Fault handling method and device for nuclear power plant

Abstract

This application relates to a fault handling method and apparatus for a nuclear power plant, and relates to the field of nuclear power technology. The method comprises obtaining detection signal sets corresponding to electrical partitions within a pressurized water reactor (PWR), determining target failure modes and temperature correlation values ​​for the PWR based on each detection signal set, and performing fault handling on the PWR based on the target failure modes and temperature correlation values. This method can improve the safety of nuclear power operations.

Description

Technical Field

[0001] The present application relates to the field of nuclear power technology, and in particular to a fault handling method and device for a nuclear power plant. Background Art

[0002] With the development of nuclear power technology, in order to ensure the safe operation of pressurized water reactors in nuclear power plants, it is necessary to detect the operation of neutron detectors in pressurized water reactors, and to repair or replace the faulty neutron detectors if there are any faults in the neutron detectors.

[0003] However, since the neutron detectors are arranged inside the pressurized water reactor, the current fault handling method can only be used after the pressurized water reactor operation cycle is completed and the cover is opened during the refueling period to repair or replace the neutron detectors, which reduces the safety of nuclear power operation. Summary of the Invention

[0004] Based on this, it is necessary to provide a fault handling method and device for a nuclear power plant that can improve the safety of nuclear power operation in response to the above technical problems.

[0005] In a first aspect, the present application provides a method for handling a fault in a nuclear power plant. The method comprises:

[0006] Acquire a detection signal set corresponding to each electrical partition in the pressurized water reactor; wherein the detection signal set corresponding to each electrical partition includes a detection signal detected by a neutron detector contained in the electrical partition;

[0007] Determining target failure modes and temperature-related values ​​of the pressurized water reactor based on each detection signal set; wherein the temperature-related values ​​include deviation from nucleate boiling ratio (DNBR) and / or linear power density (LPD);

[0008] Fault handling of pressurized water reactors is performed based on target failure modes and temperature correlation values.

[0009] In one embodiment, determining a target failure mode of a pressurized water reactor based on each detection signal set includes:

[0010] According to each detection signal set, a core power distribution corresponding to the pressurized water reactor is constructed; according to each core power value in the core power distribution, a target failure mode of the pressurized water reactor is determined.

[0011] In one embodiment, determining a target failure mode of a pressurized water reactor based on each core power value in the core power distribution includes:

[0012] According to each core power value in the core power distribution, the failure status of the neutron detector in each electrical partition in the pressurized water reactor is determined; according to the failure status of the neutron detector in each electrical partition in the pressurized water reactor, the target failure mode of the pressurized water reactor is determined.

[0013] In one embodiment, before performing fault processing on the pressurized water reactor according to the target failure mode and the temperature correlation value, the method further includes:

[0014] According to the fault condition of the neutron detector, a probe fault value is determined; when the probe fault value is greater than a quantity threshold, the pressurized water reactor is shut down.

[0015] In one embodiment, fault processing is performed on a pressurized water reactor according to a target failure mode and a temperature correlation value, including:

[0016] A pressurized water reactor (PWR) trip protection threshold is determined according to a target failure mode, wherein the trip protection threshold includes a DNBR threshold and / or an LPD threshold; and fault processing is performed on the PWR according to the trip protection threshold and a temperature correlation value.

[0017] In one embodiment, fault processing of a pressurized water reactor is performed based on a trip protection threshold and a current measurement value of the pressurized water reactor, including:

[0018] When the magnitude relationship between the shutdown protection threshold and the temperature correlation value satisfies the shutdown processing condition, the pressurized water reactor is shut down.

[0019] In one embodiment, the method further comprises:

[0020] According to the arrangement scheme of the neutron detectors in the pressurized water reactor, the neutron detectors in the pressurized water reactor are divided to obtain electrical partitions, and the electrical partitions cross-penetrate each other; wherein each electrical partition includes at least one neutron detector.

[0021] In a second aspect, the present application also provides a fault handling device for a nuclear power plant. The device comprises:

[0022] A signal acquisition module, configured to acquire a detection signal set corresponding to each electrical partition in the pressurized water reactor; wherein the detection signal set corresponding to each electrical partition includes a detection signal detected by a neutron detector contained in the electrical partition;

[0023] a determination module, configured to determine a target failure mode and a temperature-related value of the pressurized water reactor based on each detection signal set; wherein the temperature-related value includes a deviation from nucleate boiling ratio (DNBR) and / or a linear power density (LPD);

[0024] The fault processing module is used to perform fault processing on the pressurized water reactor according to the target failure mode and temperature correlation value.

[0025] In a third aspect, the present application further provides a computer device. The computer device includes a memory and a processor, wherein the memory stores a computer program, and when the processor executes the computer program, the following steps are performed:

[0026] Acquire a detection signal set corresponding to each electrical partition in the pressurized water reactor; wherein the detection signal set corresponding to each electrical partition includes a detection signal detected by a neutron detector contained in the electrical partition;

[0027] Determining target failure modes and temperature-related values ​​of the pressurized water reactor based on each detection signal set; wherein the temperature-related values ​​include deviation from nucleate boiling ratio (DNBR) and / or linear power density (LPD);

[0028] Fault handling of pressurized water reactors is performed based on target failure modes and temperature correlation values.

