross-section where the reactor core anomaly occurs and the corresponding external neutron detector can be accurately located.

[0052] The anomaly identification method for an external neutron detector provided in this application is specifically illustrated through the following embodiments. First, the anomaly identification method for an external neutron detector in this application is described.

[0053] The embodiments of this application can acquire and process relevant data based on artificial intelligence technology. Artificial intelligence (AI) refers to the theories, methods, technologies, and application systems that use digital computers or machines controlled by digital computers to simulate, extend, and expand human intelligence, perceive the environment, acquire knowledge, and use that knowledge to obtain optimal results.

[0054] Foundational technologies for artificial intelligence generally include sensors, dedicated AI chips, cloud computing, distributed storage, big data processing, operating / interactive systems, and mechatronics. AI software technologies mainly encompass computer vision, robotics, biometrics, speech processing, natural language processing, and machine learning / deep learning.

[0055] The anomaly identification method for an external neutron detector provided in this application relates to the field of nuclear power technology. This method can be applied to a terminal, a server, or software running on either a terminal or a server. In some embodiments, the terminal can be a smartphone, tablet, laptop, desktop computer, etc.; the server can be configured as an independent physical server, a server cluster or distributed system composed of multiple physical servers, or a cloud server providing basic cloud computing services such as cloud services, cloud databases, cloud computing, cloud functions, cloud storage, network services, cloud communication, middleware services, domain name services, security services, CDN, and big data and artificial intelligence platforms; the software can be an application implementing the anomaly identification method for an external neutron detector, but is not limited to the above forms.

[0056] This application can be used in a wide variety of general-purpose or special-purpose computer system environments or configurations. Examples include: personal computers, server computers, handheld or portable devices, tablet devices, multiprocessor systems, microprocessor-based systems, set-top boxes, programmable consumer electronics, network PCs, minicomputers, mainframe computers, and distributed computing environments including any of the above systems or devices. This application can be described in the general context of computer-executable instructions executed by a computer, such as program modules. Generally, program modules include routines, programs, objects, components, data structures, etc., that perform specific tasks or implement specific abstract data types. This application can also be practiced in distributed computing environments where tasks are performed by remote processing devices connected via a communication network. In distributed computing environments, program modules can reside in local and remote computer storage media, including storage devices.

[0057] It should be noted that in all specific embodiments of this application, when processing data related to user identity or characteristics, such as user information, user behavior data, user historical data, and user location information, user permission or consent is obtained first. Furthermore, the collection, use, and processing of this data comply with relevant laws, regulations, and standards. In addition, when embodiments of this application require access to sensitive personal information of users, separate permission or consent from the user is obtained through pop-ups or redirection to confirmation pages. Only after obtaining the user's separate permission or consent is the necessary user-related data required for the proper functioning of these embodiments acquired.

[0058] The basic principle of the measurement by the external neutron detector is that the core power, the core neutron flux, the neutron flux at the location of the external neutron detector, and the current of the external neutron detector are approximately proportional. Therefore, the core power level can be monitored based on the current level of the external neutron detector.

[0059] Specifically, the relationship between core power and average core neutron flux rate:

[0060] Under steady-state, burnout-free core conditions, the direct proportionality between core power and average core neutron flux can be simplified to the following equation:

[0061] P = E f ×Σ f ×Φ in ×V (1)

[0062] Where P is the core power; E f for 235 The energy produced by a single fission of the U nucleus can be considered a constant; Σ f Φ is the average macroscopic fission cross section of the reactor core, which can be considered constant under steady-state conditions without considering burnup; in denoted as the average neutron flux rate of the reactor core; V is the core volume, which can be considered a constant.

[0063] Relationship between the external neutron detector current and the neutron flux distribution in the reactor core:

[0064] The relationship between the output current R of the external neutron detector and the core power distribution can be expressed by the following formula:

[0065] R=C×∫ V P(r)×ω(r)dV (2)

[0066] Where C is the sensitivity coefficient of the external neutron detector, which characterizes the conversion relationship between neutron flux rate and current at the detector and can be approximated as a constant; P(r) is the power distribution at position r in the core, which is related to the neutron flux rate distribution in the core. When the operating conditions of the power plant (such as rod position, burnup, xenon poisoning, etc.) change slightly, the power distribution can be considered to remain unchanged; ω(r) is the detector response function at position r in the core, which characterizes the mapping relationship between the power at position r in the core and the external neutron flux rate. When the internal and external structures and the position of the external neutron detector remain unchanged, the response function can be considered to not change with the core operating conditions; and V is the core volume.

[0067] In traditional pressurized water reactors, the core loading scheme, control rod positions, and external neutron detector measurement channels typically follow a radially symmetrical arrangement. Taking a typical pressurized water reactor nuclear power unit as an example, the core loading scheme, control rod arrangement, and external neutron detector channels are arranged radially with 1 / 4 rotational symmetry. Figure 2As shown, the initial enrichment of fuel assemblies at the four marked positions K4, M10, F12, and D6 is the same. The control rods at these four positions are designed and moved synchronously during operation. This design ensures that the core power distribution also meets the 1 / 4 rotational symmetry requirement, and the power of fuel assemblies at symmetrical positions is basically the same.

[0068] The radial path of the external neutron detector's measurement channel also follows a 1 / 4 rotational symmetry principle, and the neutron transport process from the reactor core to the external neutron area is essentially the same. Figure 2 The response functions of the four detectors are basically the same.

