Abnormity identification method and device for out-of-pile neutron detector, electronic equipment and medium

Abstract

The embodiment of the invention provides an anomaly identification method and device for an out-of-core neutron detector, electronic equipment and a medium, and belongs to the technical field of nuclear power. The method comprises the following steps: acquiring a plurality of original currents measured by a plurality of out-of-core neutron detectors at a first moment; correcting each original current by using the correction coefficient of the quadrant corresponding to the original current to obtain a corrected current; according to the correction current set of each section, a deviation monitoring parameter value of each section is obtained through calculation; if the deviation monitoring parameter value corresponding to the target cross section is greater than or equal to the target threshold value of the target cross section, determining that the reactor core or the out-of-core neutron detector is abnormal at the target cross section; judging whether the reactor core is abnormal at the target section or not through a reactor core power distribution measurement mode; and if the reactor core is not abnormal at the target section, determining that the out-of-core neutron detector is abnormal at the target section. According to the embodiment of the invention, the abnormal position of the out-of-pile neutron detector can be accurately positioned.

Description

Technical Field

[0001] This application relates to the field of nuclear power technology, and in particular, to a method, device, electronic device and medium for abnormal identification of an in-core neutron detector. Background Art

[0002] The in-core neutron detectors are generally arranged outside the reactor core and are evenly distributed around the reactor. The in-core neutron detectors can be used to measure the core power. When measuring the core power of the reactor, the linear relationship between the axial power deviation of the reactor core and the in-core neutron detectors and the thermal power measurement test are mainly used to obtain the correction coefficient of the in-core detector. The core power of each quadrant of the reactor is obtained by restoring the in-core detector signal after correction, and an algorithm is used to judge whether the power of each radial quadrant of the reactor core is tilted or whether the signals of all in-core neutron detectors in the quadrant are abnormal; therefore, it is impossible to accurately locate the axial position where the reactor core appears abnormal and the axial position where the in-core neutron detector appears abnormal within the quadrant. Summary of the Invention

[0003] The main purpose of the embodiments of this application is to propose a method, device, electronic device and medium for abnormal identification of an in-core neutron detector, which can accurately locate the axial position where the in-core neutron detector appears abnormal by judging the core power at each axial height in the reactor core.

[0004] To achieve the above object, the first aspect of the embodiments of this application proposes a method for abnormal identification of an in-core neutron detector. The in-core neutron detectors are evenly arranged outside the reactor. The reactor core includes i cross-sections, and each cross-section includes k quadrants symmetrically distributed. i is a positive integer, and k is an integer greater than 1. The method includes:

[0005] Obtain a plurality of original currents measured by a plurality of in-core neutron detectors at a first moment. The in-core neutron detectors are arranged outside the reactor. The plurality of original currents include the output currents measured by the in-core neutron detectors in each quadrant of each cross-section;

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

[0007] Calculate the parameter value of the deviation monitoring parameter corresponding to each cross-section according to the corrected current set corresponding to each cross-section;

[0008] If, among the i cross-sections, 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 is determined that there is an abnormality in the reactor core at the target cross-section or there is an abnormality in the off-core neutron detector at the target cross-section;

[0009] Judge whether there is an abnormality in the reactor core at the target cross-section by means of core power distribution measurement;

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

[0011] In some embodiments, before obtaining the multiple original currents measured by multiple off-core neutron detectors, the method further includes:

[0012] Obtain multiple calibration currents measured by multiple off-core neutron detectors at a preset calibration moment, and the multiple calibration currents include the output currents measured by the off-core neutron detector in each quadrant of each cross-section;

[0013] Perform the following processing on each cross-section;

[0014] Calculate the mean value of the calibration currents corresponding to the cross-section to obtain the first mean current corresponding to the cross-section;

[0015] For each quadrant of the cross-section, perform: calculate the correction coefficient of the quadrant according to the mean current corresponding to the cross-section and the calibration current corresponding to the quadrant.

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

[0017] Calculate the mean value of the correction currents in the set of correction currents corresponding to each cross-section to obtain the second mean current corresponding to the cross-section;

[0018] For each correction current in the set of correction currents corresponding to the cross-section, perform: obtain the absolute value of the difference between the correction current and the second mean current; take the ratio of the absolute value to the second mean current as the first value; take the product of the first value and the target power as the second value, and the target power is the thermal power measured for the reactor core at the first moment;

[0019] Calculate the mean value according to the second value corresponding to each correction current to obtain the parameter value of the deviation monitoring parameter corresponding to the cross-section.

[0020] In some embodiments, after correcting each of the original currents by using the correction coefficient corresponding to the quadrant of the pre-acquired original current to obtain the corrected current corresponding to each of the original currents, before determining that there is an abnormality in the reactor core 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] Taking the sum of the corrected currents corresponding to each of the original currents as a third value;

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

[0023] For each of the cross-sections, perform the following processing:

[0024] Determining the target threshold corresponding to the cross-section according to the ratio of the fifth value to the second average current, where the second average current is the average value of each corrected current in the set of corrected currents corresponding to the cross-section.

[0025] In some embodiments, after calculating the parameter value of the deviation monitoring parameter corresponding to each cross-section according to the set of corrected currents corresponding to each cross-section, the method further includes:

[0026] 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, it is determined that there is no abnormality in the reactor core and the off-core neutron detector.

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

[0028] Issuing a warning according to the target cross-section and outputting the deviation monitoring parameter corresponding to the target cross-section.

[0029] To achieve the above object, a second aspect of the embodiments of the present application provides an abnormal identification device for an off-core neutron detector. The off-core neutron detector is uniformly arranged outside the reactor. The reactor core includes i cross-sections, and each cross-section includes k quadrants symmetrically distributed. i is a positive integer, and k is an integer greater than 1. The device includes:

[0030] A current acquisition module, configured to acquire a plurality of original currents measured by a plurality of off-core neutron detectors at a first moment, where the off-core neutron detectors are arranged outside the reactor core, and the plurality of original currents include output currents measured by the off-core neutron detectors in each quadrant of each cross-section;

[0031] A current correction module, configured to correct each of the original currents by using a correction coefficient corresponding to the quadrant of the pre-acquired original current to obtain a corrected current corresponding to each of the original currents, and the corrected currents corresponding to the original currents located in the same cross-section belong to the same corrected current set;

[0032] A parameter calculation module, configured to calculate a parameter value of a deviation monitoring parameter corresponding to each cross-section according to the corrected current set corresponding to each cross-section;

[0033] A first judgment module, configured to determine that there is an abnormality in the reactor core at the target cross-section or there is an abnormality in the off-core neutron detector at the target cross-section if the parameter value of the deviation monitoring parameter corresponding to the target cross-section among i cross-sections is greater than or equal to the target threshold corresponding to the target cross-section;

[0034] A second judgment module, configured to judge whether there is an abnormality in the reactor core at the target cross-section by a core power distribution measurement method;

[0035] A third judgment module, configured to determine that there is an abnormality in the off-core neutron detector at the target cross-section if there is no abnormality in the reactor core at the target cross-section.