[0029] In a fourth aspect, the present application further provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements the following steps:

[0030] Acquire a detection signal set corresponding to each electrical partition in the pressurized water reactor; wherein the detection signal set corresponding to each electrical partition includes a detection signal detected by a neutron detector contained in the electrical partition;

[0031] Determining target failure modes and temperature-related values ​​of the pressurized water reactor based on each detection signal set; wherein the temperature-related values ​​include deviation from nucleate boiling ratio (DNBR) and / or linear power density (LPD);

[0032] Fault handling of pressurized water reactors is performed based on target failure modes and temperature correlation values.

[0033] In a fifth aspect, the present application further provides a computer program product. The computer program product includes a computer program that, when executed by a processor, implements the following steps:

[0034] Acquire a detection signal set corresponding to each electrical partition in the pressurized water reactor; wherein the detection signal set corresponding to each electrical partition includes a detection signal detected by a neutron detector contained in the electrical partition;

[0035] Determining target failure modes and temperature-related values ​​of the pressurized water reactor based on each detection signal set; wherein the temperature-related values ​​include deviation from nucleate boiling ratio (DNBR) and / or linear power density (LPD);

[0036] Fault handling of pressurized water reactors is performed based on target failure modes and temperature correlation values.

[0037] The aforementioned nuclear power plant fault handling method and device introduces failure modes and determines the target failure modes and temperature-related values ​​of the PWR by acquiring detection signal sets corresponding to each electrical partition within the PWR. Subsequently, fault handling is performed on the PWR based on these target failure modes and temperature-related values. Compared to related technologies that cannot accurately determine whether the PWR is operating safely in the event of a neutron detection failure within the PWR, this method accurately determines whether the PWR is operating safely based on the target failure modes and temperature-related values ​​of the PWR, thereby improving the safety of PWR operation. BRIEF DESCRIPTION OF THE DRAWINGS

[0038] Figure 1 1 is a flow chart of a method for handling a fault in a nuclear power plant according to an embodiment;

[0039] Figure 2 A schematic diagram of a process for determining a target failure mode in one embodiment;

[0040] Figure 3 A schematic diagram of a fault handling process in one embodiment;

[0041] Figure 4 A schematic diagram of dividing electrical zones in one embodiment;

[0042] Figure 5 is a flow chart of a fault handling method for a nuclear power plant in another embodiment;

[0043] Figure 6 is a structural block diagram of a fault handling device for a nuclear power plant in one embodiment;

[0044] Figure 7 is a structural block diagram of a fault handling device for a nuclear power plant in another embodiment;

[0045] Figure 8 is a structural block diagram of a fault handling device for a nuclear power plant in yet another embodiment;

[0046] Figure 9 FIG. 1 is a diagram showing the internal structure of a computer device in one embodiment. DETAILED DESCRIPTION

[0047] In order to make the purpose, technical solutions and advantages of this application more clear, the following further describes this application in detail with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain this application and are not intended to limit this application.

[0048] With the development of nuclear power technology, in order to ensure the safe operation of pressurized water reactors in nuclear power plants, it is necessary to detect the operation of neutron detectors in pressurized water reactors, and to repair or replace the faulty neutron detectors if there are any faults in the neutron detectors.

[0049] However, since the neutron detectors are arranged inside the pressurized water reactor, the current fault handling method can only be used after the pressurized water reactor operation cycle is completed and the cover is opened during the refueling period to repair or replace the neutron detectors, which reduces the safety of nuclear power operation.

[0050] Based on this, in one embodiment, Figure 1 As shown, a method for handling a fault in a nuclear power plant is provided, which specifically includes the following steps:

[0051] S101, obtaining a detection signal set corresponding to each electrical partition in a pressurized water reactor.

[0052] Among them, electrical partitioning refers to the division of each neutron detector according to the layout plan of the neutron detectors in the pressurized water reactor; the detection signal set corresponding to each electrical partition includes the detection signals detected by the neutron detectors contained in the electrical partition.

[0053] Optionally, the neutron detectors in the pressurized water reactor may be divided according to the rule that the neutron detectors in each electrical partition are evenly distributed in the pressurized water reactor and according to the arrangement of the neutron detectors in the pressurized water reactor, thereby obtaining the electrical partitions.

[0054] Optionally, in order to ensure the safe operation of the pressurized water reactor, the time interval for obtaining the detection signal can be set in advance, and when the detection signal acquisition time is reached, a detection instruction is sent to the neutron detectors in each electrical partition; then, for each neutron detector, when the neutron detector receives the detection instruction, it will detect the operation status of the pressurized water reactor, and then generate a detection signal and feedback.

[0055] Furthermore, for each electrical partition, after receiving the detection signals fed back by all neutron detectors in the electrical partition, a detection signal set corresponding to the electrical partition can be generated.

[0056] For example, in a 177-core pressurized water reactor (PWR), 42 neutron detectors are deployed within the PWR. Each neutron detector has seven probes along the axial direction, allowing these detectors to be divided into four independent electrical partitions. As can be understood, since the neutron detectors in each electrical partition are evenly distributed within the PWR, each electrical partition can detect the entire PWR. Therefore, using the detection signal sets corresponding to each electrical partition, the core power at the locations of the 42 neutron detectors within the PWR can be reconstructed. This ensures the stability and accuracy of power detection even if a neutron detector in a particular electrical partition fails.

[0057] S102: Determine a target failure mode and a temperature correlation value of a pressurized water reactor according to each detection signal set.