[0069] During normal operation, the neutron flux rates at the four off-core neutron detectors are basically the same. Therefore, based on the above characteristics, by integrating the product of the component power and response function in a certain radial quadrant of equation (2) with respect to the volume, we can obtain the relationship between the power in the core quadrant and the output current of the off-core neutron detector at the i-th cross-section of the corresponding quadrant k, that is:

[0070]

[0071] Where k is the number of radial quadrant channels of the external neutron detector, and i is the number of axial segments of the external neutron detector (i.e., the number of axial cross sections of the reactor core).

[0072] And due to the sensitivity coefficient C k,i Because factory specifications may vary, a correction factor G is used to adjust the output current of the external neutron detector to the external displayed power. i k This is used to convert the relationship between the output current of the external neutron detector and the external display power, thereby obtaining the external display power P corresponding to quadrant k. k :

[0073]

[0074] Combining equations (3) and (4), the off-pile power P of quadrant k pairs is... k It can be represented as:

[0075]

[0076] Based on the above reasoning, the power uniformity between radial quadrants of the reactor core can be monitored, commonly referred to as quadrant power tilt (TILT / QPTR) monitoring, which can be expressed by the following formula:

[0077]

[0078] Due to the symmetry principle followed in the core design, the power of each quadrant of the core, ∫vP(r)×ω(r)dV, should be the same or close during normal operation. When the quadrant power tilt TILT is greater than the expected value, it indicates that the core quadrant power may be non-uniform due to local rod position loss of synchronization or uneven temperature distribution. Technicians need to be reminded to verify the non-uniformity of the core quadrant power.

[0079] On the other hand, the sensitivity coefficient C of the same off-pile neutron detector i k No significant changes are expected during normal operation. However, if TILT exceeds expectations, it may be due to C. i k Abnormal changes (such as detector damage or power failure) can cause the output current of the external neutron detector to deviate from expectations, alerting technicians to abnormal performance of the external neutron detector.

[0080] Figure 1 This is a flowchart illustrating the anomaly identification method for an external neutron detector provided in this application embodiment. Please refer to [link / reference]. Figure 1 In this application embodiment, the external neutron detector is uniformly disposed outside the reactor. The reactor core includes i cross sections, each cross section includes k symmetrically distributed quadrants, where i is a positive integer and k is an integer greater than 1. The anomaly identification method of the external neutron detector proposed in this application embodiment may include, but is not limited to, steps S101 to S106.

[0081] Step S101: At a first moment, acquire multiple raw currents measured by multiple off-pile neutron detectors, the multiple raw currents including the raw currents measured by the off-pile neutron detectors in each quadrant of each cross section.

[0082] In this step, the reactor core is divided into i sections based on its axial height, with each section representing an axial height. The entire reactor core comprises k rotationally symmetric quadrants. The first moment is the current moment, and the raw current is the raw output current measured by the external neutron detectors. The distribution of the external neutron detectors is the same as that of the reactor core, i.e., the external neutron detectors are uniformly distributed in the i sections and k quadrants outside the reactor core. The raw current in each quadrant of each section of the reactor core is measured by multiple external neutron detectors.

[0083] For example, such as Figure 3As shown, the reactor core includes cross section 01 and cross section 02, and four quadrants distributed rotationally symmetrically in each cross section. That is, cross section 01 includes quadrants 1a, 1b, 1c, and 1d, and cross section 02 includes quadrants 2a, 2b, 2c, and 2d. The raw current in each quadrant of cross section 01 and cross section 02, measured by the external neutron detector at the current moment, is obtained, that is, a total of eight raw currents are obtained.

[0084] Step S102: Correct each original current using the correction coefficient of the quadrant corresponding to the pre-acquired original current to obtain the corrected current corresponding to each original current. The corrected currents corresponding to the original currents located in the same cross section belong to the same set of corrected currents.

[0085] In this step, each quadrant in each section corresponds to a correction coefficient. Based on the section and quadrant corresponding to the original current, the correction coefficient corresponding to the original current is obtained. The original current is corrected through the correction system corresponding to the original current to obtain the corrected current corresponding to each original current. The corrected currents belonging to the same section are grouped into the same set of corrected currents.

[0086] For example, the reactor core includes a cross section and two quadrants. The first quadrant corresponds to a first correction factor, and the original current in the first quadrant is the first original current. The second quadrant corresponds to a second correction factor, and the original current in the second quadrant is the second original current. The first original current is corrected according to the first correction factor to obtain the first corrected current. The second original current is corrected according to the second correction factor to obtain the second corrected current. The first corrected current and the second corrected current constitute the first corrected current set.

[0087] Step S103: Calculate the parameter value of the deviation monitoring parameter corresponding to each cross section based on the correction current set corresponding to each cross section.

[0088] In this step, due to the symmetry of the radial power of the reactor core, the magnitude of the change of the correction current of the external neutron detector after correction in each quadrant is basically the same over time. Only when the symmetry of the core power changes or the signal of the external neutron detector becomes abnormal will the correction current in each quadrant deviate. Therefore, based on the correction current set composed of correction currents belonging to the same cross section, the deviation monitoring parameter of that cross section is calculated. The parameter value of the deviation monitoring parameter is used to determine whether there is uneven distribution in the reactor core or whether the external neutron detector is abnormal.

[0089] Step S104: If the parameter value of the deviation monitoring parameter corresponding to the target cross section is greater than or equal to the target threshold corresponding to the target cross section, then it is determined that there is an anomaly in the reactor core at the target cross section or that there is an anomaly in the external neutron detector at the target cross section.

