Nuclear power measurement value correction method and apparatus, and computer device and storage medium

Abstract

A nuclear power measurement value correction method and apparatus, and a computer device, a storage medium and a computer program product. The nuclear power measurement value correction method comprises: receiving a nuclear power measurement value and a thermal power measurement value of a nuclear reactor core in real time (S200); when the nuclear reactor core operates to a full-power steady state for the first time, acquiring a first nuclear power measurement value and a first thermal power measurement value of the nuclear reactor core, and when the nuclear reactor core operates to a low-power steady state for the first time, acquiring a second nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core (S400); on the basis of the first nuclear power measurement value, the first thermal power measurement value, the second nuclear power measurement value, and the second thermal power measurement value, determining a correction coefficient (S600); and on the basis of the correction coefficient, correcting a subsequently received nuclear power measurement value, so as to obtain a corrected nuclear power value (S800). Using the nuclear power measurement value correction method can improve the efficiency of correcting a nuclear power measurement value.

Description

Nuclear power measurement value correction method, device, computer equipment and storage medium

[0001] Related applications

[0002] This application claims priority to Chinese patent application number 202410049075.2, filed on January 12, 2024, entitled “Nuclear power measurement value correction method, device, computer equipment and storage medium,” the entire text of which is hereby incorporated by reference. Technical Field

[0003] The present application relates to the field of nuclear reactor off-core detection technology, and in particular to a method, device, computer equipment, storage medium and computer program product for correcting nuclear power measurement values. Background Art

[0004] During nuclear reactor operation, the core typically experiences high temperatures, high pressures, and high levels of radiation. Important operating parameters, such as the core's true operating power, are acquired through detectors located outside the core. However, during actual nuclear power plant operation, varying power levels may occur depending on grid load. These changes in operating conditions can cause variations in the core neutron counts detected by the external detectors, ultimately affecting their counts. Therefore, regular calibration of the external detector readings is necessary to ensure that these readings align with the actual parameter changes within the core.

[0005] The process of correcting nuclear power in traditional schemes is relatively cumbersome, and xenon oscillation is difficult to perform at the end of the nuclear reactor core life, resulting in inefficient correction of nuclear power measurements. Summary of the Invention

[0006] Based on this, it is necessary to provide a nuclear detector calibration method, device, computer equipment, computer-readable storage medium and computer program product that can improve the correction efficiency in order to address the above technical problems.

[0007] In a first aspect, the present application provides a method for correcting a nuclear power measurement value. The method comprises:

[0008] Receive real-time nuclear power and thermal power measurements of the nuclear reactor core;

[0009] obtaining a first nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core when the nuclear reactor core is first operated to a full power steady state, and obtaining a second nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core when the nuclear reactor core is first operated to a low power steady state;

[0010] determining a correction factor based on the first nuclear power measurement, the first thermal power measurement, the second nuclear power measurement, and the second thermal power measurement;

[0011] The subsequently received nuclear power measurement value is corrected according to the correction coefficient to obtain a nuclear power correction value.

[0012] In one embodiment, determining a correction factor based on the first nuclear power measurement, the first thermal power measurement, the second nuclear power measurement, and the second thermal power measurement includes:

[0013] determining a difference between the second nuclear power measurement value and the first nuclear power measurement value to obtain a nuclear power measurement difference;

[0014] determining a difference between the second thermal power measurement value and the first thermal power measurement value to obtain a thermal power measurement difference;

[0015] A correction coefficient is determined according to the thermal power measurement difference and the nuclear power measurement difference.

[0016] In one embodiment, the correcting the subsequently received nuclear power measurement value according to the correction coefficient to obtain the nuclear power correction value includes:

[0017] Obtaining a first difference between the nuclear power measurement value and the first nuclear power measurement value;

[0018] determining a second difference between the nuclear power measurement value and the first nuclear power measurement value based on the first difference and the correction coefficient, wherein the second difference is a value obtained by correcting the first difference;

[0019] A nuclear power correction value is obtained according to the second difference and the first thermal power measurement value.

[0020] In one embodiment, the method further comprises:

[0021] The correction coefficient is updated according to a preset correction coefficient update condition.