[0058] Among them, failure mode refers to various operating modes corresponding to various fault conditions of neutron detectors in a pressurized water reactor; target failure mode refers to the current failure mode of the pressurized water reactor; temperature-related values ​​can represent the temperature in the pressurized water reactor; temperature-related values ​​include deviation from nucleate boiling ratio DNBR and / or line power density LPD. Furthermore, the deviation from nucleate boiling ratio can represent the fuel cladding temperature in the pressurized water reactor, and the line power density can represent the core temperature in the pressurized water reactor.

[0059] Optionally, after obtaining the detection signal sets corresponding to each electrical partition, each detection signal set can be input into a temperature determination model, and the temperature determination model determines the deviation from nucleate boiling ratio DNBR and the linear power density LPD of the pressurized water reactor based on each detection signal set and model parameters; or, the temperature determination model determines any value of the deviation from nucleate boiling ratio DNBR or the linear power density LPD of the pressurized water reactor based on each detection signal set and model parameters.

[0060] Furthermore, the fault status of the neutron detectors in each electrical partition can be determined based on the signal strength of the detection signal set. Subsequently, the fault status of the neutron detectors in each electrical partition can be compared with the fault status of the neutron detectors corresponding to each preset failure mode, and the target failure mode of the pressurized water reactor can be determined based on the comparison results. It is understood that in actual applications, only a maximum of 10 detectors can fail simultaneously.

[0061] For example, four failure modes can be determined based on the common failure conditions of neutron detectors in pressurized water reactors, among which, the failure condition of the neutron detector corresponding to failure mode 1 is that all neutron detectors in a certain electrical partition are faulty; the failure condition of the neutron detector corresponding to failure mode 2 is that all probes on a certain neutron detector are faulty; the failure condition of the neutron detector corresponding to failure mode 3 is that one or more probes on neutron detectors are faulty; the failure condition of the neutron detector corresponding to failure mode 4 is that all neutron detectors in a certain electrical partition are faulty, and one or more probes on neutron detectors are faulty.

[0062] Accordingly, in some embodiments, determining the failure mode may include the following steps: Step 1, after determining the fault condition of the neutron detectors in each electrical partition, it can be determined based on the fault condition of the neutron detectors whether all the neutron detectors in only one electrical partition are faulty; if so, the target failure mode of the pressurized water reactor is determined to be failure mode 1; if not, execute the following step 2.

[0063] Step 2: determine whether all probes on a certain neutron detector are faulty. If so, determine that the target failure mode of the pressurized water reactor is failure mode 2; if not, execute the following step 3.

[0064] Step 3: Determine whether there is a probe failure on one or more neutron detectors. If so, determine that the target failure mode of the pressurized water reactor is failure mode 3; if not, execute the following step 4.

[0065] Step 4: Determine whether all neutron detectors in a certain electrical partition are faulty and whether there is a probe failure on one or more neutron detectors. If so, determine that the target failure mode of the pressurized water reactor is failure mode 4.

[0066] S103: Perform fault processing on the pressurized water reactor according to the target failure mode and the temperature correlation value.

[0067] Optionally, the temperature correlation value of the pressurized water reactor can be input into a processing model obtained by training based on the target failure mode, and the processing model outputs a fault processing method for the pressurized water reactor according to the temperature correlation value and model parameters.

[0068] It is understood that in some embodiments, to ensure safe operation of the PWR, before performing fault processing on the PWR based on the target failure mode and temperature correlation value, a probe failure value can be determined based on the neutron detector failure condition. Subsequently, a determination is made as to whether the probe failure value is greater than a preset threshold. If the probe failure value is greater than the preset threshold, the PWR is shut down. If the probe failure value is not greater than the preset threshold, fault processing is performed on the PWR based on the target failure mode and temperature correlation value.

[0069] The aforementioned nuclear power plant fault handling method introduces failure modes and determines the target failure modes and temperature correlation values ​​of the PWR by acquiring detection signal sets corresponding to each electrical partition within the PWR. Subsequently, fault handling is performed on the PWR based on these target failure modes and temperature correlation values. Compared to related technologies that cannot accurately determine whether the PWR is operating safely in the event of a neutron detection failure within the PWR, this method accurately determines whether the PWR is operating safely based on the target failure modes and temperature correlation values ​​within the PWR, thereby improving the safety of PWR operation.

[0070] In order to ensure the accuracy of the target failure mode determination, based on the above embodiment, this embodiment provides an optional method for determining the target failure mode, such as Figure 2 As shown, the specific steps include:

[0071] S201: Construct a core power distribution corresponding to a pressurized water reactor according to each detection signal set.

[0072] Among them, the core power distribution is used to indicate the distribution of core power in a pressurized water reactor.

[0073] Optionally, the core power distribution for the pressurized water reactor can be constructed based on the correlation between each detection signal in each detection signal set and the location of the neutron detector. For example, for the same location, the detection signals related to that location in the detection signal sets corresponding to each electrical partition can be fused.

[0074] It is understandable that, since the neutron detectors in each electrical partition are evenly distributed, even if all the neutron detectors in a certain electrical partition fail, the core power distribution corresponding to the pressurized water reactor can be constructed through other neutron detectors.

[0075] S202: Determine a target failure mode of the pressurized water reactor according to each core power value in the core power distribution.

[0076] An optional approach is to input each core power value in the core power distribution into a mode determination model, and the mode determination model determines the target failure mode of the pressurized water reactor based on each core power value and model parameters.

[0077] Another optional method is to determine the failure status of neutron detectors in each electrical partition in the pressurized water reactor based on the core power values ​​in the core power distribution; then, determine the target failure mode of the pressurized water reactor based on the failure status of neutron detectors in each electrical partition in the pressurized water reactor.