[0090] In this step, if any of the i cross sections of the reactor core deviates from the monitoring parameter of the target cross section by a value greater than or equal to the target threshold corresponding to that cross section, it can indicate that there is an anomaly in the reactor core or an anomaly in the external neutron detector.

[0091] For example, the reactor core includes a first cross section and a second cross section. The first cross section corresponds to a first target threshold, and the second cross section corresponds to a second target threshold. If the deviation monitoring parameter of the first cross section is greater than or equal to the first target threshold, and the deviation monitoring parameter of the second cross section is less than the second target threshold, it indicates that the core power measured by the external neutron detector at the first cross section is abnormal. This can indicate that there is uneven core distribution at the first cross section, and can also indicate that the external neutron detector at the first cross section is abnormal.

[0092] Step S105: Determine whether there is an anomaly at the target section of the reactor core by measuring the core power distribution.

[0093] In this step, the existing core power distribution measurement method is used to further determine whether there is an anomaly at the target section of the reactor core. The existing core power distribution measurement method uses a self-powered neutron detector (SPND) in the core neutron detector to measure the quadrant tilt of the reactor core power, that is, to determine whether the power distribution of the reactor core is uniform, thereby determining whether there is an anomaly in the reactor core.

[0094] Step S106: If there is no abnormality in the reactor core at the target cross section, then it is determined that there is an abnormality in the external neutron detector at the target cross section.

[0095] In this step, if it is determined that there is no abnormality in the reactor core at the target cross-section, it indicates that there is an abnormality in the external neutron detector at the corresponding cross-section; if there is an abnormality in the reactor core at the target cross-section, it indicates that the external neutron detector at the corresponding cross-section is operating normally.

[0096] Through steps S101 to S106, the electronic equipment acquires multiple raw currents measured by multiple external neutron detectors and corrects the raw currents according to the correction coefficients of the quadrants corresponding to the pre-acquired raw currents to obtain corrected currents. This eliminates measurement errors caused by factors such as detector position or environment, thereby improving the accuracy of subsequent identification of reactor core anomalies. The corrected currents corresponding to the raw currents at the same cross-section belong to the same set of corrected currents. The parameter value of the deviation monitoring parameter corresponding to each cross-section is calculated based on the set of corrected currents corresponding to each cross-section. If the parameter value of the deviation monitoring parameter corresponding to the target cross-section is greater than or equal to the target threshold corresponding to the target cross-section, it indicates that there is an anomaly in the reactor core at the target cross-section or that there is an anomaly in the external neutron detector at the target cross-section. Then, the reactor core power distribution measurement method is used to further determine whether there is an anomaly in the reactor core at the target cross-section. If there is no anomaly in the reactor core at the target cross-section, it is determined that there is an anomaly in the external neutron detector at the corresponding cross-section. In this way, the cross-section where the reactor core anomaly occurs and the corresponding external neutron detector can be accurately located.

[0097] In some embodiments, before obtaining multiple raw currents through multiple off-pile neutron detectors in step S101, the anomaly identification method for off-pile neutron detectors proposed in this application may include, but is not limited to, the following:

[0098] Multiple calibration currents are acquired at a preset calibration time by measuring multiple off-pile neutron detectors. The multiple calibration currents include the output currents measured by the off-pile neutron detectors in each quadrant of each cross section.

[0099] Perform the following processing on each section;

[0100] The average value of the calibration current corresponding to the cross section is calculated to obtain the first average current corresponding to the cross section;

[0101] For each quadrant of the cross section, the correction coefficient for that quadrant is calculated based on the mean current corresponding to the cross section and the calibration current corresponding to the quadrant.

[0102] The sensitivity of each neutron detector varies. If the raw signals of the off-core neutron detectors in each quadrant are used directly to determine the power tilt of the reactor core in each quadrant, the deviation between the sensitivity of the off-core neutron detectors in each quadrant will be introduced. It will be impossible to distinguish whether the deviation is caused by the difference in the sensitivity of the off-core neutron detectors or by the non-uniformity of the reactor core power or detector signals.

[0103] As can be seen from equation (5), to obtain a relatively accurate indication P... k The signal typically requires correction factor Gi k Calibration is typically performed by periodically obtaining a reference signal (such as thermal power P) through core power distribution measurement tests and thermal power measurement tests. KME After determining the actual mapping relationship between the core axial power deviation ΔI and the output current R of the external neutron detector, the calibration process is complex. The calibration test has many restrictions on the power plant's operating conditions, is complicated to operate, increases the risk of human error, and is time-consuming.

[0104] Therefore, in this embodiment, the correction coefficients of each quadrant in each cross section are calibrated at the calibration time to obtain the normalized correction coefficients of the off-pile neutron detector current in each quadrant of each cross section, and the currents of the off-pile neutron detectors in different quadrants of the same cross section under steady state are normalized to the average response of that cross section.

[0105] In this implementation, a calibration time is taken when there is no quadrant tilt in the core (i.e., the core power distribution is uniform) by a power distribution measurement based on the core neutron detector. At the calibration time, multiple calibration currents are measured by the off-core neutron detector. For each cross section, the average value of the calibration currents in all quadrants of each cross section is calculated to obtain the first average current corresponding to that cross section. The ratio of the first average current to the calibration current of the target quadrant in that cross section is used as the correction coefficient for that quadrant.