[0036] To achieve the above object, a third aspect of the embodiments of the present application provides an electronic device, where the electronic device includes a memory and a processor, the memory stores a computer program, and when the processor executes the computer program, the abnormal identification method of the off-core neutron detector described in the first aspect above is implemented.

[0037] To achieve the above object, a fourth aspect of the embodiments of the present application provides a computer-readable storage medium, where the computer-readable storage medium stores a computer program, and when the computer program is executed by a processor, the abnormal identification method of the off-core neutron detector described in the first aspect above is implemented.

[0038] An abnormal recognition method, device, electronic device and medium for an in-core neutron detector proposed in this application. By obtaining multiple original currents measured by multiple in-core neutron detectors and correcting the original currents according to the correction coefficients of the quadrants corresponding to the pre-obtained original currents to obtain corrected currents, so as to eliminate measurement errors caused by factors such as detector position or environment, thereby improving the subsequent recognition accuracy of reactor core anomalies. The corrected currents corresponding to the original currents in the same cross-section belong to the same corrected current set. Calculate the parameter values of the deviation monitoring parameters corresponding to each cross-section according to the corrected current set corresponding to each cross-section. If the parameter value of the deviation monitoring parameter corresponding to the target cross-section in i cross-sections 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 there is an anomaly in the in-core neutron detector at the target cross-section. Then, further judge whether there is an anomaly in the reactor core at the target cross-section through the reactor core power distribution measurement method. If there is no anomaly in the reactor core at the target cross-section, it is determined that the in-core neutron detector corresponding to the cross-section is abnormal; in this way, the cross-section where the reactor core anomaly occurs and the corresponding in-core neutron detector can be accurately located. BRIEF DESCRIPTION OF THE DRAWINGS

[0039] Figure 1 is a schematic flowchart of the abnormal recognition method for an in-core neutron detector provided by an embodiment of this application;

[0040] Figure 2 is a schematic structural diagram of a typical pressurized water reactor nuclear power unit provided by an embodiment of this application;

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

[0042] Figure 4 is an operating margin effect diagram of a typical operating pressurized water reactor in one implementation manner provided by an embodiment of this application;

[0043] Figure 5 is an abnormal recognition effect diagram of a typical operating pressurized water reactor in one implementation manner provided by an embodiment of this application;

[0044] Figure 6 is a schematic structural diagram of the abnormal recognition device for an in-core neutron detector provided by an embodiment of this application;

[0045] Figure 7 is a schematic hardware structure diagram of an electronic device provided by an embodiment of this application. DETAILED DESCRIPTION OF THE EMBODIMENTS

[0046] In order to make the objectives, technical solutions and advantages of the present application more clear and understandable, the present application will be further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present application and are not used to limit the present application.

[0047] It should be noted that although the functional modules are divided in the device schematic diagram and the logical sequence is shown in the flowchart, in some cases, the steps shown or described may be executed in a different module division in the device or a different sequence in the flowchart. Terms such as "first" and "second" in the specification, claims and the above-mentioned drawings are used to distinguish similar objects and do not necessarily need 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 those skilled in the technical field to which this application belongs. The terms used herein are only for the purpose of describing the embodiments of this application and are not intended to limit this application.

[0049] The safe and stable operation of a nuclear power plant has extremely high requirements for the uniformity of the core power distribution. The core radial non-uniformity (such as quadrant power tilt) may be caused by various factors, including local rod position out-of-step, fuel element failure, coolant flow non-uniformity, etc. Therefore, effective monitoring of the core radial non-uniformity is crucial for ensuring the safe operation of a nuclear power plant.

[0050] The out-of-core neutron detectors are generally arranged outside the reactor core and are evenly distributed around the reactor. The out-of-core neutron detectors can be used to measure the core power. When measuring the core power of the reactor, the linear relationship between the axial power deviation of the reactor core and the out-of-core neutron detectors and the thermal power measurement test are mainly used to obtain the correction coefficient of the out-of-core detectors. The out-of-core nuclear power is restored through the corrected out-of-core detector signals to obtain the power of each quadrant of the reactor core, and an algorithm is used to judge whether the power of each radial quadrant of the reactor core is tilted or whether the signals of all out-of-core detectors in the quadrant are abnormal; therefore, it is impossible to accurately locate the axial position where the reactor core appears abnormal and the axial position where the out-of-core neutron detectors in the quadrant appear abnormal.

[0051] Based on this, the embodiments of the present application provide a method, device, electronic device and medium for abnormal identification of out-of-core neutron detectors, aiming to solve the problems that the existing methods for abnormal identification of out-of-core neutron detectors cannot accurately locate the abnormal positions of out-of-core detectors, and the existing calibration methods for the correction coefficients of out-of-core neutron detectors are complex and inefficient. Figure 1It is an alternative flowchart of the method for identifying anomalies in out-of-core neutron detectors provided by the embodiments of the present application. The embodiments of the present application mainly obtain multiple raw currents measured by multiple out-of-core neutron detectors, and correct the raw currents according to the correction coefficients of the quadrants corresponding to the pre-obtained raw currents to obtain corrected currents, so as to eliminate measurement errors caused by factors such as detector position or environment, thereby improving the subsequent identification accuracy of reactor core anomalies. The corrected currents corresponding to the raw currents in the same cross-section belong to the same corrected current set. Calculate the parameter values of the deviation monitoring parameters corresponding to each cross-section according to the corrected current set corresponding to each cross-section. If the parameter value of the deviation monitoring parameter corresponding to the target cross-section among the i cross-sections 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 there is an anomaly in the out-of-core neutron detector at the target cross-section. Then, further judge whether there is an anomaly in the reactor core at the target cross-section through the reactor core power distribution measurement method. If there is no anomaly in the reactor core at the target cross-section, it is determined that the out-of-core neutron detector corresponding to the cross-section is abnormal; in this way, the cross-section where the reactor core anomaly occurs and the corresponding out-of-core neutron detector can be accurately located.

[0052] The method, device, electronic device and medium for identifying anomalies in out-of-core neutron detectors provided by the embodiments of the present application will be specifically described through the following embodiments. First, the method for identifying anomalies in out-of-core neutron detectors in the embodiments of the present application will be described.

[0053] The embodiments of the present application can acquire and process relevant data based on artificial intelligence technology. Among them, artificial intelligence (AI) is a theory, method, technology and application system that uses digital computers or machines controlled by digital computers to simulate, extend and expand human intelligence, perceive the environment, acquire knowledge and use knowledge to obtain the best results.