[0022] In one embodiment, updating the correction coefficient according to a preset correction coefficient update condition includes:

[0023] Get the operating time of the nuclear reactor;

[0024] If the running time is greater than a preset time threshold, the correction coefficient is updated.

[0025] In a second aspect, the present application also provides a nuclear power measurement value correction device. The device comprises:

[0026] A real-time power receiving module, used for receiving the nuclear power measurement value and thermal power measurement value of the nuclear reactor core in real time;

[0027] a measurement value acquisition module, configured to acquire a first nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core when the nuclear reactor core first operates to a full-power steady state, and to acquire a second nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core when the nuclear reactor core first operates to a low-power steady state;

[0028] a correction coefficient determination module, configured to determine a correction coefficient based on the first nuclear power measurement value, the first thermal power measurement value, the second nuclear power measurement value, and the second thermal power measurement value;

[0029] The measurement value correction module is used to correct the subsequently received nuclear power measurement value according to the correction coefficient to obtain a nuclear power correction value.

[0030] In one embodiment, the correction coefficient determination module is also used to determine the difference between the second nuclear power measurement value and the first nuclear power measurement value to obtain a nuclear power measurement difference; determine the difference between the second thermal power measurement value and the first thermal power measurement value to obtain a thermal power measurement difference; and determine the correction coefficient based on the thermal power measurement difference and the nuclear power measurement difference.

[0031] In a third aspect, the present application further provides a computer device comprising a memory and a processor, wherein the memory stores a computer program, and the processor executes the computer program to implement the steps in the above-mentioned embodiments of the nuclear power measurement value correction method.

[0032] 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 steps in the above-mentioned embodiments of the method for correcting the nuclear power measurement value.

[0033] In a fifth aspect, the present application further provides a computer program product, which includes a computer program that, when executed by a processor, implements the steps in the above-mentioned embodiments of the method for correcting the nuclear power measurement value.

[0034] The above-mentioned nuclear power measurement value correction method, device, computer equipment, storage medium and computer program product, by receiving the nuclear power measurement value and thermal power measurement value of the nuclear reactor core in real time, obtains the first nuclear power measurement value and the first thermal power measurement value of the nuclear reactor core in the first full power steady state, as well as the second nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core in the first low power steady state. Then, based on the first nuclear power measurement value, the first thermal power measurement value, the second nuclear power measurement value and the second thermal power measurement value, a correction coefficient is determined, and then the subsequently received nuclear power measurement value is corrected according to the correction coefficient, so that a more accurate nuclear power correction value can be obtained. It can be seen that this scheme only needs to obtain the nuclear power measurement value and the thermal power measurement value in the first full power steady state and the first low power steady state to determine the correction coefficient. Compared with the process of determining the correction coefficient in the traditional correction method, it is simpler and does not require complex and tedious theoretical calculations, making the nuclear power correction process simpler and more efficient, thereby improving the correction efficiency. BRIEF DESCRIPTION OF THE DRAWINGS

[0035] In order to more clearly illustrate the embodiments of the present application or the technical solutions in the conventional technology, the following briefly introduces the drawings required for use in the embodiments or the conventional technology descriptions. Obviously, the drawings described below are merely embodiments of the present application. For ordinary technicians in this field, other drawings can be obtained based on the disclosed drawings without any creative work.

[0036] FIG1 is a diagram illustrating an application environment of a method for correcting a nuclear power measurement value according to an embodiment;

[0037] FIG2 is a schematic flow chart of a method for correcting a nuclear power measurement value in one embodiment;

[0038] FIG3 is a schematic flow chart of a method for correcting a nuclear power measurement value in another embodiment;

[0039] FIG4 is a schematic flow chart of a method for correcting nuclear power measurement values ​​in yet another embodiment;

[0040] FIG5 is a schematic flow chart of a method for correcting nuclear power measurement values ​​in yet another embodiment;

[0041] FIG6 is a schematic flow chart of a method for correcting a nuclear power measurement value in another embodiment;

[0042] FIG7 is a structural block diagram of a device for correcting a nuclear power measurement value according to an embodiment;

[0043] FIG8 is a structural block diagram of a nuclear power measurement value correction device in another embodiment;

[0044] FIG9 is a diagram showing the internal structure of a computer device in one embodiment. DETAILED DESCRIPTION

[0045] The following will be combined with the drawings in the embodiments of this application to clearly and completely describe the technical solutions in the embodiments of this application. Obviously, the embodiments described are only part of the embodiments of this application, not all of the embodiments. Based on the embodiments in this application, all other embodiments obtained by ordinary technicians in this field without making creative efforts are within the scope of protection of this application.