[0106] Specifically, the correction factor can be expressed by the following formula:

[0107]

[0108] Where i represents the number of cross sections in the reactor core, k represents the number of quadrants, t0 represents the calibration time, and S i k This represents the correction factor in the k-th quadrant of the i-th section. R represents the first average current at the calibrated cross-section at the i-th time point. i k (t0) represents the calibration current measured by the off-pile neutron detector in the k-th quadrant of the i-th cross section.

[0109] In this embodiment, by normalizing the calibration time, the correction coefficient for each quadrant is determined. While achieving the same technical effect as the existing correction coefficient calibration method described above, the calibration process of the correction coefficient is greatly simplified, so that the output current of the external neutron detectors in each quadrant is unified. When there is no uneven power distribution in the reactor core, the difference in the output current of the external neutron detectors caused by the difference in the sensitivity coefficients of the external neutron detectors in each quadrant can be smoothed out by the correction coefficient, so as to more accurately identify anomalies in the reactor core.

[0110] In some embodiments, the parameter values ​​of the deviation monitoring parameters corresponding to each cross-section, calculated in step S103 based on the correction current set corresponding to each cross-section, may include, but are not limited to, the following:

[0111] The mean value of the corrected current in the corrected current set corresponding to each cross section is calculated to obtain the second mean current corresponding to the cross section;

[0112] For each corrected current in the corrected current set corresponding to the cross section, the following steps are performed: obtaining the absolute value of the difference between the corrected current and the second average current; taking the ratio of the absolute value to the second average current as a first value; and taking the product of the first value and the target power as a second value, where the target power is the thermal power measured on the reactor core at the first moment.

[0113] The average value of the deviation monitoring parameter corresponding to the cross section is obtained by calculating the mean value of the second value corresponding to each of the corrected currents.

[0114] In some implementations, the original current is first corrected according to the correction coefficient corresponding to each quadrant in each section to obtain the corrected current. The corrected currents corresponding to the original currents located in the same section belong to the same set of corrected currents.

[0115] Specifically, the original current is corrected based on the correction coefficient corresponding to each quadrant in each cross section, resulting in the corrected current, which can be expressed by the following formula:

[0116]

[0117] Among them, R' i k R represents the corrected current in the k-th quadrant of the i-th section at time t. i k S represents the initial current in the k-th quadrant of the i-th section at time t. i k Let represent the correction coefficient in the k-th quadrant of the i-th section, and t represent time t.

[0118] In this implementation, due to the symmetry of the radial power of the reactor core, the current of the corrected external neutron detectors in each quadrant changes with time at approximately the same rate. Deviations only occur between the corrected responses in each quadrant when the symmetry of the core power changes or when the external neutron detector signal becomes abnormal. Therefore, this embodiment determines whether there is uneven distribution of the reactor core or abnormality in the external neutron detector signal by monitoring the relative deviation between the corrected current of the external neutron detector in the k-th quadrant of the same cross section and the average corrected current of the external neutron detectors in the k quadrants.

[0119] Specifically, based on the correction current set corresponding to each cross section, the mean current corresponding to each cross section, i.e. the second mean current, is calculated. For each correction current in the correction current set corresponding to each cross section, the absolute value of the difference between the correction current and the second mean current is calculated. The ratio of the absolute value to the second mean current is taken as the first value. The product of the first value and the thermal power measured on the reactor core at the first moment is taken as the second value. The mean value is calculated based on the second value of the correction current in each quadrant of the same cross section to obtain the parameter value of the deviation monitoring parameter of the cross section.

[0120] The second average current corresponding to each cross section can be calculated using the following formula:

[0121]

[0122] in, Let represent the second mean current at the i-th cross-section at time t, where i represents the number of cross-sections and k represents the number of quadrants. Let represent the corrected current in the k-th quadrant of the i-th section at time t, where t represents time t.

[0123] The deviation monitoring parameter values ​​for each cross-section can be calculated using the following formula:

[0124]

[0125] Among them, D i (t) represents the deviation monitoring parameter value of the i-th section at time t, P th (t) represents the thermal power measured in the reactor core at time t.

[0126] In this embodiment, Let it be the first value, and This is denoted as the second value.

[0127] In equation (10), since the absolute value of the output current of the external neutron detector is smaller under low power, it is easy to amplify the deviation when affected by interference signals of the same absolute value. Therefore, by multiplying by the thermal power of the reactor core, the problem of amplified deviation under low power is reduced, so that the deviation monitoring parameters have a certain tolerance under low power, thus avoiding false alarms.

[0128] In this embodiment, the mean current of the correction current set corresponding to each cross section is used as a benchmark, which can more accurately identify the correction current that deviates from the normal range. By calculating the relative deviation of the correction current of the off-core neutron detector in the kth quadrant of the same cross section from the mean of the correction current of the off-core neutron detectors in the k quadrants, a more accurate deviation monitoring parameter value is obtained, thereby improving the accuracy of reactor core anomaly identification.

[0129] In some embodiments, after correcting each original current in step S102 using a correction coefficient for the quadrant corresponding to the pre-acquired original current to obtain a corrected current value for each original current, before determining that there is an anomaly in the reactor core in step S104 if the parameter value of the deviation monitoring parameter corresponding to the cross section is greater than or equal to the target threshold corresponding to the cross section, the anomaly identification method for the off-core neutron detector proposed in this application may include, but is not limited to, the following:

[0130] The sum of the corrected currents corresponding to each of the original currents is taken as the third value;

[0131] The ratio of the third value to the fourth value is taken as the fifth value, where the fourth value is the product of i and k;

[0132] For each of the aforementioned sections, the following processing is performed:

[0133] The target threshold corresponding to the cross section is determined based on the ratio of the fifth value to the second average current, wherein the second average current is the average value of each corrected current in the corrected current set corresponding to the cross section.