[0054] Artificial intelligence basic technologies generally include technologies such as sensors, dedicated artificial intelligence chips, cloud computing, distributed storage, big data processing technology, operation / interaction systems, and mechatronics. Artificial intelligence software technologies mainly include several major directions such as computer vision technology, robotics, biometric technology, speech processing technology, natural language processing technology, and machine learning / deep learning.

[0055] The abnormal recognition method of the ex-core neutron detector provided by the embodiments of the present application relates to the field of nuclear power technology. The abnormal recognition method of the ex-core neutron detector provided by the embodiments of the present application can be applied to a terminal, or to a server side, or can also be software running on a terminal or a server side. In some embodiments, the terminal can be a smart phone, a tablet computer, a laptop computer, a desktop computer, etc.; the server side can be configured as an independent physical server, or can be configured as a server cluster or a distributed system composed of multiple physical servers, or can also be configured as a cloud server providing basic cloud computing services such as cloud services, cloud databases, cloud computing, cloud functions, cloud storage, network services, cloud communications, middleware services, domain name services, security services, CDN, and big data and artificial intelligence platforms; the software can be an application that implements the abnormal recognition method of the ex-core neutron detector, etc., but is not limited to the above forms.

[0056] The present application can be used in many general or special computer system environments or configurations. For example: personal computers, server computers, handheld or portable devices, tablet-type devices, multi-processor systems, microprocessor-based systems, set-top boxes, programmable consumer electronic devices, network PCs, minicomputers, mainframe computers, distributed computing environments including any of the above systems or devices, and so on. The present 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. The present application can also be practiced in a distributed computing environment, where tasks are performed by remote processing devices connected through a communication network. In a distributed computing environment, program modules can be located in local and remote computer storage media including storage devices.

[0057] It should be noted that in each specific implementation manner of the present application, when it comes to performing relevant processing based on data related to the user's identity or characteristics such as user information, user behavior data, user historical data, and user location information, the user's permission or consent will be obtained first. Moreover, the collection, use, and processing of these data will comply with relevant laws, regulations, and standards. In addition, when the embodiments of the present application need to obtain the user's sensitive personal information, the user's separate permission or separate consent will be obtained through methods such as pop-up windows or redirecting to a confirmation page. After clearly obtaining the user's separate permission or separate consent, the necessary user-related data for the normal operation of the embodiments of the present application will be obtained.

[0058] The basic principle of the measurement of the ex-core neutron detector is that there is an approximate proportional relationship among the core power, the core neutron fluence rate, the neutron fluence rate at the position of the ex-core neutron detector, and the current of the ex-core neutron detector. Therefore, the core power level can be monitored according to the current level of the ex-core neutron detector.

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

[0060] Under the core conditions of steady state without burnup effect, the proportional relationship between the core power and the average core neutron fluence rate can be simplified to the following relational expression:

[0061] P = E f ×Σ f ×Φ in ×V (1)

[0062] where, P is the core power; E f is 235 the energy generated by a single fission of U nucleus, which can be considered as a constant; Σ f is the average macroscopic fission cross section of the core, which can be considered unchanged under the steady-state core without considering burnup; Φ in is the average core neutron fluence rate; V is the core volume, which can be considered as a constant.

[0063] The relationship between the current of the ex-core neutron detector and the core neutron fluence rate distribution:

[0064] The relationship between the output current R of the ex-core neutron detector and the core power distribution can be expressed by the following relational expression:

[0065] R = C × ∫ V P(r) × ω(r)dV (2)

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

[0067] The core loading scheme, control rod position, and the measurement channels of the ex-core neutron detector in a traditional pressurized water reactor usually follow a symmetric arrangement radially. Taking a typical pressurized water reactor nuclear power unit as an example, the core loading scheme, control rod arrangement, and the ex-core neutron detector channels are radially arranged in 1 / 4 rotational symmetry, such as Figure 2As shown, the initial enrichment of the fuel assemblies at the four positions marked K4, M10, F12, and D6 is the same, and the design of the control rods at these four positions and their movement during operation are also synchronized. Such a design can ensure that the core power distribution also satisfies 1 / 4 rotational symmetry, and the power of the fuel assemblies at symmetric positions is basically the same.

[0068] The radial measurement channels of the off-core neutron detectors also follow the principle of 1 / 4 rotational symmetry, and the paths of neutron transport from the core to the outside of the reactor are basically the same. Therefore, Figure 2 the response functions corresponding to the four detectors given are also basically the same.

[0069] During normal operation, the neutron fluence rates at the four off-core neutron detectors are also basically the same. Therefore, based on the above characteristics, after integrating the product of the component power and the response function over the volume in a certain quadrant of the radial direction for P(r) in Equation (2), the relationship between the power of the core quadrant and the output current of the off-core neutron detector at the i-th cross-section of the corresponding quadrant k can be obtained, that is:

[0070]

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

[0072] And due to the sensitivity coefficient C k,i Since there are differences in the factory characteristics, a correction coefficient G is also used to convert the relationship between the output current of the off-core neutron detector and the off-core displayed power, i k so as to obtain the off-core displayed power P corresponding to quadrant k k :

[0073]

[0074] After combining Equation (3) and Equation (4), the off-core displayed power P corresponding to quadrant k k can be expressed as:

[0075]

[0076] Through the above reasoning, the uniformity of the power among the radial quadrants of the core can be monitored, which is usually called the quadrant power tilt (TILT / QPTR) monitoring, and can be expressed by the following formula:

[0077]

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

[0079] On the other hand, the sensitivity coefficient C of the same out-of-core neutron detector i k will not change significantly during normal operation. When TILT is greater than expected, it may also be due to an abnormal change in C i k (such as detector damage or power loss) resulting in the output current of the out-of-core neutron detector deviating from the expected value, reminding the technicians that there is an abnormality in the performance of the out-of-core neutron detector.

[0080] Figure 1 is a schematic flow chart of the method for identifying abnormalities of the out-of-core neutron detector provided by the embodiments of the present application. Please refer to Figure 1 , the out-of-core neutron detectors of the embodiments of the present application are uniformly arranged outside the reactor. The core of the reactor includes i cross-sections, and each cross-section includes k quadrants symmetrically distributed. i is a positive integer, and k is an integer greater than 1. The method for identifying abnormalities of the out-of-core neutron detector proposed by the embodiments of the present application may include, but is not limited to, steps S101 to S106.

[0081] Step S101: Obtain a plurality of original currents measured by a plurality of out-of-core neutron detectors at a first moment. The plurality of original currents include the original currents measured by the out-of-core neutron detectors in each quadrant of each cross-section.