[0046] The nuclear power measurement correction method provided in the embodiments of the present application can be applied in the application environment shown in FIG1 . Here, detector 102 is connected to server 104. A data storage system can store data that server 104 needs to process. The data storage system can be integrated with server 104 or placed in the cloud or on other network servers.

[0047] Specifically, the detector 102 may detect the nuclear power and thermal power of the nuclear reactor core in real time, and upload the detected nuclear power and thermal power to the server 104 in real time. The server 104 obtains the first nuclear power measurement value and the first thermal power measurement value of the nuclear reactor core in the first full-power steady state, as well as the second nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core in the first low-power steady state. Then, the server 104 determines the correction coefficient based on the first nuclear power measurement value, the first thermal power measurement value, the second nuclear power measurement value and the second thermal power measurement value. Furthermore, the server 104 corrects the subsequently received nuclear power measurement value according to the correction coefficient to obtain a more accurate nuclear power correction value. It can be understood that the nuclear power measurement value correction method provided in the embodiment of the present application can also be applied to a terminal, or a system including a terminal and a server.

[0048] The detector 102 may be, but is not limited to, various nuclear reactor external detectors. The server 104 may be implemented as an independent server or a server cluster consisting of multiple servers.

[0049] In one embodiment, as shown in FIG2 , a method for correcting a nuclear power measurement value is provided. The method is described by taking the server 104 in FIG1 as an example, and includes the following steps:

[0050] S200: Receive the nuclear power measurement value and thermal power measurement value of the nuclear reactor core in real time.

[0051] Nuclear power and thermal power are two key parameters in nuclear reactor operation. Nuclear power is the amount of nuclear energy released per unit time by the nuclear fuel within the reactor. This refers to the rate at which this energy is released, as atomic nuclei undergo nuclear fission or fusion, producing neutrons and releasing energy. Thermal power is the rate at which nuclear energy is ultimately transferred to the reactor coolant in the form of heat.

[0052] Specifically, the nuclear power measurement value and thermal power measurement value of the nuclear reactor core can be directly or indirectly detected by an off-core detector or other power measuring equipment, and the off-core detector or other power measuring equipment can feed back the nuclear power measurement value and thermal power measurement value to the corresponding server or terminal in real time for subsequent correction processing, and can also be displayed in real time on the dashboard in the control room for technical personnel to view at any time.

[0053] In a specific implementation, an external core detector can be installed around the nuclear reactor. The external core detector can measure the nuclear power and thermal power of the nuclear reactor core in real time and report the measured nuclear power and thermal power values ​​to the server in real time. The server receives the nuclear power and thermal power values ​​of the nuclear reactor core reported in real time by the external core detector.

[0054] S400, when the nuclear reactor core first operates to a full-power steady state, obtains a first nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core; and when the nuclear reactor core first operates to a low-power steady state, obtains a second nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core.

[0055] Full power refers to the state in which a nuclear reactor reaches its rated power. This means that, with components such as the nuclear fuel and cooling system functioning normally, the nuclear reaction proceeds at the rated rate, thereby achieving the reactor's rated power. Low-power steady-state refers to the state in which a nuclear reactor operates at a less-than-full-power steady state, such as 80% or 60% of full power. During nuclear reactor operation, steady-state refers to the state in which the reactor's operating state remains relatively unchanged over a certain period of time. In steady-state, key reactor parameters such as power, temperature, and pressure tend to be stable.