[0134] In this implementation, since the axial arrangement of the external neutron detector is usually a multi-segment design, typically symmetrically designed vertically along the mid-plane of the core axial height, and since the axial power distribution of the core is usually non-uniform, the target threshold at different axial heights i (i.e., different cross-sections i of the reactor) is defined as SET. i Target threshold SET i It can be expressed by the following formula:

[0135]

[0136] Among them, SET i denoted as the target threshold for the i-th section, and e represents an adjustable constant, which can be set according to the actual operating margin and alarm capability of the nuclear power plant.

[0137] In this embodiment, Let it be the third value. It is denoted as the fifth value.

[0138] In this embodiment, the denominator of the calculation of the target threshold corresponding to each cross section is consistent with the denominator of the calculation of the deviation monitoring parameter corresponding to that cross section, so as to ensure that the deviation of the deviation monitoring parameter and the target threshold are consistent when the core axial power is non-uniform. That is, when the deviation monitoring parameter of a cross section is small, the target threshold corresponding to that cross section is also small. By using the target threshold corresponding to each cross section, the anomaly of the reactor core power can be identified more quickly and accurately.

[0139] In some embodiments, after calculating the parameter value of the deviation monitoring parameter corresponding to each cross-section based on the correction current set corresponding to each cross-section in step S103, the anomaly identification method of the off-pile neutron detector proposed in this application embodiment may include, but is not limited to, the following:

[0140] If the deviation monitoring parameter value corresponding to each of the i cross sections is less than the target threshold corresponding to the cross section, then it is determined that there is no abnormality in the reactor core and the external neutron detector.

[0141] In this implementation, if the deviation monitoring parameter value of each of the i cross sections of the reactor core is less than the target threshold corresponding to that cross section, it indicates that the power distribution of the reactor core is uniform, thus determining that there is no abnormality in the reactor core.

[0142] In this embodiment, by monitoring the core power of each cross section of the reactor core, the normal operation of the reactor core is ensured, and when an anomaly occurs in a cross section, the abnormal situation of the reactor core can be quickly identified.

[0143] In some embodiments, after determining that there is an anomaly in the reactor core at the target cross-section or an anomaly in the external neutron detector at the target cross-section in step S104 if the parameter value of the deviation monitoring parameter corresponding to the target cross-section is greater than or equal to the target threshold corresponding to the target cross-section, the anomaly identification method for the external neutron detector proposed in this application may include, but is not limited to, the following:

[0144] An early warning is issued based on the target cross-section, and the deviation monitoring parameters corresponding to the target cross-section are output.

[0145] In this implementation, when the parameter value of the deviation monitoring parameter corresponding to a cross section is greater than or equal to the target threshold corresponding to that cross section, the cross section is taken as the target cross section, and an early warning is issued for the abnormal situation of the reactor core. That is, the cross section information of the target cross section and the deviation monitoring parameter are sent to the technicians so that the technicians can quickly locate the cross section of the reactor core that is abnormal or the cross section of the external neutron detector that is abnormal.

[0146] The above embodiments are illustrated below through experimental verification:

[0147] To verify the effectiveness of the method, this invention takes a typical operating pressurized water reactor technology as an example (the design of the external neutron detector is a radial 4-channel design and an axial 4-segment design, which includes 4 cross sections) to verify the implementation effect of the technical solution proposed in this invention, and verifies the alarm margin during normal operation and the alarm capability under abnormal operating conditions.

[0148] likeFigure 4 As shown, taking the measured response data of the external detector at section 1 in a single quadrant of a third-generation nuclear power unit during 50% FP operation as an example, the operating margin of the distance alarm setpoint SET(t) of the monitoring parameter D(t) during operation was verified. The constant e in the SET(t) setpoint was set to 2%. The verification results are as follows: Figure 4 As shown in the results, the monitoring system will not generate false alarms during operation and has sufficient operational margin.

[0149] like Figure 5 As shown, based on the measured data, the relationship between the monitoring parameter D(t) and the alarm setpoint SET(t) at time t with a 20% attenuation of the external detector response was virtually constructed. The results show that a 20% attenuation of the external detector can effectively trigger an alarm, which can identify abnormal power in the reactor core and abnormalities in the external neutron detector.

[0150] In summary, it can be seen that the method proposed in this invention has good implementation effect in terms of both preventing false alarms and alarm accuracy.

[0151] Figure 6 This is a schematic diagram of the anomaly detection device for an off-site neutron detector provided in this application embodiment. Please refer to [link / reference]. Figure 6 This application also provides an anomaly identification device 800 for an external neutron detector. The reactor core includes i cross-sections, each cross-section including k symmetrically distributed quadrants, where i is a positive integer and k is an integer greater than 1. The anomaly identification device 800 for the external neutron detector can implement the above-mentioned anomaly identification method for the external neutron detector. The anomaly identification device 800 for the external neutron detector includes:

[0152] The current acquisition module 801 is used to acquire multiple raw currents measured by multiple external neutron detectors at a first moment. The external neutron detectors are located outside the reactor. The multiple raw currents include the output currents measured by the external neutron detectors in each quadrant of each cross section.

