Method, device and computer equipment for determining deviation from nucleate boiling ratio
By calculating the integral power and peak axial linear power density of the thermal channel in a large pressurized water reactor nuclear power plant, and selecting key fuel assemblies for deviation from the nucleus boiling ratio calculation, the problem of large computational workload in traditional methods is solved, and the response speed and efficiency of the protection system are improved.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- CHINA NUCLEAR POWER TECH RES INST CO LTD
- Filing Date
- 2023-11-29
- Publication Date
- 2026-07-24
AI Technical Summary
In large pressurized water reactor nuclear power plants, the traditional method requires a huge amount of work to perform DNBR calculations on the thermal channels of each fuel assembly, which leads to a prolonged response time of the protection system.
By determining the axial linear power density and grid height of each fuel assembly in the reactor core, the integral power and peak axial linear power density of the thermal channels are calculated. Only key fuel assemblies are selected for deviation nucleus boiling ratio calculation, reducing the DNBR calculation workload for each fuel assembly.
This shortens the computational control delay time of the protection system, improving the response speed and working efficiency of the protection system.
Smart Images
Figure CN117763263B_ABST
Abstract
Description
Technical Field
[0001] This application relates to the field of nuclear reactor engineering technology, and in particular to a method, apparatus and computer equipment for determining the deviation of the nucleus boiling ratio. Background Technology
[0002] The Departure from Nucleate Boiling Ratio (DNBR) is the ratio of the critical heat flux density at a point on the surface of a fuel element in a coolant channel, calculated using a suitable critical heat flux density formula, to the actual heat flux density at that point. In pressurized water reactor nuclear power plants, in order to monitor the minimum DNBR value of the reactor core in real time and to implement core protection functions using the minimum DNBR value to prevent DNB from occurring in the core under accident conditions, it is necessary to measure the power distribution of the core in real time and calculate the minimum DNBR value of the core.
[0003] Large pressurized water reactors typically have a core with over 100 fuel assemblies, each of which can be divided into dozens of computational grids. Traditionally, a fixed self-powered neutron detector (SPND) positioned inside the core is used to measure the neutron flux density at the measurement point. Based on this neutron flux density, a core power reconstruction method is employed to reconstruct the line power density of the computational grid in each fuel assembly. Then, based on the line power density of the computational grid in each fuel assembly, multiple DNBR values for the thermal channels of each fuel assembly are calculated. Finally, the minimum DNBR value is determined from these multiple DNBR values.
[0004] However, for large pressurized water reactors, the core typically has more than 100 fuel assemblies, and each fuel assembly can be divided into dozens of computational grids. Therefore, the workload of performing DNBR calculations on the thermal channels of each fuel assembly is enormous. Summary of the Invention
[0005] Therefore, it is necessary to provide a method, apparatus, and computer equipment for determining the deviation nucleus boiling ratio that can reduce the number of deviation nucleus boiling ratio calculations, in order to address the above-mentioned technical problems.
[0006] Firstly, this application provides a method for determining the deviation from the nucleation-boiling ratio. The method includes:
[0007] The integral power of the thermal channel of each fuel assembly is determined based on the linear power density of each computational grid along the axial direction of each fuel assembly in the reactor core and the corresponding grid height.
[0008] Based on the line power density of each computational grid of each fuel assembly, determine the peak value of the axial line power density of the thermal channel of each fuel assembly.
[0009] The deviation from the core boiling ratio is determined based on the integral power of the thermal channel of each fuel assembly and the peak value of the axial linear power density.
[0010] In one embodiment, determining the core's deviation from nucleation boiling ratio based on the integrated power of the thermal channels of each fuel assembly and the peak value of the axial linear power density includes:
[0011] The target fuel assembly is determined from each fuel assembly based on the integrated power of the thermal channel of each fuel assembly and the peak value of the axial linear power density.
[0012] Determine the deviated nucleus boiling ratio of the target fuel assembly, and based on the deviated nucleus boiling ratio of the target fuel assembly, determine the deviated nucleus boiling ratio of the reactor core.
[0013] In one embodiment, determining a target fuel assembly from the fuel assemblies based on the integrated power of the thermal channels of each fuel assembly and the peak value of the axial linear power density includes:
[0014] According to the order of the integral power, starting from the largest integral power, the first preset number of integral power is selected in sequence;
[0015] The fuel assembly corresponding to the first preset number of integral power is selected as the first candidate fuel assembly;
[0016] According to the order of the peak values of axial linear power density, starting from the largest peak value of axial linear power density, the second preset number of peak values of axial linear power density are selected in sequence.
[0017] The fuel assembly corresponding to the peak axial linear power density of the second preset number is used as the second candidate fuel assembly;
[0018] Based on the first candidate fuel assembly and / or the second candidate fuel assembly, a target fuel assembly is determined from each of the fuel assemblies.