[0056] By using the real-time nuclear power and thermal power measurements uploaded by external detectors or other power measurement devices, it is possible to directly obtain the first nuclear power measurement value and the first thermal power measurement value of the nuclear reactor core in its first full-power steady-state, as well as the second nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core in its first low-power steady-state. It should be noted that when the nuclear reactor core first operates to full-power steady-state, the nuclear power and thermal power collected by the external detectors or other power measurement devices can be considered to accurately reflect the operating conditions within the nuclear reactor core. Similarly, when the nuclear reactor core first operates to low power, the nuclear power and thermal power collected by the external detectors or other power measurement devices can also be considered to accurately reflect the operating conditions within the nuclear reactor core. Therefore, based on the first nuclear power measurement value, the first thermal power measurement value, the second nuclear power measurement value, and the second thermal power measurement value collected in the above two situations, the nuclear power measurement values ​​when the nuclear reactor core is in other operating conditions can be corrected.

[0057] S600 , determining a correction coefficient according to the first nuclear power measurement value, the first thermal power measurement value, the second nuclear power measurement value, and the second thermal power measurement value.

[0058] The correction coefficient is used to correct the value indicated by the external detector so that the indication value of the external detector can accurately reflect the actual operating status inside the nuclear reactor core.

[0059] Due to changes in the operating state of the nuclear reactor core and other objective factors, in most cases, the readings from the external detectors do not accurately reflect the actual operating state of the nuclear reactor core. Therefore, most of the time, the real-time nuclear power measurement is a pending value that requires correction through subsequent steps. Research has found that the deviations between the external detector readings and the actual operating state inside the core may be caused by factors such as the detector's response sensitivity, burnup effects, and the influence of water temperature. Given the different causes of the deviations, the correction methods vary.

[0060] In this embodiment, the main consideration is the deviation between the nuclear power and thermal power indicated by the external core detector. Therefore, the correction coefficient can be determined based on the first nuclear power measurement value, the second nuclear power measurement value, the first thermal power measurement value, and the first thermal power measurement value obtained in the above steps. For example, a linear regression method can be used to determine the functional relationship between nuclear power and thermal power and further determine the correction coefficient.

[0061] S800: Correct the subsequently received nuclear power measurement value according to the correction coefficient to obtain a nuclear power correction value.

[0062] Subsequent nuclear power measurements are corrected based on the correction factor. This correction process allows the nuclear power measurements to more accurately reflect the actual operating status of the nuclear reactor, resulting in a corrected nuclear power value. This corrected nuclear power value can be used for subsequent analysis of the nuclear reactor's operation and performance.

[0063] The above-mentioned nuclear power measurement value correction method receives the nuclear power measurement value and thermal power measurement value of the nuclear reactor core in real time, obtains the first nuclear power measurement value and the first thermal power measurement value of the nuclear reactor core in the first full-power steady state, and the second nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core in the first low-power steady state. Then, based on the first nuclear power measurement value, the first thermal power measurement value, the second nuclear power measurement value, and the second thermal power measurement value, a correction coefficient is determined, and then the subsequently received nuclear power measurement value is corrected according to the correction coefficient, so that a more accurate nuclear power correction value can be obtained. It can be seen that this scheme only needs to obtain the nuclear power measurement value and the thermal power measurement value in the first full-power steady state and the first low-power steady state to determine the correction coefficient. Compared with the process of determining the correction coefficient in the traditional correction method, it is simpler and does not require complex and tedious theoretical calculations, making the nuclear power correction process simpler and more efficient, thereby improving the correction efficiency.

[0064] In one embodiment, as shown in FIG3 , S600 includes:

[0065] S620: Determine a difference between the second nuclear power measurement value and the first nuclear power measurement value to obtain a nuclear power measurement difference.

[0066] S640: Determine a difference between the second thermal power measurement value and the first thermal power measurement value to obtain a thermal power measurement difference.

[0067] S660: Determine a correction coefficient based on the thermal power measurement difference and the nuclear power measurement difference.

[0068] In determining the correction factor, the operating conditions of the nuclear reactor in the first full-power steady-state and the first low-power steady-state are taken into account. Specifically, it is necessary to determine the difference between the second nuclear power measurement value and the first nuclear power measurement value, as well as the difference between the second thermal power measurement value and the first thermal power measurement value, and then determine the correction factor based on the thermal power measurement difference and the nuclear power measurement difference. The formula can be as follows:

[0069] Wherein, K represents the correction coefficient, W2 represents the second thermal power measurement value, W1 represents the first thermal power measurement value, P2 represents the second nuclear power measurement value, and P1 represents the first nuclear power measurement value.