[0153] The current correction module 802 is used to correct each original current using a correction coefficient of the quadrant corresponding to the pre-acquired original current, so as to obtain the corrected current corresponding to each original current. The corrected currents corresponding to the original currents located in the same cross section belong to the same set of corrected currents.

[0154] The parameter calculation module 803 is used to calculate the parameter value of the deviation monitoring parameter corresponding to each cross section based on the correction current set corresponding to each cross section.

[0155] The first judgment module 804 is used to determine that if the parameter value of the deviation monitoring parameter corresponding to the target section is greater than or equal to the target threshold corresponding to the target section, the reactor core is abnormal at the target section or the external neutron detector is abnormal at the target section.

[0156] The second judgment module 805 is used to determine whether there is an anomaly in the reactor core at the target section by measuring the core power distribution.

[0157] The third judgment module 806 is used to determine that the external neutron detector has an anomaly at the target section if there is no anomaly in the reactor core.

[0158] In some embodiments, the anomaly detection device 800 of the external neutron detector further includes:

[0159] The calibration module is used to acquire multiple calibration currents measured by multiple external neutron detectors at a preset calibration time. The multiple calibration currents include the output currents measured by the external neutron detectors in each quadrant of each cross section.

[0160] The first processing module is used to perform the following processing on each section;

[0161] The average value of the calibration current corresponding to the cross section is calculated to obtain the first average current corresponding to the cross section;

[0162] For each quadrant of the cross section, the correction coefficient for that quadrant is calculated based on the mean current corresponding to the cross section and the calibration current corresponding to the quadrant.

[0163] In some implementations, the computing module 803 includes:

[0164] The first calculation submodule is used to calculate the mean value of the correction current in the correction current set corresponding to each cross section, so as to obtain the second mean current corresponding to the cross section.

[0165] The second calculation submodule is used to perform the following steps for each corrected current in the corrected current set corresponding to the cross section: obtaining the absolute value of the difference between the corrected current and the second average current; taking the ratio of the absolute value to the second average current as a first value; and taking the product of the first value and the target power as a second value, wherein the target power is the thermal power measured on the reactor core at the first moment.

[0166] The third calculation submodule is used to calculate the average value based on the second value corresponding to each of the correction currents to obtain the parameter value of the deviation monitoring parameter corresponding to the cross section.

[0167] In some embodiments, the anomaly detection device 800 of the external neutron detector further includes:

[0168] The summation module is used to sum the corrected currents corresponding to each of the original currents as a third value;

[0169] The ratio module is used to take the ratio of the third value to the fourth value as the fifth value, where the fourth value is the product of i and k;

[0170] The second processing module is used to perform the following processing for each of the cross sections:

[0171] The target threshold corresponding to the cross section is determined based on the ratio of the fifth value to the second average current, wherein the second average current is the average value of each corrected current in the corrected current set corresponding to the cross section.

[0172] In some embodiments, the anomaly detection device 800 of the external neutron detector further includes:

[0173] The second judgment module is used to determine that there is no abnormality in the reactor core and the external neutron detector if the parameter value of the deviation monitoring parameter corresponding to each of the i cross sections is less than the target threshold corresponding to the cross section.

[0174] In some embodiments, the anomaly detection device 800 of the external neutron detector further includes:

[0175] The early warning module is used to issue an early warning based on the target cross section and output the deviation monitoring parameters corresponding to the target cross section.

[0176] The specific implementation of the anomaly identification device 800 for the external neutron detector is basically the same as the specific implementation of the anomaly identification method for the external neutron detector described above, and will not be repeated here.

[0177] The anomaly identification device 800 of the external neutron detector acquires multiple raw currents measured by multiple external neutron detectors and corrects the raw currents according to the correction coefficients of the quadrants corresponding to the pre-acquired raw currents to obtain corrected currents. This eliminates measurement errors caused by factors such as detector position or environment, thereby improving the accuracy of subsequent identification of reactor core anomalies. The corrected currents corresponding to the raw currents located at the same cross section belong to the same corrected current set. The parameter value of the deviation monitoring parameter corresponding to each cross section is calculated based on the corrected current set corresponding to each cross section. If the parameter value of the deviation monitoring parameter corresponding to the target cross section is greater than or equal to the target threshold corresponding to the target cross section, it indicates that there is an anomaly in the reactor core at the target cross section or that there is an anomaly in the external neutron detector at the target cross section. Then, the reactor core power distribution measurement method is used to further determine whether there is an anomaly in the reactor core at the target cross section. If there is no anomaly in the reactor core at the target cross section, it is determined that there is an anomaly in the external neutron detector at the corresponding cross section. In this way, the cross section of the reactor core where the anomaly occurs and the corresponding external neutron detector can be accurately located.

[0178] This application also provides an electronic device, which includes a memory and a processor. The memory stores a computer program, and the processor executes the computer program to implement the above-described anomaly identification method for an external neutron detector. This electronic device can be any smart terminal, including desktop computers, tablets, mobile phones, and in-vehicle computers.

[0179] Please see Figure 7 , Figure 7 This is a schematic diagram of the hardware structure of an electronic device provided in an embodiment of this application. The electronic device includes:

[0180] The processor 901 can be implemented using a general-purpose CPU (Central Processing Unit), microprocessor, application-specific integrated circuit (ASIC), or one or more integrated circuits, and is used to execute relevant programs to implement the technical solutions provided in the embodiments of this application.