[0082] In this step, according to the axial height of the reactor core, the reactor core is divided into i cross-sections, each cross-section represents an axial height, the entire reactor core includes k rotationally symmetric quadrants, the first moment is the current moment, the original current is the original output current measured by the out-of-core neutron detector, and the distribution mode of the out-of-core neutron detector is the same as the distribution mode of the reactor core, that is, the out-of-core neutron detectors are uniformly distributed in the i cross-sections and k quadrants outside the reactor core, and the original currents of each quadrant of each cross-section of the reactor core are measured by a plurality of out-of-core neutron detectors.

[0083] Exemplarily, such as Figure 3As shown, the reactor core includes cross-section 01 and cross-section 02, as well as four quadrants symmetrically distributed in rotation in each cross-section, that is, quadrants 1a, 1b, 1c, and 1d are included in cross-section 01, and quadrants 2a, 2b, 2c, and 2d are included in cross-section 02. Obtain the original current of each quadrant in the four quadrants of cross-section 01 and the original current of each quadrant in the four quadrants of cross-section 02 measured by the out-of-core neutron detector at the current moment, that is, a total of eight original currents are obtained.

[0084] Step S102: Correct each of the original currents by using the correction coefficient corresponding to the quadrant of the pre-obtained 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 corrected current set.

[0085] In this step, each quadrant in each cross-section corresponds to a correction coefficient. According to the cross-section and quadrant corresponding to the original current, obtain the correction coefficient corresponding to the original current, and correct the original current by the correction system corresponding to the original current to obtain the corrected current corresponding to each original current, and classify the corrected currents belonging to the same cross-section into the same corrected current set.

[0086] Exemplarily, the reactor core includes one cross-section and two quadrants. The first quadrant corresponds to the first correction coefficient, the original current of the first quadrant is the first original current, the second quadrant corresponds to the second correction coefficient, and the original current of the second quadrant is the second original current. Correct the first original current according to the first correction coefficient to obtain the first corrected current, correct the second original current according to the second correction coefficient to obtain the second corrected current, and the first corrected current set is composed of the first corrected current and the second corrected current.

[0087] Step S103: Calculate the parameter value of the deviation monitoring parameter corresponding to each cross-section according to the corrected current set corresponding to each cross-section.

[0088] In this step, due to the symmetry of the radial power of the reactor core, the variation amplitude of the corrected currents of the out-of-core neutron detectors after correction in each quadrant is basically the same over time. Only when the symmetry of the core power changes or the signals of the out-of-core neutron detectors are abnormal, there will be a deviation between the corrected currents in each quadrant. Therefore, according to the corrected current set composed of the corrected currents belonging to the same cross-section, calculate the deviation monitoring parameter of this cross-section, and judge whether there is uneven distribution in the reactor core or whether the out-of-core neutron detectors are abnormal through the parameter value of the deviation monitoring parameter.

[0089] Step S104: If, among the i cross-sections, 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 is determined that there is an abnormality in the reactor core at the target cross-section or there is an abnormality in the off-core neutron detector at the target cross-section.

[0090] In this step, among the i cross-sections of the reactor core, if the deviation monitoring parameter of the target cross-section is greater than or equal to the target threshold corresponding to this cross-section, it can indicate an abnormality in the reactor core or an abnormality in the off-core neutron detector.

[0091] Exemplarily, 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 there is an abnormality in the core power measured by the off-core neutron detector at the first cross-section. Thus, it can be indicated that there is uneven core distribution in the reactor core at the first cross-section, or it can be indicated that there is an abnormality in the off-core neutron detector at the first cross-section.

[0092] Step S105: Determine whether there is an abnormality in the reactor core at the target cross-section by means of core power distribution measurement.

[0093] In this step, further determine whether there is an abnormality in the reactor core at the target cross-section by using the existing core power distribution measurement method. Among them, the existing core power distribution measurement method is to use a self-powered neutron detector (SPND) in the core neutron detector to realize the measurement of the power quadrant tilt of the reactor core, that is, to determine whether the power distribution of the reactor core is uniform, so as to determine whether there is an abnormality in the reactor core.

[0094] Step S106: If there is no abnormality in the reactor core at the target cross-section, it is determined that there is an abnormality in the off-core 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 off-core 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 off-core neutron detector at the corresponding cross-section operates normally.

[0096] Through the above steps S101 to S106, the electronic device obtains multiple raw currents measured by multiple ex-core neutron detectors, and corrects the raw currents according to the correction factors corresponding to the quadrants of the pre-obtained raw currents to obtain corrected currents, so as to eliminate measurement errors caused by factors such as detector position or environment, thereby improving the subsequent recognition accuracy of reactor core anomalies. The corrected currents corresponding to the raw currents in the same cross-section belong to the same corrected current set. The parameter values of the deviation monitoring parameters corresponding to each cross-section are calculated according to the corrected current set corresponding to each cross-section. If the parameter value of the deviation monitoring parameter corresponding to the target cross-section in the i cross-sections 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 there is an anomaly in the ex-core neutron detector at the target cross-section. Then, further judgment is made on whether there is an anomaly in the reactor core at the target cross-section through the core power distribution measurement method. If there is no anomaly in the reactor core at the target cross-section, it is determined that the ex-core neutron detector corresponding to the cross-section is abnormal; in this way, the cross-section where the reactor core anomaly occurs and the corresponding ex-core neutron detector can be accurately located.

[0097] In some embodiments, before obtaining multiple raw currents measured by multiple ex-core neutron detectors in step S101, the method for identifying anomalies of ex-core neutron detectors proposed in the embodiments of the present application may include but is not limited to the following:

[0098] Obtain multiple calibrated currents measured by multiple ex-core neutron detectors at a preset calibration moment, and the multiple calibrated currents include the output currents measured by the ex-core neutron detector in each quadrant of each cross-section;

[0099] Perform the following processing on each cross-section;

[0100] Calculate the mean value of the calibrated currents corresponding to the cross-section to obtain the first mean current corresponding to the cross-section;

[0101] For each quadrant of the cross-section, perform: calculate the correction factor of the quadrant according to the mean current corresponding to the cross-section and the calibrated current corresponding to the quadrant.

[0102] There are differences in the sensitivities of each neutron detector. If the raw signals of the ex-core neutron detectors in each quadrant are directly used to judge the power tilt of the core power in each quadrant, the deviation between the sensitivities of the ex-core neutron detectors in each quadrant will be introduced, and it is impossible to distinguish whether the deviation reason comes from the difference in the sensitivity of the ex-core neutron detector or the deviation caused by the unevenness of the reactor core power or detector signal.