[0070] In this embodiment, a nuclear power measurement difference is obtained by determining the difference between the second nuclear power measurement value and the first nuclear power measurement value, and a thermal power measurement difference is obtained by determining the difference between the second thermal power measurement value and the first thermal power measurement value. A correction factor is then determined based on the thermal power measurement difference and the nuclear power measurement difference. Because the correction factor determination process simultaneously considers both the nuclear power and thermal power of the nuclear reactor under different states, the deviation between the nuclear power and thermal power can be effectively corrected, thereby enabling the indication value of the ex-core detector to more closely approximate the actual operating conditions within the nuclear reactor core.

[0071] In one embodiment, as shown in FIG4 , S800 includes:

[0072] S820: Obtain a first difference between the core power measurement value and the first core power measurement value.

[0073] S840: Determine a second difference between the nuclear power measurement value and the first nuclear power measurement value based on the first difference and the correction coefficient, where the second difference is a value obtained after the first difference is corrected.

[0074] S860: Obtain a nuclear power correction value according to the second difference and the first thermal power measurement value.

[0075] Following the above embodiment, after determining the correction coefficient, it is necessary to use the correction coefficient to correct the indication value of the ex-core detector. Specifically, it is possible to obtain the nuclear power measurement value subsequently detected by the ex-core detector, determine the first difference between the nuclear power measurement value and the first nuclear power measurement value, and use the correction coefficient to correct the first difference to obtain the second difference. Further, based on the second difference and the first thermal power measurement value, the nuclear power correction value is determined. The specific formula is: P r =K(P-P1)+W1

[0076] Among them, P r is the nuclear power correction value, P is the nuclear power measurement value, P1 is the first nuclear power measurement value, and W1 is the first thermal power measurement value.

[0077] This correction method is applicable to multiple stages of a nuclear reactor, including low-power operation and returning to full-power operation. When the reactor returns to full-power operation, the nuclear power measurement is very close to the first nuclear power measurement, meaning the correction is negligible. It can be assumed that the external detector's indication at this point accurately reflects the operating state within the reactor core.

[0078] In this embodiment, a first difference between a nuclear power measurement value and a first nuclear power measurement value is obtained, and then a second difference between the nuclear power measurement value and the first nuclear power measurement value is determined based on the first difference and a correction coefficient, wherein the second difference is the value obtained by correcting the first difference. Based on the second difference and the first thermal power measurement value, a real-time nuclear power correction value can be obtained. The entire correction process improves the real-time monitoring accuracy of nuclear power and allows correction of nuclear power measurement values ​​at multiple stages of a nuclear reactor, which helps ensure that the corrected nuclear power measurement value accurately reflects the operating conditions of the nuclear reactor core.

[0079] In one embodiment, as shown in FIG5 , the method for correcting the nuclear power measurement value further includes:

[0080] S900: Update the correction coefficient according to a preset correction coefficient update condition.

[0081] The updating conditions of the correction coefficient are related to the specific nuclear reaction system. The updating of the correction coefficient is intended to adapt to and respond to changes in the operating state of the system in order to improve the accuracy of the correction.

[0082] For example, if the structure or operating conditions of a nuclear reactor change significantly, a correction coefficient needs to be updated to adapt to the new operating conditions. The performance of the nuclear reactor can be monitored regularly, and if deviations in the operating state of the nuclear reactor are found, the correction coefficient needs to be updated. The correction coefficient can be updated by using the latest operating data and re-determining the correction coefficient according to the correction coefficient determination method in the above-mentioned embodiments. Furthermore, statistical methods, such as regression analysis, can be used to continuously fit and update the correction coefficient so that the correction coefficient is more applicable to the current operating state of the nuclear reactor.

[0083] In this embodiment, by updating the correction coefficient according to the preset correction coefficient update conditions, the adaptability of the correction coefficient to different nuclear reactor operating conditions can be improved, thereby improving the efficiency and accuracy of the correction process.

[0084] In one embodiment, as shown in FIG6 , S900 includes:

[0085] S920, obtaining the operating time of the nuclear reactor.

[0086] S940: If the running time is greater than the preset time threshold, the correction coefficient is updated.