[0078] It is understandable that when there is a fault in the probe of the neutron detector, the detection signal obtained by the faulty probe is 0. Therefore, when constructing the core power distribution corresponding to the pressurized water reactor, the core power value corresponding to the probe will be lowered. At this time, the fault status of the neutron detector in each electrical partition in the pressurized water reactor can be determined based on the core power values ​​in the core power distribution.

[0079] Alternatively, in order to facilitate the observation of the failure condition of the neutron detector, when constructing the core power distribution corresponding to the pressurized water reactor, for the core power value at any position, if there is a detection signal concentration corresponding to a certain electrical partition, and the detection signal at this position is 0, then when constructing the core power distribution, the core power value at this position is directly 0; further, the failure condition of the neutron detector can be determined by observing the position where the core power value is 0 in the core power distribution.

[0080] Furthermore, after determining the failure condition of the neutron detector, the target failure mode of the pressurized water reactor can be determined based on the failure condition of the neutron detector in each electrical partition in the pressurized water reactor and the failure condition of the neutron detector corresponding to the failure mode.

[0081] In this embodiment, the core power distribution is introduced, and the target failure mode of the pressurized water reactor is determined according to each core power value in the core power distribution, which can ensure the accuracy of the determination of the target failure mode.

[0082] In order to ensure the accuracy of fault handling, based on the above embodiment, this embodiment provides an optional method for fault handling, such as Figure 3 As shown, the specific steps include:

[0083] S301: Determine a shutdown protection threshold of a pressurized water reactor according to a target failure mode.

[0084] The shutdown protection threshold refers to a value used to measure whether a pressurized water reactor requires shutdown processing; further, the shutdown protection threshold includes a DNBR threshold and / or an LPD threshold.

[0085] Optionally, a corresponding shutdown protection threshold may be pre-configured for each failure mode; subsequently, after determining the target failure mode of the pressurized water reactor, the shutdown protection threshold of the pressurized water reactor may be determined according to the target failure mode.

[0086] S302: Perform fault processing on the pressurized water reactor according to the shutdown protection threshold and the temperature correlation value.

[0087] Optionally, the shutdown protection threshold and the temperature correlation value may be compared, and then, based on the comparison result, the pressurized water reactor fault processing may be performed. For example, if the magnitude relationship between the shutdown protection threshold and the temperature correlation value satisfies the shutdown processing condition, the pressurized water reactor is shutdown.

[0088] For example, the corresponding trip protection thresholds for failure mode 1 are DNBR1 and LPD1; the corresponding trip protection thresholds for failure mode 2 are DNBR2 and LPD2; the corresponding trip protection thresholds for failure mode 3 are DNBR3 and LPD3; and the corresponding trip protection thresholds for failure mode 4 are DNBR4 and LPD4.

[0089] Furthermore, when the PWR A is in failure mode 1, the deviation from nucleate boiling ratio A of the PWR is DNBR , compared with DNBR1, if A DNBR If it is less than DNBR1, the pressurized water reactor A will be shut down; if A DNBR If the linear power density of the PWR is greater than or equal to DNBR1, LPD , compared with LPD1, if A LPD If LPD1 is greater than the PWR A, the PWR A is shut down. LPD If it is less than or equal to LPD1, the PWR is operating normally.

[0090] In this embodiment, a trip protection threshold is introduced, and fault processing is performed on the pressurized water reactor according to the trip protection threshold and the temperature correlation value, thereby ensuring the accuracy of the pressurized water reactor fault processing.

[0091] In order to ensure the accuracy of electrical partitioning, based on the above embodiments, in some embodiments, a method for dividing electrical partitions is provided. Specifically, according to the arrangement scheme of the neutron detectors in the pressurized water reactor, the neutron detectors in the pressurized water reactor are divided to obtain electrical partitions, and the electrical partitions cross-penetrate each other; wherein, each electrical partition includes at least one neutron detector.

[0092] Optionally, due to the symmetry of the distribution of core power, when placing neutron detectors in a pressurized water reactor, multiple neutron detectors can be evenly arranged in the pressurized water reactor while avoiding the location of control rods and taking into account installation constraints in actual layout scenarios.

[0093] Furthermore, after determining the arrangement of the neutron detectors in the pressurized water reactor, when dividing the neutron detectors, it is necessary to ensure that the detectors in each electrical partition are dispersed in the pressurized water reactor, that cross-penetration can occur between the electrical partitions, and that the vertical center axis of the neutron detector is parallel to the vertical center axis of the core in the pressurized water reactor, so as to ensure that each electrical partition can accurately simulate the core power distribution of the pressurized water reactor.

[0094] For example, after 14 neutron detectors are evenly arranged in a pressurized water reactor, in order to ensure that the detectors in each electrical partition are dispersed in the pressurized water reactor, that the electrical partitions can cross-penetrate, and that the vertical center axis of the neutron detector is parallel to the vertical center axis of the pressurized water reactor core, reference can be made to Figure 4 , the 14 neutron detectors are divided into group A, group B, group C and group D.

[0095] In this embodiment, the neutron detectors in the pressurized water reactor are divided according to the arrangement scheme of the neutron detectors in the pressurized water reactor, which can ensure the accuracy of the electrical partitioning and ensure the smooth progress of subsequent fault processing.