[0103] And it can be seen from Equation (5) that to obtain a relatively accurate indication P k The signal usually requires the correction factor Gi k Calibration is carried out. The usual acquisition method is to regularly obtain the reference signals (such as the thermal power P KME and the core axial power deviation ΔI) and the measured mapping relationship between the output current R of the ex-core neutron detector through the core power distribution measurement test and the thermal power measurement test. Its calibration process is complex, and the calibration test has many limiting conditions for the power plant operation conditions, with complex operations, increasing the risk of human error and taking a long time.

[0104] Therefore, in this embodiment, the correction coefficient of each quadrant in each cross-section is calibrated at the calibration moment to obtain the normalized correction coefficient of the ex-core neutron detector current in each quadrant of each cross-section, and the currents of the ex-core neutron detectors in different quadrants of the same cross-section under steady state are normalized to the average response of this cross-section.

[0105] In this implementation manner, through a power distribution measurement based on the core neutron detector once, the moment when there is no quadrant tilt in the core (that is, the core power distribution is uniform) is used as the calibration moment. At the calibration moment, multiple calibration currents are measured through the ex-core neutron detector. For each cross-section, the average value of the calibration currents of all quadrants in this cross-section is calculated to obtain the first mean current corresponding to this cross-section, and the ratio of the first mean current to the calibration current of the target quadrant in this cross-section is used as the correction coefficient of this quadrant.

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

[0107]

[0108] where i represents the number of cross-sections of the reactor core, k represents the number of quadrants, t 0 represents the calibration moment, S i k represents the correction coefficient of the k-th quadrant in the i-th cross-section, represents the first mean current of the i-th cross-section at the calibration moment, R i k (t 0 ) represents the calibration current measured by the ex-core neutron detector in the k-th quadrant of the i-th cross-section.

[0109] In this embodiment, by normalizing at the calibration moment, the correction coefficient of 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 currents of the ex-core neutron detectors in each quadrant are unified. When there is no uneven power distribution in the reactor core, the difference in the output currents of the ex-core neutron detectors caused by the difference in the sensitivity coefficients of the ex-core neutron detectors between each quadrant can be smoothed out through the correction coefficient, so as to more accurately identify abnormalities in the reactor core.

[0110] In some embodiments, calculating the parameter value of the deviation monitoring parameter corresponding to each cross-section according to the set of corrected currents corresponding to each cross-section in step S103 may include, but is not limited to, the following:

[0111] Calculate the mean value of the corrected currents in the set of corrected currents corresponding to each cross-section to obtain the second mean current corresponding to the cross-section;

[0112] For each corrected current in the set of corrected currents corresponding to the cross-section, perform the following: obtain the absolute value of the difference between the corrected current and the second mean current; take the ratio of the absolute value to the second mean current as the first value; take the product of the first value and the target power as the second value, where the target power is the thermal power measured for the reactor core at the first moment;

[0113] Calculate the mean value according to the second value corresponding to each corrected current to obtain the parameter value of the deviation monitoring parameter corresponding to the cross-section.

[0114] In some implementation manners, first correct the original current according to the correction coefficient corresponding to each quadrant in each cross-section to obtain the corrected current, and the corrected currents corresponding to the original currents in the same cross-section belong to the same set of corrected currents.

[0115] Specifically, correcting the original current according to the correction coefficient corresponding to each quadrant in each cross-section to obtain the corrected current can be expressed by the following formula:

[0116]

[0117] Where represents the corrected current in the k-th quadrant of the i-th cross-section at time t, R i k represents the original current in the k-th quadrant of the i-th cross-section at time t, S i k represents the correction coefficient in the k-th quadrant of the i-th cross-section, and t represents time t.

[0118] In this implementation manner, due to the symmetry of the radial power of the reactor core, the variation amplitudes of the currents of the off-core neutron detectors after correction in each quadrant are basically the same over time. Only when the symmetry of the core power changes or the signals of the off-core neutron detectors are abnormal, there will be a deviation between the responses after correction in each quadrant. Therefore, in this embodiment, it is determined whether there is uneven distribution of the reactor core or abnormal signals of the off-core neutron detectors by monitoring the relative deviation degree of the corrected current of the off-core neutron detector in the k-th quadrant of the same cross-section from the mean value of the corrected currents of the off-core neutron detectors in the k quadrants.

[0119] Specifically, according to the set of corrected currents corresponding to each cross-section, calculate the mean current corresponding to each cross-section, that is, the second mean current. For each corrected current in the set of corrected currents corresponding to each cross-section: calculate the absolute value of the difference between the corrected current and the second mean current, take the ratio of the absolute value to the second mean current as the first value, and take the product of the first value and the thermal power measured for the reactor core at the first moment as the second value. Calculate the mean value according to the second values of the corrected currents in each quadrant of the same cross-section to obtain the parameter value of the deviation monitoring parameter for this cross-section.

[0120] The second mean current corresponding to each cross-section can be calculated by the following formula:

[0121]

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

[0123] The parameter value of the deviation monitoring parameter for each cross-section can be calculated by the following formula:

[0124]

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

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

[0127] In formula (10), since the absolute value of the output current of the ex-core neutron detector at low power is smaller, when affected by interference signals of the same absolute value magnitude, the degree of deviation is easily amplified. Therefore, by multiplying the thermal power of the reactor core, the problem that the degree of deviation is amplified at low power is reduced, so that the deviation monitoring parameter has a certain tolerance rate at low power, avoiding false alarm triggering.

[0128] In this embodiment, taking the mean current of the set of corrected currents corresponding to each cross-section as a reference can more accurately identify the corrected currents that deviate from the normal range. By calculating the relative deviation degree of the corrected current of the ex-core neutron detector in the k-th quadrant of the same cross-section compared with the mean value of the corrected currents of the ex-core neutron detectors in k quadrants, a more accurate deviation monitoring parameter value can be obtained, improving the recognition accuracy of reactor core anomalies.

[0129] In some embodiments, after correcting each of the original currents by using the correction coefficient corresponding to the quadrant of the original current obtained in advance to obtain the corrected current value corresponding to each of the original currents in step S102, before determining that there is an abnormality in the reactor core 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 in step S104, the method for identifying an abnormality of an out-of-core neutron detector proposed by the embodiments of the present application may include but is not limited to the following:

[0130] Taking the sum of the corrected currents corresponding to each of the original currents as a third value;

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

[0132] For each of the cross-sections, perform the following processing:

[0133] Determining the target threshold corresponding to the cross-section according to the ratio of the fifth value to the second average current, where 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 out-of-core neutron detector is usually designed in a multi-segmental manner axially, and is usually designed symmetrically up and down along the mid-plane of the axial height of the reactor core, and since the axial power distribution of the reactor 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 , and the target threshold SET i can be expressed by the following formula:

[0135]

[0136] where SET i represents the target threshold of the i-th cross-section, e represents an adjustable constant, and e can be set according to the actual operating margin of the nuclear power plant and the actual situation of the alarm capability.