[0087] The operating time of the nuclear reactor is one of the conditions for determining whether the correction coefficient needs to be updated. Among them, the operating time of the nuclear reactor can be the total operating time from the start of the nuclear reactor to the current moment. The operating time of the nuclear reactor is obtained, and a time threshold is set. If the operating time is greater than the preset time threshold, the correction coefficient is updated. For example, the time threshold is set to 7 days. Within this time threshold, it can be considered that the performance of the nuclear reactor core changes relatively little with the operating time, and the correction coefficient is still applicable, so there is no need to update the correction coefficient. If the operating time of the nuclear reactor is greater than or equal to 7 days, the performance of the nuclear reactor may have changed, resulting in the correction coefficient no longer being applicable to the current nuclear reactor, and thus the correction coefficient needs to be updated.

[0088] The above operation is performed because nuclear reactor performance may change over time due to, for example, burnup effects and equipment aging. These factors may cause the original correction coefficient to no longer be appropriate for the current state of the nuclear reactor, resulting in inaccurate corrections to the indications of the external detectors. Therefore, the correction coefficient needs to be updated. In this embodiment, by obtaining the operating time of the nuclear reactor and updating the correction coefficient if the operating time exceeds a preset threshold, the correction coefficient can be adapted to the changes in the long-term operation of the nuclear reactor, improving the effectiveness of the correction coefficient and thereby increasing the efficiency and accuracy of the correction process.

[0089] In order to more clearly illustrate the nuclear power measurement value correction method provided in this application, a specific embodiment and FIG6 are used to illustrate the method. The specific embodiment includes the following steps:

[0090] S200: Receive the nuclear power measurement value and thermal power measurement value of the nuclear reactor core in real time.

[0091] S400, when the nuclear reactor core first operates to a full-power steady state, obtains a first nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core; and when the nuclear reactor core first operates to a low-power steady state, obtains a second nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core.

[0092] S620: Determine a difference between the second nuclear power measurement value and the first nuclear power measurement value to obtain a nuclear power measurement difference.

[0093] S640: Determine a difference between the second thermal power measurement value and the first thermal power measurement value to obtain a thermal power measurement difference.

[0094] S660: Determine a correction coefficient based on the thermal power measurement difference and the nuclear power measurement difference.

[0095] S820: Obtain a first difference between the core power measurement value and the first core power measurement value.

[0096] S840: Determine a second difference between the nuclear power measurement value and the first nuclear power measurement value based on the first difference and the correction coefficient, where the second difference is a value obtained after the first difference is corrected.

[0097] S860: Obtain a nuclear power correction value according to the second difference and the first thermal power measurement value.

[0098] S920, obtaining the operating time of the nuclear reactor.

[0099] S940: If the running time is greater than the preset time threshold, the correction coefficient is updated.

[0100] 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.

[0101] Based on the same inventive concept, embodiments of the present application further provide a nuclear power measurement value correction device for implementing the aforementioned nuclear power measurement value correction method. The solution provided by this device is similar to the solution described in the aforementioned method. Therefore, the specific limitations of one or more embodiments of the nuclear power measurement value correction device provided below can be found in the above-described limitations of the nuclear power measurement value correction method and will not be further elaborated here.

[0102] In one embodiment, as shown in FIG7 , a nuclear power measurement value correction device 700 is provided, comprising: a real-time power receiving module 710 , a measurement value acquisition module 720 , a correction coefficient determination module 730 , and a measurement value correction module 740 , wherein:

[0103] A real-time power receiving module 710 is used to receive the nuclear power measurement value and the thermal power measurement value of the nuclear reactor core in real time;

[0104] The measurement value acquisition module 720 is used to obtain the first nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core when the nuclear reactor core first operates to a full-power steady state, and to obtain the second nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core when the nuclear reactor core first operates to a low-power steady state.

[0105] a correction coefficient determination module 730 for determining a correction coefficient based on the first nuclear power measurement value, the first thermal power measurement value, the second nuclear power measurement value, and the second thermal power measurement value;

[0106] The measurement value correction module 740 is used to correct the subsequently received nuclear power measurement value according to the correction coefficient to obtain a nuclear power correction value.