[0019] In one embodiment, determining the target fuel assembly from among the fuel assemblies based on the first candidate fuel assembly and / or the second candidate fuel assembly includes:
[0020] The union of the first candidate fuel assembly and the second candidate fuel assembly is taken as the target fuel assembly.
[0021] In one embodiment, determining the integral power of the thermal channels of each fuel assembly based on the linear power density of each computational grid along the axial direction of each fuel assembly in the reactor core and the corresponding grid height includes:
[0022] For each fuel assembly, determine the product between the line power density of each computational grid of the fuel assembly and the corresponding grid height;
[0023] The sum of the products corresponding to each computational grid is taken as the integral power of the thermal channel of the fuel assembly.
[0024] In one embodiment, determining the peak axial linear power density of the thermal channel of each fuel assembly based on the linear power density of each computational grid of each fuel assembly includes:
[0025] For each fuel assembly, the maximum linear power density corresponding to that fuel assembly is taken as the peak value of the axial linear power density of the thermal channel of that fuel assembly.
[0026] Secondly, this application also provides an apparatus for determining the deviation from the nucleation-boiling ratio. The apparatus includes:
[0027] The first determining module is used to determine the integral power of the thermal channel of each fuel assembly based on the linear power density of each computational grid along the axial direction of each fuel assembly in the reactor core and the grid height corresponding to that computational grid.
[0028] The second determining module is used to determine the peak value of the axial linear power density of the thermal channel of each fuel assembly based on the linear power density of each computational grid of each fuel assembly.
[0029] The third determining module is used to determine the core's deviation from the nucleation boiling ratio based on the integral power of the thermal channel of each fuel assembly and the peak value of the axial linear power density.
[0030] Thirdly, this application also provides a computer device, including a memory and a processor, the memory storing a computer program, the processor executing the computer program to implement the steps of any of the above methods.
[0031] Fourthly, this application also provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements the steps of any of the above methods.
[0032] Fifthly, this application also provides a computer program product, including a computer program that, when executed by a processor, implements the steps of any of the above methods.
[0033] The aforementioned method, apparatus, and computer equipment for determining the deviation from nucleus boiling ratio (DNBR) determine the integrated power of the thermal channels of each fuel assembly based on the linear power density of each computational grid along the axial direction of each fuel assembly and the corresponding grid height. Then, based on the linear power density of each computational grid of each fuel assembly, the peak axial linear power density of the thermal channels of each fuel assembly is determined. Finally, based on the integrated power and peak axial linear power density of the thermal channels of each fuel assembly, the deviation from nucleus boiling ratio of the core is determined. Since this embodiment does not require calculating all DNBR values for each fuel assembly in the core, but instead determines the deviation from nucleus boiling ratio based on the integrated power and peak axial linear power density of the thermal channels of each fuel assembly, the workload of calculating the DNBR of the thermal channels of each fuel assembly is reduced, shortening the instrumentation and control delay time of the protection system calculation, thereby shortening the response time of the protection system and improving the efficiency of the protection system in performing its protection functions. Attached Figure Description
[0034] Figure 1 An internal structural diagram of a computer device provided in an embodiment of this application;
[0035] Figure 2 A flowchart illustrating a method for determining the deviation from the nucleus boiling ratio provided in an embodiment of this application;
[0036] Figure 3 A flowchart illustrating another method for determining the deviation from the nucleation-boiling ratio provided in this application embodiment;
[0037] Figure 4 A flowchart illustrating a method for determining a target fuel assembly provided in an embodiment of this application;
[0038] Figure 5 A flowchart illustrating a method for determining integral power provided in an embodiment of this application;
[0039] Figure 6 A flowchart illustrating a method for determining the minimum deviation nucleus boiling ratio provided in an embodiment of this application;
[0040] Figure 7 This is a structural block diagram of a device for determining the deviation of the nucleus boiling ratio provided in an embodiment of this application. Detailed Implementation
[0041] To make the objectives, technical solutions, and advantages of this application clearer, the following detailed description is provided in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the scope of this application.
[0042] The Departure from Nucleate Boiling Ratio (DNBR) is the ratio of the critical heat flux density at a point on the surface of a fuel element in a coolant channel, calculated using a suitable critical heat flux density formula, to the actual heat flux density at that point. In pressurized water reactor nuclear power plants, in order to monitor the minimum DNBR value of the reactor core in real time and to implement core protection functions using the minimum DNBR value to prevent DNB from occurring in the core under accident conditions, it is necessary to measure the power distribution of the core in real time and calculate the minimum DNBR value of the core.