[0181] The memory 902 can be implemented as a read-only memory (ROM), static storage device, dynamic storage device, or random access memory (RAM). The memory 902 can store the operating system and other application programs. When the technical solutions provided in the embodiments of this specification are implemented through software or firmware, the relevant program code is stored in the memory 902 and is called and executed by the processor 901 to execute the anomaly identification method of the off-pile neutron detector in the embodiments of this application.

[0182] The input / output interface 903 is used to implement information input and output;

[0183] The communication interface 904 is used to enable communication and interaction between this device and other devices. Communication can be achieved through wired means (such as USB, Ethernet cable, etc.) or wireless means (such as mobile network, WIFI, Bluetooth, etc.).

[0184] Bus 905 transmits information between various components of the device (e.g., processor 901, memory 902, input / output interface 903, and communication interface 904);

[0185] The processor 901, memory 902, input / output interface 903, and communication interface 904 are connected to each other within the device via bus 905.

[0186] This application also provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the above-described anomaly identification method for an external neutron detector.

[0187] Memory, as a non-transitory computer-readable storage medium, can be used to store non-transitory software programs and non-transitory computer-executable programs. Furthermore, memory may include high-speed random access memory, and may also include non-transitory memory, such as at least one disk storage device, flash memory device, or other non-transitory solid-state storage device. In some embodiments, memory may optionally include memory remotely located relative to the processor, and these remote memories can be connected to the processor via a network. Examples of such networks include, but are not limited to, the Internet, intranets, local area networks, mobile communication networks, and combinations thereof.

[0188] The anomaly identification method for external neutron detectors provided in this application acquires multiple raw currents measured by multiple external neutron detectors, and corrects the raw currents according to the correction coefficients of the quadrants corresponding to the pre-acquired raw currents to obtain corrected currents. This eliminates measurement errors caused by factors such as detector position or environment, thereby improving the accuracy of subsequent identification of reactor core anomalies. The corrected currents corresponding to the raw currents located at the same cross-section belong to the same set of corrected currents. The parameter value of the deviation monitoring parameter corresponding to each cross-section is calculated based on the set of corrected currents corresponding to each cross-section. If the parameter value of the deviation monitoring parameter corresponding to the target cross-section is greater than or equal to the target threshold corresponding to the target cross-section, it indicates that there is an anomaly in the reactor core at the target cross-section or that there is an anomaly in the external neutron detector at the target cross-section. Then, the reactor core power distribution measurement method is used to further determine whether there is an anomaly in the reactor core at the target cross-section. If there is no anomaly in the reactor core at the target cross-section, it is determined that there is an anomaly in the external neutron detector at the corresponding cross-section. In this way, the cross-section where the reactor core anomaly occurs and the corresponding external neutron detector can be accurately located.

[0189] The embodiments described in this application are for the purpose of more clearly illustrating the technical solutions of the embodiments of this application, and do not constitute a limitation on the technical solutions provided by the embodiments of this application. As those skilled in the art will know, with the evolution of technology and the emergence of new application scenarios, the technical solutions provided by the embodiments of this application are also applicable to similar technical problems.

[0190] Those skilled in the art will understand that the technical solutions shown in the figures do not constitute a limitation on the embodiments of this application, and may include more or fewer steps than shown, or combine certain steps, or different steps.

[0191] The device embodiments described above are merely illustrative. The units described as separate components may or may not be physically separate; that is, they may be located in one place or distributed across multiple network units. Some or all of the modules can be selected to achieve the purpose of this embodiment according to actual needs.

[0192] Those skilled in the art will understand that all or some of the steps in the methods disclosed above, as well as the functional modules / units in the systems and devices, can be implemented as software, firmware, hardware, or suitable combinations thereof.

[0193] The terms “first,” “second,” “third,” “fourth,” etc. (if present) in the specification and accompanying drawings of this application are used to distinguish similar objects and are not necessarily used to describe a specific order or sequence. It should be understood that such data can be interchanged where appropriate so that the embodiments of this application described herein can be implemented in orders other than those illustrated or described herein. Furthermore, the terms “comprising” and “having,” and any variations thereof, are intended to cover non-exclusive inclusion; for example, a process, method, system, product, or apparatus that comprises a series of steps or units is not necessarily limited to those steps or units explicitly listed, but may include other steps or units not explicitly listed or inherent to such processes, methods, products, or apparatus.

[0194] It should be understood that in this application, "at least one (item)" means one or more, and "more than" means two or more. "And / or" is used to describe the relationship between related objects, indicating that three relationships can exist. For example, "A and / or B" can represent three cases: only A exists, only B exists, and both A and B exist simultaneously, where A and B can be singular or plural. The character " / " generally indicates that the preceding and following related objects are in an "or" relationship. "At least one (item) of the following" or similar expressions refer to any combination of these items, including any combination of single or plural items. For example, at least one (item) of a, b, or c can represent: a, b, c, "a and b", "a and c", "b and c", or "a and b and c", where a, b, and c can be single or multiple.

[0195] In the several embodiments provided in this application, it should be understood that the disclosed apparatus and methods can be implemented in other ways. For example, the apparatus embodiments described above are merely illustrative; for instance, the division of the units described above is only a logical functional division, and in actual implementation, there may be other division methods. For example, multiple units or components may be combined or integrated into another system, or some features may be ignored or not executed. Furthermore, the coupling or direct coupling or communication connection shown or discussed may be through some interfaces; the indirect coupling or communication connection between apparatuses or units may be electrical, mechanical, or other forms.