[0107] In one embodiment, the correction coefficient determination module 730 is also used to determine the difference between the second nuclear power measurement value and the first nuclear power measurement value to obtain the nuclear power measurement difference, determine the difference between the second thermal power measurement value and the first thermal power measurement value to obtain the thermal power measurement difference, and determine the correction coefficient based on the thermal power measurement difference and the nuclear power measurement difference.

[0108] In one embodiment, the correction coefficient determination module 730 is also used to obtain a pre-constructed functional relationship, where the functional relationship represents that the correction coefficient is equal to the ratio of the thermal power measurement difference to the nuclear power measurement difference, and the correction coefficient is determined based on the functional relationship, the thermal power measurement difference, and the nuclear power measurement difference.

[0109] In one embodiment, the measurement value correction module 740 is also used to obtain a first difference between the nuclear power measurement value and the first nuclear power measurement value, and determine a second difference between the nuclear power measurement value and the first nuclear power measurement value based on the first difference and the correction coefficient. The second difference is the value obtained after the first difference is corrected. The nuclear power correction value is obtained based on the second difference and the first thermal power measurement value.

[0110] In one embodiment, as shown in FIG8 , the nuclear power measurement value correction device 700 further includes a correction coefficient updating module 750 . The correction coefficient updating module 750 is configured to update the correction coefficient according to a preset correction coefficient updating condition.

[0111] In one embodiment, the correction coefficient updating module 750 is further configured to obtain the operating time of the nuclear reactor, and update the correction coefficient if the operating time is greater than a preset time threshold.

[0112] Each module in the aforementioned nuclear power measurement correction 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 in a computer device in the form of hardware, or may be stored in a memory in the computer device in the form of software, so that the processor can call and execute the corresponding operations of each module.

[0113] In one embodiment, a computer device is provided, which may be a server, and its internal structure diagram may be shown in Figure 8. The computer device includes a processor, memory, an input / output (I / O) interface, and a communication interface. The processor, memory, and I / O interface are connected via a system bus, and the communication interface is connected to the system bus via the I / O 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 data such as real-time nuclear power measurement values ​​and correction factors. The I / O interface of the computer device is used to exchange information between the processor and external devices. The communication interface of the computer device is used to communicate with external terminals via a network connection. When executed by the processor, the computer program implements a method for correcting nuclear power measurement values.

[0114] Those skilled in the art will understand that the structure shown in Figure 9 is merely a block diagram of a portion 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.

[0115] In one embodiment, a computer device is provided, including a memory and a processor. The memory stores a computer program, and the processor implements the steps in the above-mentioned embodiments of the nuclear power measurement value correction method when executing the computer program.

[0116] 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 steps in the above-mentioned nuclear power measurement value correction method embodiments are implemented.

[0117] In one embodiment, a computer program product is provided, comprising a computer program, which, when executed by a processor, implements the steps in the above-mentioned embodiments of the nuclear power measurement value correction method.

[0118] It should be noted that the user information (including but not limited to user device information, user personal information, etc.) and data (including but not limited to data used for analysis, stored data, displayed data, etc.) involved in this application are all information and data authorized by the user or fully authorized by all parties, and the collection, use and processing of relevant data must comply with the relevant laws, regulations and standards of relevant countries and regions.

[0119] 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.

[0120] The technical features of the above-mentioned embodiments can be combined arbitrarily. In order to make the description concise, not all possible combinations of the technical features in the above-mentioned 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.

[0121] 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 patent 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 patent application shall be determined by the appended claims.

Claims

1. A method for correcting nuclear power measurement values, characterized in that, The method includes: Receiving in real time the nuclear power measurement value and the thermal power measurement value of the nuclear reactor core; Under the condition that the nuclear reactor core runs to the full power steady state for the first time, obtaining the first nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core, and under the condition that the nuclear reactor core runs to the low power steady state for the first time, obtaining the second nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core; Determining a correction coefficient according to the first nuclear power measurement value, the first thermal power measurement value, the second nuclear power measurement value and the second thermal power measurement value; Correcting the subsequently received nuclear power measurement value according to the correction coefficient to obtain a nuclear power correction value.