[0043] Large pressurized water reactors typically have a core with over 100 fuel assemblies, each of which can be divided into dozens of computational grids. Traditionally, a fixed self-powered neutron detector (SPND) positioned inside the core is used to measure the neutron flux density at the measurement point. Based on this neutron flux density, a core power reconstruction method is employed to reconstruct the line power density of the computational grid in each fuel assembly. Then, based on the line power density of the computational grid in each fuel assembly, multiple DNBR values for the thermal channels of each fuel assembly are calculated. Finally, the minimum DNBR value is determined from these multiple DNBR values.
[0044] However, for large pressurized water reactors, the core typically has more than 100 fuel assemblies, and each fuel assembly can be divided into dozens of computational grids. Therefore, the workload of performing DNBR calculations on the thermal channels of each fuel assembly is enormous.
[0045] The method for determining the deviation from the nucleus boiling ratio provided in this application embodiment can be applied to, for example, Figure 1 The application environment shown. Figure 1 This is an internal structure diagram of a computer device provided in an embodiment of this application. The computer device may be a server, and its internal structure diagram may be as follows: Figure 1 As shown, the computer device includes a processor, memory, and a network interface connected via a system bus. The processor provides computing and control capabilities. The memory includes non-volatile storage media and internal memory. The non-volatile storage media stores the operating system, computer programs, and a database. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The network interface is used to communicate with external terminals via a network connection. When executed by the processor, the computer program implements a method for determining the deviation from the nucleus-boiling ratio.
[0046] Those skilled in the art will understand that Figure 1The structure shown is merely a block diagram of a portion of the structure related to the present application and does not constitute a limitation on the computer device to which the present application is applied. Specific computer devices may include more or fewer components than those shown in the figure, or combine certain components, or have different component arrangements.
[0047] In one embodiment, such as Figure 2 As shown, Figure 2 This is a flowchart illustrating a method for determining the deviation of the nucleation-boiling ratio provided in an embodiment of this application. This method can be applied to... Figure 1 The method, using a computer device, includes the following steps:
[0048] S201. Based on the linear power density of each computational grid along the axial direction of each fuel assembly in the reactor core and the corresponding grid height, determine the integral power of the thermal channel of each fuel assembly.
[0049] In the embodiments of this application, each fuel assembly can be divided into a number of computational grids along its axial direction, and each fuel assembly corresponds to a thermal channel. Therefore, the thermal channels of each fuel assembly can also be divided into a corresponding number of computational grids.
[0050] In this embodiment, the integral power of the thermal channel of each fuel assembly can be determined as follows: The linear power density of each computational grid is multiplied by the corresponding grid height, and the sum of these products is used as the integral power of the thermal channel of each fuel assembly. Alternatively, the linear power density, the corresponding grid height, and a preset coefficient are multiplied by each computational grid, and the sum of these products is used as the integral power of the thermal channel of each fuel assembly.
[0051] S202, based on the linear power density of each computational grid of each fuel assembly, determine the peak value of the axial linear power density of the thermal channel of each fuel assembly.
[0052] In this embodiment, the peak value of the axial linear power density of the thermal channel of each fuel assembly can be determined in the following way: Select the maximum linear power density corresponding to each fuel assembly from the linear power densities of each computational grid of each fuel assembly, and use the maximum linear power density corresponding to each fuel assembly as the peak value of the axial linear power density of the thermal channel of each fuel assembly. Alternatively, select the maximum value from the product of the linear power density of each computational grid of each fuel assembly and a preset coefficient corresponding to each computational grid as the peak value of the axial linear power density of the thermal channel of each fuel assembly.
[0053] S203 determines the core deviation nucleation-boiling ratio based on the integrated power and peak axial linear power density of the thermal channels of each fuel assembly.
[0054] In this embodiment, the fuel assembly with the highest integrated power in the hot channel can be selected as the target fuel assembly. Then, the deviation from nucleus boiling ratio of the target fuel assembly is calculated, and the core's deviation from nucleus boiling ratio is determined based on this ratio. Alternatively, the fuel assembly with the highest peak axial power density in the hot channel can be selected as the target fuel assembly. Then, the deviation from nucleus boiling ratio of the target fuel assembly is calculated, and the core's deviation from nucleus boiling ratio is determined based on this ratio.
[0055] In this embodiment, the integral power of the thermal channels of each fuel assembly is determined based on the linear power density of each computational grid along the axial direction and the corresponding grid height. Then, the peak axial linear power density of the thermal channels of each fuel assembly is determined based on the linear power density of each computational grid. Finally, the deviation from nucleation-boiling ratio (DNBR) of the core is determined based on the integral power and peak axial linear power density of the thermal channels of each fuel assembly. Since this embodiment does not require calculating all DNBR values for each fuel assembly in the core, but instead determines the DNBR based on the integral power and peak axial linear power density of the thermal channels of each fuel assembly, the workload of calculating the DNBR for the thermal channels of each fuel assembly is reduced, shortening the instrumentation and control delay time of the protection system calculation, thereby shortening the response time of the protection system and improving the efficiency of the protection system in performing protection functions.