[0096] Figure 5 This is a flow chart of a method for handling a nuclear power plant fault in another embodiment. Based on the above embodiment, this embodiment provides an optional example of a method for handling a nuclear power plant fault. Figure 5 The specific implementation process is as follows:

[0097] S501: Acquire a detection signal set corresponding to each electrical partition in a pressurized water reactor.

[0098] The detection signal set corresponding to each electrical partition includes the detection signals detected by the neutron detectors contained in the electrical partition.

[0099] Optionally, according to the arrangement scheme of the neutron detectors in the pressurized water reactor, the neutron detectors in the pressurized water reactor are divided to obtain electrical partitions, and the electrical partitions cross-penetrate each other; wherein each electrical partition includes at least one neutron detector.

[0100] S502: Determine a temperature correlation value of the pressurized water reactor according to each detection signal set.

[0101] The temperature-related value includes the deviation from nucleate boiling ratio DNBR and / or the linear power density LPD.

[0102] S503: Constructing a core power distribution corresponding to the pressurized water reactor based on each detection signal set.

[0103] S504: Determine the fault status of the neutron detectors in each electrical partition in the pressurized water reactor based on each core power value in the core power distribution.

[0104] S505 , determining a target failure mode of the pressurized water reactor based on the failure conditions of the neutron detectors in each electrical partition within the pressurized water reactor.

[0105] S506: Determine a trip protection threshold of the pressurized water reactor according to the target failure mode.

[0106] The trip protection threshold includes a DNBR threshold and / or an LPD threshold.

[0107] Furthermore, before determining the shutdown protection threshold of the pressurized water reactor according to the target failure mode, a probe failure value can also be determined according to the failure condition of the neutron detector; when the probe failure value is greater than the quantity threshold, the pressurized water reactor is shut down.

[0108] S507 , when the magnitude relationship between the shutdown protection threshold and the temperature correlation value satisfies the shutdown processing condition, the pressurized water reactor is shut down.

[0109] The specific process of the above S501-S507 can be found in the description of the above method embodiment. The implementation principle and technical effect are similar and will not be repeated here.

[0110] It should be understood that, although the various steps in the flowcharts involved in the various embodiments described above are displayed in sequence according to the instructions of the arrows, these steps are not necessarily executed in sequence in the order indicated by the arrows. Unless otherwise specified herein, there is no strict order restriction on the execution of these steps, and these steps can be executed in other orders. Moreover, at least a portion of the steps in the flowcharts involved in the various embodiments described above can include multiple steps or multiple stages, and these steps or stages are not necessarily executed and completed at the same time, but can be executed at different times, and the execution order of these steps or stages is not necessarily to be carried out in sequence, but can be executed in turn or alternately with other steps or at least a portion of steps or stages in other steps.

[0111] Based on the same inventive concept, embodiments of the present application also provide a nuclear power plant fault handling device for implementing the aforementioned nuclear power plant fault handling method. The solution provided by this device is similar to the solution described in the aforementioned method. Therefore, the specific limitations in one or more of the following embodiments of the fault handling device can be found in the aforementioned limitations of the nuclear power plant fault handling method and will not be further elaborated here.

[0112] In one embodiment, Figure 6 As shown, a fault processing device 1 for a nuclear power plant is provided, comprising: a signal acquisition module 10, a determination module 20 and a fault processing module 30, wherein:

[0113] The signal acquisition module 10 is used to acquire a detection signal set corresponding to each electrical partition in the pressurized water reactor; wherein the detection signal set corresponding to each electrical partition includes the detection signal detected by the neutron detector contained in the electrical partition;

[0114] A determination module 20 is configured to determine a target failure mode of the pressurized water reactor and a temperature-related value based on each detection signal set; wherein the temperature-related value includes a deviation from nucleate boiling ratio (DNBR) and / or a linear power density (LPD);

[0115] The fault processing module 30 is used to perform fault processing on the pressurized water reactor according to the target failure mode and the temperature correlation value.

[0116] In one embodiment, Figure 7 As shown, the determination module 20 includes:

[0117] A construction unit 21 is used to construct a core power distribution corresponding to the pressurized water reactor according to each detection signal set;

[0118] The mode determination unit 22 is configured to determine a target failure mode of the pressurized water reactor according to each core power value in the core power distribution.

[0119] In one embodiment, the mode determination unit 22 is specifically configured to:

[0120] According to each core power value in the core power distribution, the failure status of the neutron detector in each electrical partition in the pressurized water reactor is determined; according to the failure status of the neutron detector in each electrical partition in the pressurized water reactor, the target failure mode of the pressurized water reactor is determined.

[0121] In one embodiment, the fault processing module 30 is specifically configured to:

[0122] According to the fault condition of the neutron detector, a probe fault value is determined; when the probe fault value is greater than a quantity threshold, the pressurized water reactor is shut down.

[0123] In one embodiment, Figure 8 As shown, the fault processing module 30 includes:

[0124] A threshold determination unit 31 is configured to determine a trip protection threshold of the pressurized water reactor according to a target failure mode; wherein the trip protection threshold includes a DNBR threshold and / or an LPD threshold;

[0125] The fault processing unit 32 is used to perform fault processing on the pressurized water reactor according to the shutdown protection threshold and the temperature correlation value.

[0126] In one embodiment, the fault processing unit 32 is specifically configured to:

[0127] When the magnitude relationship between the shutdown protection threshold and the temperature correlation value satisfies the shutdown processing condition, the pressurized water reactor is shut down.