2. The method according to claim 1, wherein The determining a correction coefficient according to the first nuclear power measurement value, the first thermal power measurement value, the second nuclear power measurement value and the second thermal power measurement value includes: Determining the difference between the second nuclear power measurement value and the first nuclear power measurement value to obtain a nuclear power measurement difference; Determining the difference between the second thermal power measurement value and the first thermal power measurement value to obtain a thermal power measurement difference; Determining a correction coefficient according to the thermal power measurement difference and the nuclear power measurement difference.

3. The method according to claim 2, wherein The determining a correction coefficient according to the thermal power measurement difference and the nuclear power measurement difference includes: Obtaining a pre-constructed functional relationship, where the functional relationship represents that the correction coefficient is equal to the ratio of the thermal power measurement difference to the nuclear power measurement difference; Determining a correction coefficient according to the functional relationship, the thermal power measurement difference, and the nuclear power measurement difference.

4. The method according to claim 1, characterized in that, The correcting the subsequently received nuclear power measurement value according to the correction coefficient to obtain a nuclear power correction value includes: Obtaining a first difference between the nuclear power measurement value and the first nuclear power measurement value; Determining a second difference between the nuclear power measurement value and the first nuclear power measurement value according to the first difference and the correction coefficient, where the second difference is a value obtained after the first difference is corrected; Obtaining a nuclear power correction value according to the second difference and the first thermal power measurement value.

5. The method according to any one of claims 1 to 4, characterized in that The method further includes: Updating the correction coefficient according to a preset correction coefficient update condition.

6. The method according to claim 5, characterized in that, The updating the correction coefficient according to a preset correction coefficient update condition includes: Obtaining the operation duration of the nuclear reactor; If the operation duration is greater than a preset duration threshold, updating the correction coefficient.

7. A nuclear power measurement value correction device, characterized in that, The device includes: A real-time power receiving module, configured to receive in real time the nuclear power measurement value and the thermal power measurement value of the nuclear reactor core; A measurement value obtaining module, configured to obtain the first nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core under the condition that the nuclear reactor core runs to the full power steady state for the first time, and obtain the second nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core under the condition that the nuclear reactor core runs to the low power steady state for the first time; A correction coefficient determining module, configured to determine a correction coefficient according to the first nuclear power measurement value, the first thermal power measurement value, the second nuclear power measurement value and the second thermal power measurement value; A measurement value correction module, configured to correct a subsequently received nuclear power measurement value according to the correction coefficient to obtain a nuclear power correction value.

8. The device according to claim 7, characterized in that, The correction coefficient determination module is further configured to determine a difference between the second nuclear power measurement value and the first nuclear power measurement value to obtain a nuclear power measurement difference; determine a difference between the second thermal power measurement value and the first thermal power measurement value to obtain a thermal power measurement difference; Determine a correction coefficient according to the thermal power measurement difference and the nuclear power measurement difference.

9. The device according to claim 8, characterized in that, The correction coefficient determination module is further configured to obtain a pre-constructed functional relationship, where the functional relationship represents that the correction coefficient is equal to the ratio of the thermal power measurement difference to the nuclear power measurement difference, and determine the correction coefficient according to the functional relationship, the thermal power measurement difference, and the nuclear power measurement difference.

10. The device according to claim 7, wherein The measurement value correction module is further configured to obtain a first difference between the nuclear power measurement value and the first nuclear power measurement value, determine a second difference between the nuclear power measurement value and the first nuclear power measurement value according to the first difference and the correction coefficient, where the second difference is a value obtained after the first difference is corrected, and obtain a nuclear power correction value according to the second difference and the first thermal power measurement value.

11. The device according to any one of claims 7 to 10, characterized in that The device further includes a correction coefficient update module, configured to update the correction coefficient according to a preset correction coefficient update condition.

12. The device according to claim 11, wherein, The correction coefficient update module is further configured to obtain the operation duration of the nuclear reactor, and if the operation duration is greater than a preset duration threshold, update the correction coefficient.

13. A computer device, comprising a memory and a processor, the memory storing a computer program, characterized in that, When the processor executes the computer program, the steps of the method according to any one of claims 1 to 6 are implemented.

14. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by the processor, the steps of the method according to any one of claims 1 to 6 are implemented.

15. A computer program product, comprising a computer program, characterized in that, When the computer program is executed by the processor, the steps of the method according to any one of claims 1 to 6 are implemented.

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