[0137] In this embodiment, is denoted as the third value, and is denoted as the fifth value.

[0138] In this implementation, the denominator part for calculating the target threshold corresponding to each cross-section is kept consistent with the denominator form for calculating the deviation monitoring parameter corresponding to the cross-section, so as to ensure that when the axial power of the reactor core is non-uniform, the allowable deviation degree between the deviation monitoring parameter and the target threshold is consistent, that is, when the deviation monitoring parameter of a cross-section is small, the target threshold corresponding to the cross-section is also small; through the target threshold corresponding to each cross-section, the abnormality of the reactor core power can be identified more quickly and accurately.

[0139] In some embodiments, after calculating the parameter values of the deviation monitoring parameters corresponding to each of the cross-sections according to the set of correction currents corresponding to each of the cross-sections in step S103, the method for identifying anomalies of the ex-core neutron detector proposed in the embodiments of the present application may include but is not limited to the following:

[0140] If the parameter values of the deviation monitoring parameters corresponding to each of the i cross-sections are less than the target threshold corresponding to the cross-section, it is determined that there are no anomalies in the reactor core and the ex-core neutron detector.

[0141] In this implementation, if, among the i cross-sections of the reactor core, the parameter values of the deviation monitoring parameters corresponding to each cross-section are all less than the target threshold corresponding to the cross-section, it indicates that the power distribution of the reactor core is uniform, and thus it is determined that there are no anomalies 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, in step S104, if there is a target cross-section among the i cross-sections whose parameter value of the deviation monitoring parameter is greater than or equal to the target threshold corresponding to the target cross-section, and it is determined that there is an anomaly in the reactor core at the target cross-section or there is an anomaly in the ex-core neutron detector at the target cross-section, the method for identifying anomalies of the ex-core neutron detector proposed in the embodiments of the present application may include but is not limited to the following:

[0144] Give an early warning according to the target cross-section and output the deviation monitoring parameter corresponding to the target cross-section.

[0145] In this implementation, when there is a parameter value of the deviation monitoring parameter corresponding to a cross-section that is greater than or equal to the target threshold corresponding to the cross-section, this cross-section is taken as the target cross-section, and an early warning is given for the abnormal situation of the reactor core, that is, the cross-section information and the deviation monitoring parameter of the target cross-section are sent to the technical personnel so that the technical personnel can quickly locate the cross-section where the reactor core has an anomaly or the cross-section where the ex-core neutron detector has an anomaly.

[0146] The above embodiments are described below by means of experimental verification:

[0147] To verify the effectiveness of this method, the present invention takes a typical operating pressurized water reactor technology as an example (the design of the ex-core neutron detector is a 4-channel design in the radial direction and a 4-section design in the axial direction, that is, it includes 4 cross-sections), and verifies the implementation effect of the technical solution proposed by the present invention, and verifies the alarm margin situation during normal operation and the alarm ability under abnormal conditions respectively.

[0148] Such asFigure 4 As shown in the figure, taking the measured data of the response of the out-of-core detectors in a single quadrant of a certain third-generation nuclear power unit during operation at 50% FP as an example, the operating margin of the distance alarm setting value SET(t) of the monitoring parameter D(t) during operation is verified. The constant e in the SET(t) setting value takes a value of 2%. The verification results are as Figure 4 shown. It can be seen from the results that there will be no false alarms during operation, and there is sufficient operating margin.

[0149] As Figure 5 shown, based on the measured operation data, the size relationship between the monitoring parameter D(t) and the alarm setting value SET(t) when the response of the out-of-core detector decays by 20% at time t is virtually constructed. The results show that a 20% decay of the out-of-core detector can effectively trigger an alarm, and it can identify the abnormal power of the reactor core and the abnormality of the out-of-core neutron detector.

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

[0151] Figure 6 is a schematic structural diagram of an out-of-core neutron detector abnormality recognition device provided by an embodiment of the present application. Please refer to Figure 6 , an embodiment of the present application also provides an out-of-core neutron detector abnormality recognition device 800. The reactor core includes i cross-sections, and each cross-section includes k quadrants symmetrically distributed. i is a positive integer, and k is an integer greater than 1. The out-of-core neutron detector abnormality recognition device 800 can implement the above-mentioned out-of-core neutron detector abnormality recognition method. The out-of-core neutron detector abnormality recognition device 800 includes:

[0152] A current acquisition module 801, configured to acquire a plurality of original currents measured by a plurality of out-of-core neutron detectors at a first moment. The out-of-core neutron detectors are arranged outside the reactor. The plurality of original currents include output currents measured by the out-of-core neutron detectors in each quadrant of each cross-section;

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

[0154] A parameter calculation module 803, configured to calculate a parameter value of the deviation monitoring parameter corresponding to each cross-section according to the corrected current set corresponding to each cross-section;

[0155] The first determination module 804 is configured to determine that there is an abnormality in the reactor core at the target cross-section or there is an abnormality in the off-core neutron detector at the target cross-section if the parameter value of the deviation monitoring parameter corresponding to the target cross-section among the i cross-sections is greater than or equal to the target threshold corresponding to the target cross-section;

[0156] The second determination module 805 is configured to determine whether there is an abnormality in the reactor core at the target cross-section by means of core power distribution measurement;

[0157] The third determination module 806 is configured to determine that there is an abnormality in the off-core neutron detector at the target cross-section if there is no abnormality in the reactor core at the target cross-section.

[0158] In some embodiments, the off-core neutron detector abnormality identification device 800 further includes:

[0159] A calibration module, configured to obtain a plurality of calibration currents measured by a plurality of off-core neutron detectors at a preset calibration moment, and the plurality of calibration currents include output currents measured by the off-core neutron detector in each quadrant of each of the cross-sections;

[0160] A first processing module, configured to perform the following processing on each cross-section;

[0161] Calculate the mean value of the calibration currents corresponding to the cross-section to obtain the first mean current corresponding to the cross-section;

[0162] For each quadrant of the cross-section, perform: calculate a correction coefficient for the quadrant according to the mean current corresponding to the cross-section and the calibration current corresponding to the quadrant.

[0163] In some embodiments, the calculation module 803 includes:

[0164] A first calculation sub-module, configured to calculate the mean value of the correction currents in the correction current set corresponding to each of the cross-sections to obtain the second mean current corresponding to the cross-section;

[0165] A second calculation sub-module, configured to perform, for each correction current in the correction current set corresponding to the cross-section: obtain the absolute value of the difference between the correction current and the second mean current; use the ratio of the absolute value to the second mean current as a first value; use the product of the first value and the target power as a second value, where the target power is the thermal power measured for the reactor core at the first moment;

[0166] A third calculation sub-module, configured to calculate the mean value according to the second values 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 off - core neutron detector anomaly recognition device 800 further includes:

[0168] An addition module, configured to use the sum of the corrected currents corresponding to each of the original currents as a third value;

[0169] A ratio module, configured to use the ratio of the third value to a fourth value as a fifth value, where the fourth value is the product of i and k;

[0170] A second processing module, configured to perform the following processing for each of the cross - sections:

[0171] Determine a target threshold corresponding to the cross - section according to the ratio of the fifth value to the second average current, where the second average current is the average of each corrected current in the corrected current set corresponding to the cross - section.