[0056] Reference Figure 3 , Figure 3 This is a flowchart illustrating another method for determining the deviation from the nucleus-boiling ratio provided in this application embodiment. This embodiment relates to a possible implementation of determining the core's deviation from the nucleus-boiling ratio based on the integrated power and peak axial linear power density of the thermal channels of each fuel assembly. Based on the above embodiment, S203 includes the following steps:
[0057] S301, based on the integrated power and peak axial power density of the thermal channels of each fuel assembly, determine the target fuel assembly from among the fuel assemblies.
[0058] In one possible implementation, a fuel assembly with an integral power greater than a preset integral power in the hot channel is selected as the target fuel assembly.
[0059] In another possible implementation, a fuel assembly with a peak axial power density in the thermal channel that is greater than a preset peak axial power density is selected as the target fuel assembly.
[0060] In another possible implementation, based on the integral power and peak axial power density of the thermal channels of each fuel assembly, a preset number of fuel assemblies are selected as target fuel assemblies. This can be achieved as follows: in order of the magnitude of the integral power, starting from the largest integral power, a first preset number of integral power assemblies are selected sequentially, and the fuel assemblies corresponding to the first preset number of integral power assemblies are selected as first candidate fuel assemblies. Then, in order of the magnitude of the peak axial power density, starting from the largest peak axial power density, a second preset number of peak axial power density are selected sequentially, and the fuel assemblies corresponding to the second preset number of peak axial power density are selected as second candidate fuel assemblies. The union of the first candidate fuel assemblies and the second candidate fuel assemblies is taken as the target fuel assembly.
[0061] S302, determine the deviation nucleus boiling ratio of the target fuel assembly, and determine the deviation nucleus boiling ratio of the reactor core based on the deviation nucleus boiling ratio of the target fuel assembly.
[0062] In this embodiment, the deviation nucleus boiling ratio of the target fuel assembly is determined, and the minimum deviation nucleus boiling ratio among the deviation nucleus boiling ratios of the target fuel assembly is taken as the deviation nucleus boiling ratio of the reactor core. Alternatively, the deviation nucleus boiling ratio of the target fuel assembly is determined, and the deviation nucleus boiling ratio of the target fuel assembly is multiplied by a preset parameter to obtain a product result, and the minimum value of the product result is taken as the deviation nucleus boiling ratio of the reactor core.
[0063] In this embodiment, a target fuel assembly is determined from the fuel assemblies based on the integrated power and peak axial power density of the thermal channels of each fuel assembly. Then, the deviation nucleus boiling ratio (DNBR) of the target fuel assembly is determined. Based on the DNBR of the target fuel assembly, the core's DNBR is determined. Since this embodiment determines the target fuel assembly from each fuel assembly, only the DNBR of the target fuel assembly needs to be calculated. This reduces the workload of performing DNBR calculations on the thermal channels of each fuel assembly, shortens the instrumentation delay time of the protection system, thereby shortening the response time of the protection system and improving the efficiency of the protection system in performing its protection functions.
[0064] Reference Figure 4 , Figure 4 This is a flowchart illustrating a method for determining a target fuel assembly according to an embodiment of this application. This embodiment relates to a possible implementation of determining a target fuel assembly from among various fuel assemblies based on the integrated power and peak axial linear power density of the thermal channels of each fuel assembly. Based on the above embodiment, step S301 includes the following steps:
[0065] S401, in order of the magnitude of the integral power, starting from the largest integral power, the first preset number of integral powers are selected sequentially.
[0066] In this embodiment, the integral power can be arranged in descending order, starting with the largest integral power and selecting a first preset number of integral power values sequentially. Alternatively, the integral power can be arranged in ascending order, starting with the largest integral power and selecting a first preset number of integral power values sequentially.
[0067] S402, the fuel assembly corresponding to the first preset number of integral power is selected as the first candidate fuel assembly.
[0068] In this embodiment of the application, for example, the integral power can be arranged in descending order, starting from the largest integral power, and i integral power can be selected in sequence, and the i fuel components corresponding to the i integral power can be used as the first candidate fuel components.
[0069] S403, in accordance with the order of the peak values of axial linear power density, starting from the largest peak value of axial linear power density, sequentially select the second preset number of peak values of axial linear power density.
[0070] In this embodiment, the axial linear power density peaks can be arranged in descending order, starting with the largest axial linear power density peak and sequentially selecting a second preset number of axial linear power density peaks. Alternatively, the axial linear power density peaks can be arranged in ascending order, starting with the largest axial linear power density peak and sequentially selecting a second preset number of axial linear power density peaks.
[0071] S404, the fuel assembly corresponding to the second preset number of axial linear power density peaks is selected as the second candidate fuel assembly.