[0128] In one embodiment, the fault handling device 1 further includes a division module, wherein the division module is specifically configured to:

[0129] According to the arrangement scheme of the neutron detectors in the pressurized water reactor, the neutron detectors in the pressurized water reactor are divided to obtain electrical partitions, and the electrical partitions cross-penetrate each other; wherein each electrical partition includes at least one neutron detector.

[0130] Each module in the aforementioned nuclear power plant fault handling device may be implemented in whole or in part through software, hardware, or a combination thereof. Each module may be embedded in or independent of a processor within a computer device in hardware form, or may be stored in a computer device memory in software form, so that the processor can call and execute the corresponding operations of each module.

[0131] In one embodiment, a computer device is provided. The computer device may be a server, and its internal structure diagram may be as follows: Figure 9As shown. The computer device includes a processor, a memory, an input / output interface (Input / Output, abbreviated as I / O) and a communication interface. The processor, memory and input / output interface are connected through a system bus, and the communication interface is connected to the system bus through the input / output interface. The processor of the computer device is used to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, a computer program and a database. The internal memory provides an environment for the operation of the operating system and computer program in the non-volatile storage medium. The database of the computer device is used to store shutdown protection threshold data corresponding to each failure mode. The input / output interface of the computer device is used to exchange information between the processor and an external device. The communication interface of the computer device is used to communicate with an external terminal through a network connection. When the computer program is executed by the processor, a fault handling method for a nuclear power plant is implemented.

[0132] Those skilled in the art will understand that Figure 9 The structure shown in the figure is only a block diagram of a part of the structure related to the solution of the present application, and does not constitute a limitation on the computer device to which the solution of the present application is applied. The specific computer device may include more or fewer components than shown in the figure, or combine certain components, or have a different component arrangement.

[0133] In one embodiment, a computer device is provided, including a memory and a processor, wherein a computer program is stored in the memory, and when the processor executes the computer program, the following steps are implemented:

[0134] Acquire a detection signal set corresponding to each electrical partition in the pressurized water reactor; wherein the detection signal set corresponding to each electrical partition includes a detection signal detected by a neutron detector contained in the electrical partition;

[0135] Determining target failure modes and temperature-related values ​​of the pressurized water reactor based on each detection signal set; wherein the temperature-related values ​​include deviation from nucleate boiling ratio (DNBR) and / or linear power density (LPD);

[0136] Fault handling of pressurized water reactors is performed based on target failure modes and temperature correlation values.

[0137] In one embodiment, when the processor executes the logic in the computer program for determining the target failure mode of the pressurized water reactor based on each detection signal set, the processor specifically implements the following steps:

[0138] According to each detection signal set, a core power distribution corresponding to the pressurized water reactor is constructed; according to each core power value in the core power distribution, a target failure mode of the pressurized water reactor is determined.

[0139] In one embodiment, when a processor executes logic in a computer program for determining a target failure mode of a pressurized water reactor based on each core power value in a core power distribution, the processor specifically implements the following steps:

[0140] According to each core power value in the core power distribution, the failure status of the neutron detector in each electrical partition in the pressurized water reactor is determined; according to the failure status of the neutron detector in each electrical partition in the pressurized water reactor, the target failure mode of the pressurized water reactor is determined.

[0141] In one embodiment, before performing fault processing on a pressurized water reactor according to a target failure mode and a temperature-related value, the processor executes logic in a computer program to specifically implement the following steps:

[0142] According to the fault condition of the neutron detector, a probe fault value is determined; when the probe fault value is greater than a quantity threshold, the pressurized water reactor is shut down.

[0143] In one embodiment, when a processor executes logic in a computer program for performing fault processing on a pressurized water reactor based on a target failure mode and a temperature-related value, the processor specifically implements the following steps:

[0144] A pressurized water reactor (PWR) trip protection threshold is determined according to a target failure mode, wherein the trip protection threshold includes a DNBR threshold and / or an LPD threshold; and fault processing is performed on the PWR according to the trip protection threshold and a temperature correlation value.

[0145] In one embodiment, when the processor executes logic in the computer program for performing fault processing on the pressurized water reactor based on the trip protection threshold and the current measurement value of the pressurized water reactor, the following steps are specifically implemented:

[0146] When the magnitude relationship between the shutdown protection threshold and the temperature correlation value satisfies the shutdown processing condition, the pressurized water reactor is shut down.

[0147] In one embodiment, when the processor executes the logic in the computer program, the following steps are specifically implemented:

[0148] According to the arrangement scheme of the neutron detectors in the pressurized water reactor, the neutron detectors in the pressurized water reactor are divided to obtain electrical partitions, and the electrical partitions cross-penetrate each other; wherein each electrical partition includes at least one neutron detector.

[0149] In one embodiment, a computer-readable storage medium is provided, on which a computer program is stored. When the computer program is executed by a processor, the following steps are implemented:

[0150] Acquire a detection signal set corresponding to each electrical partition in the pressurized water reactor; wherein the detection signal set corresponding to each electrical partition includes a detection signal detected by a neutron detector contained in the electrical partition;

[0151] Determining target failure modes and temperature-related values ​​of the pressurized water reactor based on each detection signal set; wherein the temperature-related values ​​include deviation from nucleate boiling ratio (DNBR) and / or linear power density (LPD);

[0152] Fault handling of pressurized water reactors is performed based on target failure modes and temperature correlation values.