[0172] In some embodiments, the off - core neutron detector anomaly recognition device 800 further includes:

[0173] A second judgment module, configured to determine that there is no anomaly in the reactor core and the off - core 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 off - core neutron detector anomaly recognition device 800 further includes:

[0175] An early warning module, configured to give an early warning according to the target cross - section and output the deviation monitoring parameter corresponding to the target cross - section.

[0176] The specific implementation manner of the off - core neutron detector anomaly recognition device 800 is basically the same as the specific embodiments of the above - mentioned off - core neutron detector anomaly recognition method, and will not be elaborated here.

[0177] The out-of-core neutron detector anomaly recognition device 800 obtains multiple original currents measured by multiple out-of-core neutron detectors, and corrects the original currents according to the correction coefficients of the quadrants corresponding to the pre-obtained original currents to obtain corrected currents, so as to eliminate measurement errors caused by factors such as detector position or environment, thereby improving the subsequent recognition accuracy of reactor core anomalies. The corrected currents corresponding to the original currents in the same cross-section belong to the same corrected current set. The parameter values of the deviation monitoring parameters corresponding to each cross-section are calculated according to the corrected current set corresponding to each cross-section. If the parameter values of the deviation monitoring parameters corresponding to the target cross-section in i cross-sections are 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 there is an anomaly in the out-of-core neutron detector at the target cross-section. Then, further judgment is made on whether there is an anomaly in the reactor core at the target cross-section through the reactor core power distribution measurement method. If there is no anomaly in the reactor core at the target cross-section, it is determined that the out-of-core neutron detector corresponding to the cross-section is abnormal; in this way, the cross-section where the reactor core anomaly occurs and the corresponding out-of-core neutron detector can be accurately located.

[0178] An embodiment of this application also provides an electronic device. The electronic device includes a memory and a processor. The memory stores a computer program, and when the processor executes the computer program, it implements the above-mentioned out-of-core neutron detector anomaly recognition method. The electronic device can be any intelligent terminal including a desktop computer, a tablet computer, a mobile phone, a vehicle-mounted computer, etc.

[0179] Please refer to Figure 7 , Figure 7 which is a schematic diagram of the hardware structure of the electronic device provided by the embodiment of this application. The electronic device includes:

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

[0181] A memory 902, which can be implemented in forms such as a read-only memory (ROM), a static storage device, a dynamic storage device, or a random access memory (RAM). The memory 902 can store an operating system and other application programs. When implementing the technical solutions provided by the embodiments of this specification through software or firmware, the relevant program codes are stored in the memory 902 and are called by the processor 901 to execute the out-of-core neutron detector anomaly recognition method of the embodiments of this application;

[0182] An input / output interface 903 for implementing information input and output;

[0183] A communication interface 904 for implementing communication interaction between this device and other devices, which can implement communication through wired means (such as USB, network cable, etc.) or through wireless means (such as mobile network, WIFI, Bluetooth, etc.);

[0184] A bus 905 for transmitting information between various components of the device (such as a processor 901, a memory 902, an input / output interface 903, and a communication interface 904);

[0185] Among them, the processor 901, the memory 902, the input / output interface 903, and the communication interface 904 achieve communication connections with each other inside the device through the bus 905.

[0186] The embodiment of the present application also provides a computer-readable storage medium, which stores a computer program. When the computer program is executed by a processor, it implements the above-mentioned method for abnormal identification of an off-heap neutron detector.

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

[0188] The method, device, electronic device and medium for abnormal identification of an in-core neutron detector provided by an embodiment of the present application obtain multiple original currents measured by multiple in-core neutron detectors, and correct the original currents according to the correction coefficients corresponding to the quadrants of the pre-obtained original currents to obtain corrected currents, so as to eliminate measurement errors caused by factors such as detector position or environment, thereby improving the subsequent identification accuracy of reactor core anomalies. The corrected currents corresponding to the original currents in the same cross-section belong to the same corrected current set. Calculate the parameter values of the deviation monitoring parameters corresponding to each cross-section according to the corrected current set corresponding to each cross-section. If the parameter value of the deviation monitoring parameter corresponding to the target cross-section in the i cross-sections 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 there is an anomaly in the in-core neutron detector at the target cross-section. Then, further determine whether there is an anomaly in the reactor core at the target cross-section through the reactor core power distribution measurement method. If there is no anomaly in the reactor core at the target cross-section, it is determined that the in-core neutron detector corresponding to the cross-section is abnormal; in this way, the cross-section where the reactor core anomaly occurs and the corresponding in-core neutron detector can be accurately located.

[0189] The embodiments described in the embodiments of the present application are for more clearly explaining the technical solutions of the embodiments of the present application, and do not constitute a limitation on the technical solutions provided by the embodiments of the present application. Those skilled in the art know that with the evolution of technology and the emergence of new application scenarios, the technical solutions provided by the embodiments of the present application are equally applicable to similar technical problems.

[0190] Those skilled in the art can understand that the technical solutions shown in the figures do not constitute a limitation on the embodiments of the present application, and may include more or fewer steps than shown in the figures, or combine some 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 separated, that is, they may be located in one place, or may be distributed to multiple network units. Some or all of the modules can be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0192] Those of ordinary skill in the art can understand that all or some of the steps in the methods disclosed above, and the functional modules / units in the systems and devices can be implemented as software, firmware, hardware and their appropriate combinations.

[0193] In the description of this application and the above-mentioned accompanying drawings, terms such as "first", "second", "third", "fourth", etc. (if any) are used to distinguish similar objects and are not necessarily used to describe a specific order or sequence. It should be understood that the data used in this way can be interchanged under appropriate circumstances so that the embodiments of the application described herein can be implemented in an order different from those illustrated or described herein. In addition, the terms "comprising" and "having" and any variations thereof are intended to cover non-exclusive inclusion. For example, a process, method, system, product or device that comprises a series of steps or units does not necessarily have to be limited to those steps or units clearly listed, but may include other steps or units not clearly listed or inherent to these processes, methods, products or devices.