[0072] In this embodiment of the application, for example, the axial linear power density peaks can be arranged in descending order. Starting from the largest axial linear power density peak, j axial linear power density peaks are selected sequentially, and the j fuel assemblies corresponding to the j axial linear power density peaks are selected as the second candidate fuel assemblies.
[0073] S405, determine the target fuel assembly from among the fuel assemblies based on the first candidate fuel assembly and / or the second candidate fuel assembly.
[0074] In the embodiments of this application, a first candidate fuel assembly can be used as the target fuel assembly. Alternatively, a second candidate fuel assembly can be used as the target fuel assembly. Or, the union of the first and second candidate fuel assemblies can be used as the target fuel assembly.
[0075] In this embodiment, following the order of integral power, starting with the largest integral power, a first preset number of integral power units are selected sequentially. The fuel assemblies corresponding to these first preset number of integral power units are designated as first candidate fuel assemblies. Then, following the order of axial linear power density peak values, starting with the largest axial linear power density peak value, a second preset number of axial linear power density peak values are selected sequentially. The fuel assemblies corresponding to these second preset number of axial linear power density peak values are designated as second candidate fuel assemblies. Finally, based on the first and / or second candidate fuel assemblies, a target fuel assembly is determined from among all fuel assemblies. Because this embodiment determines the target fuel assembly based on the first and / or second candidate fuel assemblies, the fuel assemblies are screened, reducing the workload of performing DNBR calculations on the thermal channels of each fuel assembly and improving work efficiency.
[0076] Based on the above embodiments, S405, which determines the target fuel assembly from among the fuel assemblies according to the first candidate fuel assembly and / or the second candidate fuel assembly, can be achieved in the following manner:
[0077] The union of the first and second candidate fuel assemblies is taken as the target fuel assembly.
[0078] In the embodiments of this application, if the fuel components in the first candidate fuel assembly and the second candidate fuel assembly completely overlap, then the first candidate fuel assembly or the second candidate fuel assembly is used as the target fuel assembly; if the first candidate fuel assembly and the second candidate fuel assembly contain the same fuel components, but are not completely identical, then the fuel component in the first candidate fuel assembly and the second candidate fuel assembly that does not overlap with the first candidate fuel assembly is used as the target fuel assembly; if the fuel components in the first candidate fuel assembly and the second candidate fuel assembly are completely different, then both the first candidate fuel assembly and the second candidate fuel assembly are used as the target fuel assembly.
[0079] In this embodiment, the union of the first candidate fuel assembly and the second candidate fuel assembly is used as the target fuel assembly. This eliminates duplicate fuel assemblies in the first and second candidate fuel assemblies, reduces the number of target fuel assemblies, thereby reducing the workload of performing DNBR calculations on the thermal channels of each fuel assembly and improving work efficiency.
[0080] Reference Figure 5 , Figure 5This is a flowchart illustrating a method for determining integrated power according to an embodiment of this application. This embodiment relates to a possible implementation of determining the integrated power of the thermal channels of each fuel assembly based on the line power density of each computational grid along the axial direction of each fuel assembly in the reactor core and the corresponding grid height. Based on the above embodiment, step S201 includes the following steps:
[0081] S501, for each fuel assembly, determine the product between the linear power density of each computational grid of the fuel assembly and the corresponding grid height.
[0082] In this embodiment, the linear power density of each computational grid of the fuel assembly can be multiplied by the corresponding grid height to obtain the corresponding product. Alternatively, the linear power density of each computational grid of the fuel assembly, the corresponding grid height, and a preset coefficient can be multiplied to obtain the corresponding product.
[0083] S502 uses the sum of the products of each computational grid as the integrated power of the thermal channels of the fuel assembly.
[0084] In this embodiment of the application, for each fuel assembly, the product between the linear power density of each computational grid of the fuel assembly and the corresponding grid height of the computational grid is determined, and the sum of the products corresponding to each computational grid is used as the integral power of the thermal channel of the fuel assembly. Since the larger the integral power of the thermal channel of the fuel assembly, the smaller the DNBR value of the thermal channel of the fuel assembly will be, the fuel assemblies to be calculated can be screened according to the integral power of the thermal channel of each fuel assembly.
[0085] Based on the above embodiments, in S202, determining the peak value of the axial linear power density of the thermal channel of each fuel assembly according to the linear power density of each computational grid of each fuel assembly can be achieved in the following way:
[0086] For each fuel assembly, the maximum linear power density corresponding to the fuel assembly is taken as the peak value of the axial linear power density of the thermal channel of the fuel assembly.
[0087] In this embodiment, the maximum linear power density corresponding to each fuel assembly can be selected from the linear power densities of each computational grid of each fuel assembly, and the maximum linear power density corresponding to each fuel assembly can be used as the peak value of the axial linear power density of the thermal channel of each fuel assembly. Alternatively, the maximum value can be selected as the peak value of the axial linear power density of the thermal channel of each fuel assembly from the product of the linear power density of each computational grid of each fuel assembly and the preset coefficient corresponding to each computational grid.