[0196] The units described above as separate components may or may not be physically separate. The components shown as units may or may not be physical units; that is, they may be located in one place or distributed across multiple network units. Some or all of the units can be selected to achieve the purpose of this embodiment according to actual needs.

[0197] Furthermore, the functional units in the various embodiments of this application can be integrated into one processing unit, or each unit can exist physically separately, or two or more units can be integrated into one unit. The integrated unit can be implemented in hardware or as a software functional unit.

[0198] If the integrated unit is implemented as a software functional unit and sold or used as an independent product, it can be stored in a computer-readable storage medium. Based on this understanding, the technical solution of this application, in essence, or the part that contributes to the prior art, or all or part of the technical solution, can be embodied in the form of a software product. This computer software product is stored in a storage medium and includes multiple instructions to cause a computer device (which may be a personal computer, server, or network device, etc.) to execute all or part of the steps of the methods of the various embodiments of this application. The aforementioned storage medium includes various media capable of storing programs, such as USB flash drives, portable hard drives, read-only memory (ROM), random access memory (RAM), magnetic disks, or optical disks.

[0199] The preferred embodiments of the present application have been described above with reference to the accompanying drawings, but this does not limit the scope of the claims of the present application. Any modifications, equivalent substitutions, and improvements made by those skilled in the art without departing from the scope and substance of the embodiments of the present application shall be within the scope of the claims of the present application.

Claims

1. A method for anomaly identification in an external neutron detector, characterized in that, The external neutron detectors are uniformly disposed outside the reactor core. The reactor core comprises i cross-sections, each cross-section comprising k symmetrically distributed quadrants, where i is a positive integer and k is an integer greater than 1. The method includes: At a first moment, multiple raw currents are acquired by multiple off-pile neutron detectors, the multiple raw currents including the output currents measured by the off-pile neutron detectors in each quadrant of each cross section; Each original current is corrected using the correction coefficient of the quadrant corresponding to the pre-acquired original current to obtain the corrected current corresponding to each original current. The corrected currents corresponding to the original currents located in the same cross section belong to the same set of corrected currents. Based on the corrected current set corresponding to each cross section, the parameter values ​​of the deviation monitoring parameters corresponding to each cross section are calculated; If the parameter value of the deviation monitoring parameter corresponding to the target section is greater than or equal to the target threshold corresponding to the target section among the i sections, it is determined that there is an anomaly in the reactor core at the target section or that there is an anomaly in the external neutron detector at the target section; The presence of anomalies in the reactor core at the target cross-section is determined by measuring the core power distribution. If there is no anomaly in the reactor core at the target cross-section, then it is determined that there is an anomaly in the external neutron detector at the target cross-section. Prior to acquiring multiple raw currents measured by multiple off-pile neutron detectors, the method further includes: Multiple calibration currents are acquired at a preset calibration time by measuring multiple off-pile neutron detectors. The multiple calibration currents include the output currents measured by the off-pile neutron detectors in each quadrant of each cross section. Perform the following processing on each section; The average value of the calibration current corresponding to the cross section is calculated to obtain the first average current corresponding to the cross section; For each quadrant of the cross section, the correction coefficient for that quadrant is calculated based on the mean current corresponding to the cross section and the calibration current corresponding to the quadrant.

2. The method according to claim 1, characterized in that, The step of calculating the parameter value of the deviation monitoring parameter corresponding to each cross-section based on the corrected current set corresponding to each cross-section includes: The mean value of the corrected current in the corrected current set corresponding to each cross section is calculated to obtain the second mean current corresponding to the cross section; For each corrected current in the corrected current set corresponding to the cross section, the following steps are performed: obtaining the absolute value of the difference between the corrected current and the second average current; taking the ratio of the absolute value to the second average current as a first value; and taking the product of the first value and the target power as a second value, where the target power is the thermal power measured on the reactor core at the first moment. The average value of the deviation monitoring parameter corresponding to the cross section is obtained by calculating the mean value of the second value corresponding to each of the corrected currents.

3. The method according to claim 1, characterized in that, After correcting each original current using a correction coefficient corresponding to the quadrant of the pre-acquired original current to obtain a corrected current for each original current, and before determining that the reactor core has an anomaly if the parameter value of the deviation monitoring parameter corresponding to the cross section is greater than or equal to the target threshold corresponding to the cross section, the method further includes: The sum of the corrected currents corresponding to each of the original currents is taken as the third value; The ratio of the third value to the fourth value is taken as the fifth value, where the fourth value is the product of i and k; For each of the aforementioned sections, the following processing is performed: The target threshold corresponding to the cross section is determined based on the ratio of the fifth value to the second average current, wherein the second average current is the average value of each corrected current in the corrected current set corresponding to the cross section.

4. The method according to claim 1, characterized in that, After calculating the parameter values ​​of the deviation monitoring parameters corresponding to each cross-section based on the corrected current set corresponding to each cross-section, the method further includes: If the deviation monitoring parameter value corresponding to each of the i cross sections is less than the target threshold corresponding to the cross section, then it is determined that there is no abnormality in the reactor core and the external neutron detector.

5. The method according to claim 1, characterized in that, After determining that either the reactor core or the external neutron detector has an anomaly at the target cross-section if the deviation monitoring parameter value of the target cross-section is greater than or equal to the target threshold value of the target cross-section, the method further includes: An early warning is issued based on the target cross-section, and the deviation monitoring parameters corresponding to the target cross-section are output.

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