[0153] In one embodiment, when the code logic in the computer program for determining the target failure mode of the pressurized water reactor based on each detection signal set is executed by a processor, the following steps are specifically implemented:

[0154] According to each detection signal set, a core power distribution corresponding to the pressurized water reactor is constructed; according to each core power value in the core power distribution, a target failure mode of the pressurized water reactor is determined.

[0155] In one embodiment, when the code logic in the computer program for determining a target failure mode of a pressurized water reactor based on each core power value in the core power distribution is executed by a processor, the following steps are specifically implemented:

[0156] According to each core power value in the core power distribution, the failure status of the neutron detector in each electrical partition in the pressurized water reactor is determined; according to the failure status of the neutron detector in each electrical partition in the pressurized water reactor, the target failure mode of the pressurized water reactor is determined.

[0157] In one embodiment, before performing fault processing on a pressurized water reactor according to a target failure mode and a temperature-related value, when the code logic in the computer program is executed by a processor, the following steps are specifically implemented:

[0158] According to the fault condition of the neutron detector, a probe fault value is determined; when the probe fault value is greater than a quantity threshold, the pressurized water reactor is shut down.

[0159] In one embodiment, when the code logic in the computer program for performing fault processing on a pressurized water reactor according to a target failure mode and a temperature-related value is executed by a processor, the following steps are specifically implemented:

[0160] A pressurized water reactor (PWR) trip protection threshold is determined according to a target failure mode, wherein the trip protection threshold includes a DNBR threshold and / or an LPD threshold; and fault processing is performed on the PWR according to the trip protection threshold and a temperature correlation value.

[0161] In one embodiment, when the processor executes the code logic in the computer program for performing fault processing on the pressurized water reactor based on the trip protection threshold and the current measurement value of the pressurized water reactor, the following steps are specifically implemented:

[0162] When the magnitude relationship between the shutdown protection threshold and the temperature correlation value satisfies the shutdown processing condition, the pressurized water reactor is shut down.

[0163] In one embodiment, when the code logic in the computer program is executed by a processor, the following steps are specifically implemented:

[0164] According to the arrangement scheme of the neutron detectors in the pressurized water reactor, the neutron detectors in the pressurized water reactor are divided to obtain electrical partitions, and the electrical partitions cross-penetrate each other; wherein each electrical partition includes at least one neutron detector.

[0165] In one embodiment, a computer program product is provided, comprising a computer program, which, when executed by a processor, implements the following steps:

[0166] Acquire a detection signal set corresponding to each electrical partition in the pressurized water reactor; wherein the detection signal set corresponding to each electrical partition includes a detection signal detected by a neutron detector contained in the electrical partition;

[0167] Determining target failure modes and temperature-related values ​​of the pressurized water reactor based on each detection signal set; wherein the temperature-related values ​​include deviation from nucleate boiling ratio (DNBR) and / or linear power density (LPD);

[0168] Fault handling of pressurized water reactors is performed based on target failure modes and temperature correlation values.

[0169] In one embodiment, when the computer program is executed by a processor to determine the target failure mode of a pressurized water reactor based on each detection signal set, the following steps are specifically implemented:

[0170] According to each detection signal set, a core power distribution corresponding to the pressurized water reactor is constructed; according to each core power value in the core power distribution, a target failure mode of the pressurized water reactor is determined.

[0171] In one embodiment, when a computer program is executed by a processor to determine a target failure mode of a pressurized water reactor based on each core power value in a core power distribution, the computer program specifically implements the following steps:

[0172] According to each core power value in the core power distribution, the failure status of the neutron detector in each electrical partition in the pressurized water reactor is determined; according to the failure status of the neutron detector in each electrical partition in the pressurized water reactor, the target failure mode of the pressurized water reactor is determined.

[0173] In one embodiment, before performing fault processing on a pressurized water reactor according to a target failure mode and a temperature-related value, the computer program, when executed by a processor, specifically implements the following steps:

[0174] According to the fault condition of the neutron detector, a probe fault value is determined; when the probe fault value is greater than a quantity threshold, the pressurized water reactor is shut down.

[0175] In one embodiment, when a computer program is executed by a processor to perform fault processing on a pressurized water reactor according to a target failure mode and a temperature correlation value, the following steps are specifically implemented:

[0176] A pressurized water reactor (PWR) trip protection threshold is determined according to a target failure mode, wherein the trip protection threshold includes a DNBR threshold and / or an LPD threshold; and fault processing is performed on the PWR according to the trip protection threshold and a temperature correlation value.

[0177] In one embodiment, when a computer program is executed by a processor to perform a fault processing operation on a pressurized water reactor based on a trip protection threshold value and a current measurement value of the pressurized water reactor, the following steps are specifically implemented:

[0178] When the magnitude relationship between the shutdown protection threshold and the temperature correlation value satisfies the shutdown processing condition, the pressurized water reactor is shut down.

[0179] In one embodiment, when the computer program is executed by a processor, the following steps are specifically implemented:

[0180] According to the arrangement scheme of the neutron detectors in the pressurized water reactor, the neutron detectors in the pressurized water reactor are divided to obtain electrical partitions, and the electrical partitions cross-penetrate each other; wherein each electrical partition includes at least one neutron detector.

[0181] It should be noted that the data involved in this application (including but not limited to the shutdown protection thresholds corresponding to each failure mode, etc.) are all data authorized by the user or fully authorized by all parties, and the collection, use and processing of relevant data must comply with relevant regulations.