[0088] In this embodiment, for each fuel assembly, the maximum linear power density corresponding to the fuel assembly is taken as the peak value of the axial linear power density of the thermal channel of the fuel assembly. Since the higher the peak value of the axial linear power density of the thermal channel of the fuel assembly, the smaller the DNBR value of the thermal channel of the fuel assembly will be, the fuel assemblies whose DNBR value is to be calculated can be screened according to the peak value of the axial linear power density of the thermal channel of each fuel assembly.
[0089] Reference Figure 6 , Figure 6 This is a flowchart illustrating a method for determining the minimum deviation nucleus boiling ratio provided in an embodiment of this application. The method includes the following steps:
[0090] S601, for each fuel assembly, determine the product between the linear power density of each computational grid of the fuel assembly and the corresponding grid height.
[0091] S602 uses the sum of the products of each computational grid as the integrated power of the thermal channels of the fuel assembly.
[0092] S603, in accordance with the order of integral power, starting from the largest integral power, sequentially selects the first preset number of integral power.
[0093] S604, the fuel assembly corresponding to the first preset number of integral power is selected as the first candidate fuel assembly.
[0094] S605, for each fuel assembly, takes the maximum linear power density corresponding to the fuel assembly as the peak value of the axial linear power density of the thermal channel of the fuel assembly.
[0095] S606, in accordance with the order of the peak values of axial linear power density, starting from the largest peak value of axial linear power density, sequentially select the second preset number of peak values of axial linear power density.
[0096] S607, the fuel assembly corresponding to the second preset number of axial linear power density peaks is selected as the second candidate fuel assembly.
[0097] S608, take the union of the first candidate fuel assembly and the second candidate fuel assembly as the target fuel assembly.
[0098] S609, determine the deviation nucleation-boiling ratio of the target fuel assembly.
[0099] S610 selects the smallest deviated nucleus boiling ratio from the target fuel assembly's deviated nucleus boiling ratios as the core's minimum deviated nucleus boiling ratio.
[0100] It should be understood that although the steps in the flowcharts of the embodiments described above are shown sequentially according to the arrows, these steps are not necessarily executed in the order indicated by the arrows. Unless explicitly stated herein, there is no strict order restriction on the execution of these steps, and they can be executed in other orders. Moreover, at least some steps in the flowcharts of the embodiments described above may include multiple steps or multiple stages. These steps or stages are not necessarily completed at the same time, but can be executed at different times. The execution order of these steps or stages is not necessarily sequential, but can be performed alternately or in turn with other steps or at least some of the steps or stages of other steps.
[0101] Based on the same inventive concept, this application also provides an apparatus for determining the deviation from the nucleus-boiling ratio to implement the above-described method for determining the deviation from the nucleus-boiling ratio. The solution provided by this apparatus is similar to the solution described in the above-described method. Therefore, the specific limitations in one or more embodiments of the apparatus for determining the deviation from the nucleus-boiling ratio provided below can be found in the limitations of the method for determining the deviation from the nucleus-boiling ratio described above, and will not be repeated here.
[0102] In one embodiment, such as Figure 7 As shown, Figure 7 This is a structural block diagram of a device for determining the deviation of the nucleation-boiling ratio provided in an embodiment of this application. The device 700 includes:
[0103] The first determining module 701 is used to determine the integral power of the thermal channel of each fuel assembly based on the linear power density of each computational grid along the axial direction of each fuel assembly in the reactor core and the corresponding grid height.
[0104] The second determining module 702 is used to determine the peak value of the axial linear power density of the thermal channel of each fuel assembly based on the linear power density of each computational grid of each fuel assembly.
[0105] The third determining module 703 is used to determine the core deviation nucleation boiling ratio based on the integrated power and axial linear power density peak of the thermal channels of each fuel assembly.
[0106] In one embodiment, the third determining module 703 includes:
[0107] The first determining unit is used to determine the target fuel assembly from among the fuel assemblies based on the integrated power and peak axial power density of the thermal channels of each fuel assembly.
[0108] The second determining unit determines the deviation nucleus boiling ratio of the target fuel assembly and, based on the deviation nucleus boiling ratio of the target fuel assembly, determines the deviation nucleus boiling ratio of the reactor core.
[0109] In one embodiment, the first determining unit includes:
[0110] The first selection subunit is used to select a first preset number of integral powers in order of magnitude of the integral power, starting from the largest integral power.
[0111] The first determining subunit is used to select the fuel assembly corresponding to the first preset number of integral power as the first candidate fuel assembly.
[0112] The second selection subunit is used to select a second preset number of axial linear power density peaks in sequence, starting from the largest axial linear power density peak.