[0194] It should be understood that in this application, "at least one (item)" means one or more, and "a plurality" means two or more. "And / or" is used to describe the association relationship of associated objects and indicates that three relationships may exist. For example, "A and / or B" may mean: only A exists, only B exists, and both A and B exist at the same time. Among them, A and B can be singular or plural. The character " / " generally indicates that the associated objects before and after are in an "or" relationship. "At least one (one) of the following" or its similar expression refers to any combination of these items, including any combination of single items (ones) or plural items (ones). For example, at least one (one) of a, b, or c can mean: 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 several embodiments provided in this application, it should be understood that the disclosed devices and methods can be implemented in other ways. For example, the device embodiments described above are merely illustrative. For example, the above-mentioned division of units is only a logical function division. In actual implementation, there may be other division methods. For example, multiple units or components can be combined or integrated into another system, or some features can be ignored or not executed. Another point is that the displayed or discussed coupling or direct coupling or communication connection between each other can be through some interfaces, and the indirect coupling or communication connection of devices or units can be in electrical, mechanical or other forms.

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

[0197] In addition, in each embodiment of the present application, each functional unit can be integrated into one processing unit, or each unit can exist physically alone, or two or more units can be integrated into one unit. The above-mentioned integrated unit can be implemented in the form of hardware or in the form of a software functional unit.

[0198] If the integrated unit is implemented in the form of 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 the present application, in essence, or the part that contributes to the prior art, or all or part of this 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 for causing a computer device (which can be a personal computer, a server, or a network device, etc.) to execute all or part of the steps of the methods in each embodiment of the present application. The foregoing storage medium includes: various media that can store programs, such as USB flash drives, mobile hard disks, read-only memory (ROM), random access memory (RAM), magnetic disks, or optical discs.

[0199] The preferred embodiments of the embodiments of the present application have been described above with reference to the accompanying drawings, which does not limit the scope of rights of the embodiments of the present application. Any modification, equivalent replacement, and improvement made by those skilled in the art without departing from the scope and essence of the embodiments of the present application shall be within the scope of rights of the embodiments of the present application.

Claims

1. A method for identifying abnormality of an out-of-core neutron detector, characterized in that: The ex-core neutron detectors are evenly arranged outside the reactor, the core of the reactor includes i sections, each section includes k quadrants that are symmetrically distributed, i is a positive integer, and k is an integer greater than 1, and the method includes: Acquire a plurality of original currents measured by a plurality of ex-core neutron detectors at a first moment, wherein the plurality of original currents include output currents measured by the ex-core neutron detectors in each quadrant of each cross section; Each of the original currents is corrected by using the correction coefficient of the quadrant corresponding to the original current obtained in advance, so as to obtain a corrected current corresponding to each of the original currents, and the corrected currents corresponding to the original currents at the same cross section belong to the same corrected current set; Calculating the parameter value of the deviation monitoring parameter corresponding to each of the cross sections according to the correction current set corresponding to each of the cross sections; If there is a target section among the i sections whose parameter value of the deviation monitoring parameter is greater than or equal to the target threshold corresponding to the target section, it is determined that the reactor core has an abnormality at the target section or the ex-core neutron detector has an abnormality at the target section; Determining whether there is an abnormality in the reactor core at a target cross section by measuring the core power distribution; If there is no abnormality in the target cross section of the reactor core, it is determined that there is an abnormality in the target cross section of the ex-core neutron detector.

2. The method according to claim 1, characterized in that Before obtaining a plurality of original currents measured by a plurality of out-of-core neutron detectors, the method further comprises: Acquire a plurality of calibration currents measured by a plurality of ex-core neutron detectors at a preset calibration time, wherein the plurality of calibration currents include output currents measured by the ex-core neutron detectors in each quadrant of each of the cross sections; The following processing is performed on each section; Performing mean calculation on the calibration current corresponding to the cross section to obtain a first mean current corresponding to the cross section; For each quadrant of the cross section, executing: calculating a correction coefficient of the quadrant according to a mean current corresponding to the cross section and a calibration current corresponding to the quadrant.

3. 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 according to the corrected current set corresponding to each cross section includes: Calculating the mean of the corrected currents in the corrected current set corresponding to each of the cross sections to obtain a second mean current corresponding to the cross section; For each correction current in the correction current set corresponding to the cross section, performing: obtaining an absolute value of a difference between the correction current and a second mean current; taking a ratio of the absolute value to the second mean current as a first value; taking a product of the first value and a target power as a second value, wherein the target power is a thermal power measured for the reactor core at the first moment; The mean value is calculated according to 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.

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

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

6. The method according to claim 1, characterized in that After determining that the reactor core has an abnormality at the target section or the ex-core neutron detector has an abnormality at the target section if the parameter value of the deviation monitoring parameter corresponding to the target section among the i sections is greater than or equal to the target threshold corresponding to the target section, the method further includes: An early warning is issued according to the target cross section, and a deviation monitoring parameter corresponding to the target cross section is output.

7. An abnormality identification device for an out-of-core neutron detector, characterized in that: The ex-core neutron detectors are evenly arranged outside the reactor, the core of the reactor includes i sections, each section includes k quadrants that are symmetrically distributed, i is a positive integer, k is an integer greater than 1, and the device includes: A current acquisition module, used for acquiring, at a first moment, a plurality of original currents measured by a plurality of ex-core neutron detectors, wherein the ex-core neutron detectors are arranged outside the reactor, and the plurality of original currents include output currents measured by the ex-core neutron detectors in each quadrant of each cross section; A current correction module, used to correct each of the original currents using a correction coefficient of the quadrant corresponding to the original current obtained in advance, to obtain a corrected current corresponding to each of the original currents, wherein the corrected currents corresponding to the original currents at the same cross section belong to the same corrected current set; A parameter calculation module, used for calculating the parameter value of the deviation monitoring parameter corresponding to each of the cross sections according to the correction current set corresponding to each of the cross sections; A first judgment module is used to determine that the reactor core has an abnormality at the target section or the ex-core neutron detector has an abnormality at the target section if the parameter value of the deviation monitoring parameter corresponding to the target section among the i sections is greater than or equal to the target threshold value corresponding to the target section; A second judgment module is used to judge whether there is an abnormality in the reactor core at a target cross section by measuring the core power distribution; The third judgment module is used to determine that the external neutron detector has an abnormality at the target cross section if there is no abnormality at the target cross section of the reactor core.

8. An electronic device, characterized in that: The electronic device includes a memory and a processor, the memory stores a computer program, and the processor implements the abnormality identification method of the ex-pile neutron detector according to any one of claims 1 to 6 when executing the computer program.

9. A computer-readable storage medium storing a computer program, characterized in that: When the computer program is executed by a processor, the abnormality identification method of the ex-core neutron detector according to any one of claims 1 to 6 is implemented.

10. A computer program product, characterized in that When the instructions in the computer program product are executed by a processor of an electronic device, the electronic device executes the method for identifying anomalies of an out-of-core neutron detector as described in any one of claims 1 to 6.

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