[0182] Those skilled in the art will appreciate that all or part of the processes in the above-mentioned embodiment methods can be implemented by instructing the relevant hardware through a computer program, and the computer program can be stored in a non-volatile computer-readable storage medium. When the computer program is executed, it can include the processes of the embodiments of the above-mentioned methods. Among them, any reference to memory, database or other media used in the embodiments provided in this application may include at least one of non-volatile and volatile memory. Non-volatile memory may include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical memory, high-density embedded non-volatile memory, resistive random access memory (ReRAM), magnetic random access memory (MRAM), ferroelectric random access memory (FRAM), phase change memory (PCM), graphene memory, etc. Volatile memory may include random access memory (RAM) or external cache memory, etc. By way of illustration and not limitation, RAM can be in various forms, such as static random access memory (SRAM) or dynamic random access memory (DRAM). The database involved in the various embodiments provided herein may include at least one of a relational database and a non-relational database. Non-relational databases may include, but are not limited to, distributed databases based on blockchains. The processor involved in the various embodiments provided herein may be, but are not limited to, a general-purpose processor, a central processing unit, a graphics processing unit, a digital signal processor, a programmable logic unit, a data processing logic unit based on quantum computing, and the like.

[0183] The technical features of the above embodiments can be combined arbitrarily. To make the description concise, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0184] The above-described embodiments merely represent several implementation methods of the present application. While the descriptions are relatively specific and detailed, they should not be construed as limiting the scope of the present application. It should be noted that a person of ordinary skill in the art may make various modifications and improvements without departing from the spirit of the present application, and these modifications and improvements fall within the scope of protection of the present application. Therefore, the scope of protection of the present application shall be determined by the appended claims.

Claims

1. A method for handling a fault in a nuclear power plant, characterized in that: The method comprises: Acquire a detection signal set corresponding to each electrical partition in the pressurized water reactor; wherein the detection signal set corresponding to each electrical partition includes a detection signal detected by a neutron detector contained in the electrical partition; Determining target failure modes and temperature-related values ​​of the pressurized water reactor based on each set of detection signals; wherein the failure modes are various operating modes corresponding to various fault conditions of neutron detectors in the pressurized water reactor; and the temperature-related values ​​include deviation from nucleate boiling ratio (DNBR) and / or linear power density (LPD); Fault processing is performed on the pressurized water reactor according to the target failure mode and the temperature correlation value.

2. The method according to claim 1, characterized in that Determining the target failure mode of the pressurized water reactor according to each detection signal set includes: constructing a core power distribution corresponding to the pressurized water reactor according to each detection signal set; A target failure mode of the pressurized water reactor is determined according to each core power value in the core power distribution.

3. The method according to claim 2, characterized in that The constructing the core power distribution corresponding to the pressurized water reactor according to each detection signal set includes: A core power distribution corresponding to the pressurized water reactor is constructed according to a correlation relationship between each detection signal in each detection signal set and a position of a neutron detector in the pressurized water reactor.

4. The method according to claim 2, characterized in that Determining the target failure mode of the pressurized water reactor according to each core power value in the core power distribution includes: determining a fault condition of a neutron detector in each electrical partition within the pressurized water reactor according to each core power value in the core power distribution; A target failure mode of the pressurized water reactor is determined according to the failure conditions of neutron detectors in each electrical partition within the pressurized water reactor.

5. The method according to claim 4, characterized in that Before performing fault processing on the pressurized water reactor according to the target failure mode and the temperature correlation value, the method further includes: determining a probe fault value according to a fault condition of the neutron detector; When the probe fault value is greater than a quantity threshold, the pressurized water reactor is shut down.

6. The method according to claim 1, characterized in that The performing fault processing on the pressurized water reactor according to the target failure mode and the temperature correlation value includes: Determining a trip protection threshold of the pressurized water reactor according to the target failure mode; wherein the trip protection threshold includes a DNBR threshold and / or an LPD threshold; Fault processing is performed on the pressurized water reactor according to the shutdown protection threshold and the temperature correlation value.

7. The method according to claim 6, characterized in that The performing fault processing on the pressurized water reactor according to the shutdown protection threshold of the pressurized water reactor and the temperature correlation value includes: When the magnitude relationship between the shutdown protection threshold and the temperature correlation value satisfies a shutdown processing condition, the pressurized water reactor is shut down.

8. The method according to claim 1, characterized in that The method further comprises: According to the arrangement scheme of the neutron detectors in the pressurized water reactor, the neutron detectors in the pressurized water reactor are divided to obtain electrical partitions, and the electrical partitions cross-penetrate each other; wherein each electrical partition includes at least one neutron detector.

9. The method according to claim 1, characterized in that The deviation from nucleate boiling ratio DNBR represents the fuel cladding temperature in the pressurized water reactor; and the linear power density LPD represents the pellet temperature in the pressurized water reactor.

10. A fault handling device, characterized in that: The device comprises: A signal acquisition module, configured to acquire a detection signal set corresponding to each electrical partition in the pressurized water reactor; wherein the detection signal set corresponding to each electrical partition includes a detection signal detected by a neutron detector contained in the electrical partition; a determination module, configured to determine target failure modes and temperature-related values ​​of the pressurized water reactor based on each set of detection signals; wherein the failure modes are various operating modes corresponding to various fault conditions of neutron detectors in the pressurized water reactor; and the temperature-related values ​​include deviation from nucleate boiling ratio (DNBR) and / or linear power density (LPD); A fault processing module is used to perform fault processing on the pressurized water reactor according to the target failure mode and the temperature correlation value.

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