[0113] The second determining subunit is used to select the fuel assembly corresponding to the second preset number of axial linear power density peaks as the second candidate fuel assembly.
[0114] The third determining subunit is used to determine the target fuel assembly from among the fuel assemblies based on the first candidate fuel assembly and / or the second candidate fuel assembly.
[0115] In one embodiment, the third determining subunit is specifically used to take the union of the first candidate fuel assembly and the second candidate fuel assembly as the target fuel assembly.
[0116] In one embodiment, the first determining module 701 is specifically used to determine, for each fuel assembly, the product between the linear power density of each computational grid of the fuel assembly and the grid height corresponding to the computational grid, and to use the sum of the products corresponding to each computational grid as the integral power of the thermal channel of the fuel assembly.
[0117] In one embodiment, the second determining module 702 is specifically used to determine the maximum linear power density corresponding to each fuel assembly as the peak value of the axial linear power density of the thermal channel of the fuel assembly.
[0118] Each module in the aforementioned device for determining the deviation from the nucleus-boiling ratio can be implemented entirely or partially through software, hardware, or a combination thereof. These modules can be embedded in or independent of the processor in a computer device, or stored in the memory of a computer device as software, so that the processor can call and execute the operations corresponding to each module.
[0119] In one embodiment, a computer device is provided, including a memory and a processor, wherein the memory stores a computer program, and the processor executes the computer program to perform the following steps:
[0120] The integral power of the thermal channel of each fuel assembly is determined based on the linear power density of each computational grid along the axial direction of each fuel assembly in the reactor core and the corresponding grid height.
[0121] Based on the linear power density of each computational grid of each fuel assembly, the peak value of the axial linear power density of the thermal channel of each fuel assembly is determined.
[0122] The core deviation nucleation boiling ratio is determined based on the integrated power and peak axial power density of the thermal channels of each fuel assembly.
[0123] In one embodiment, the processor, when executing a computer program, also performs the following steps:
[0124] The target fuel assembly is determined from each fuel assembly based on the integrated power and peak axial power density of the thermal channels of each fuel assembly.
[0125] Determine the deviated nucleus boiling ratio of the target fuel assembly, and based on the deviated nucleus boiling ratio of the target fuel assembly, determine the deviated nucleus boiling ratio of the reactor core.
[0126] In one embodiment, the processor, when executing a computer program, also performs the following steps:
[0127] According to the order of the integral power, starting from the largest integral power, the first preset number of integral power is selected in sequence;
[0128] The fuel assembly corresponding to the first preset number of integral power is selected as the first candidate fuel assembly;
[0129] According to the order of the peak values of axial linear power density, starting from the largest peak value of axial linear power density, the second preset number of peak values of axial linear power density are selected in sequence.
[0130] The fuel assembly corresponding to the peak axial linear power density of the second preset number is used as the second candidate fuel assembly;
[0131] The target fuel assembly is determined from the fuel assemblies based on the first candidate fuel assembly and / or the second candidate fuel assembly.
[0132] In one embodiment, the processor, when executing a computer program, also performs the following steps:
[0133] The union of the first and second candidate fuel assemblies is taken as the target fuel assembly.
[0134] In one embodiment, the processor, when executing a computer program, also performs the following steps:
[0135] For each fuel assembly, determine the product between the linear power density of each computational grid of the fuel assembly and the corresponding grid height;
[0136] The sum of the products corresponding to each computational grid is used as the integral power of the thermal channel of the fuel assembly.
[0137] In one embodiment, the processor, when executing a computer program, also performs the following steps:
[0138] For each fuel assembly, the maximum linear power density corresponding to the fuel assembly is taken as the peak value of the axial linear power density of the thermal channel of the fuel assembly.
[0139] In one embodiment, a computer-readable storage medium is provided having a computer program stored thereon, the computer program performing the following steps when executed by a processor:
[0140] The integral power of the thermal channel of each fuel assembly is determined based on the linear power density of each computational grid along the axial direction of each fuel assembly in the reactor core and the corresponding grid height.
[0141] Based on the linear power density of each computational grid of each fuel assembly, the peak value of the axial linear power density of the thermal channel of each fuel assembly is determined.
[0142] The core deviation nucleation boiling ratio is determined based on the integrated power and peak axial power density of the thermal channels of each fuel assembly.
[0143] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0144] The target fuel assembly is determined from each fuel assembly based on the integrated power and peak axial power density of the thermal channels of each fuel assembly.
[0145] Determine the deviated nucleus boiling ratio of the target fuel assembly, and based on the deviated nucleus boiling ratio of the target fuel assembly, determine the deviated nucleus boiling ratio of the reactor core.
[0146] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0147] According to the order of the integral power, starting from the largest integral power, the first preset number of integral power is selected in sequence;
[0148] The fuel assembly corresponding to the first preset number of integral power is selected as the first candidate fuel assembly;
[0149] According to the order of the peak values of axial linear power density, starting from the largest peak value of axial linear power density, the second preset number of peak values of axial linear power density are selected in sequence.
[0150] The fuel assembly corresponding to the peak axial linear power density of the second preset number is used as the second candidate fuel assembly;
[0151] The target fuel assembly is determined from the fuel assemblies based on the first candidate fuel assembly and / or the second candidate fuel assembly.
[0152] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0153] The union of the first and second candidate fuel assemblies is taken as the target fuel assembly.
[0154] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0155] For each fuel assembly, determine the product between the linear power density of each computational grid of the fuel assembly and the corresponding grid height;
[0156] The sum of the products corresponding to each computational grid is used as the integral power of the thermal channel of the fuel assembly.
[0157] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0158] For each fuel assembly, the maximum linear power density corresponding to the fuel assembly is taken as the peak value of the axial linear power density of the thermal channel of the fuel assembly.
[0159] In one embodiment, a computer program product is provided, including a computer program that, when executed by a processor, performs the following steps:
[0160] The integral power of the thermal channel of each fuel assembly is determined based on the linear power density of each computational grid along the axial direction of each fuel assembly in the reactor core and the corresponding grid height.
[0161] Based on the linear power density of each computational grid of each fuel assembly, the peak value of the axial linear power density of the thermal channel of each fuel assembly is determined.
[0162] The core deviation nucleation boiling ratio is determined based on the integrated power and peak axial power density of the thermal channels of each fuel assembly.
[0163] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0164] The target fuel assembly is determined from each fuel assembly based on the integrated power and peak axial power density of the thermal channels of each fuel assembly.
[0165] Determine the deviated nucleus boiling ratio of the target fuel assembly, and based on the deviated nucleus boiling ratio of the target fuel assembly, determine the deviated nucleus boiling ratio of the reactor core.
[0166] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0167] According to the order of the integral power, starting from the largest integral power, the first preset number of integral power is selected in sequence;
[0168] The fuel assembly corresponding to the first preset number of integral power is selected as the first candidate fuel assembly;
[0169] According to the order of the peak values of axial linear power density, starting from the largest peak value of axial linear power density, the second preset number of peak values of axial linear power density are selected in sequence.
[0170] The fuel assembly corresponding to the peak axial linear power density of the second preset number is used as the second candidate fuel assembly;
[0171] The target fuel assembly is determined from the fuel assemblies based on the first candidate fuel assembly and / or the second candidate fuel assembly.
[0172] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0173] The union of the first and second candidate fuel assemblies is taken as the target fuel assembly.
[0174] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0175] For each fuel assembly, determine the product between the linear power density of each computational grid of the fuel assembly and the corresponding grid height;
[0176] The sum of the products corresponding to each computational grid is used as the integral power of the thermal channel of the fuel assembly.
[0177] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0178] For each fuel assembly, the maximum linear power density corresponding to the fuel assembly is taken as the peak value of the axial linear power density of the thermal channel of the fuel assembly.
[0179] Those skilled in the art will understand that all or part of the processes in the methods of the above embodiments can be implemented by a computer program instructing related hardware. The computer program can be stored in a non-volatile computer-readable storage medium, and when executed, it can include the processes of the embodiments of the above methods. Any references to memory, databases, or other media used in the embodiments provided in this application can include at least one of non-volatile and volatile memory. Non-volatile memory can 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 can include random access memory (RAM) or external cache memory, etc. By way of illustration and not limitation, RAM can take many forms, such as Static Random Access Memory (SRAM) or Dynamic Random Access Memory (DRAM). The databases involved in the embodiments provided in this application may include at least one type of relational database and non-relational database. Non-relational databases may include, but are not limited to, blockchain-based distributed databases. The processors involved in the embodiments provided in this application may be general-purpose processors, central processing units, graphics processing units, digital signal processors, programmable logic devices, quantum computing-based data processing logic devices, etc., and are not limited to these.
[0180] The technical features of the above embodiments can be combined in any way. For the sake of brevity, 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.
[0181] The embodiments described above are merely illustrative of several implementation methods of this application, and while the descriptions are specific and detailed, they should not be construed as limiting the scope of this patent application. It should be noted that those skilled in the art can make various modifications and improvements without departing from the concept of this application, and these all fall within the protection scope of this application. Therefore, the protection scope of this application should be determined by the appended claims.
Claims
1. A method for determining the deviation from the nucleus boiling ratio, characterized in that, The method includes: The integral power of the thermal channel of each fuel assembly is determined based on the linear power density of each computational grid along the axial direction of each fuel assembly in the reactor core and the grid height corresponding to the computational grid. The peak value of the axial linear power density of the thermal channel of each fuel assembly is determined based on the linear power density of each computational grid of each fuel assembly. The target fuel assembly is determined from the fuel assemblies based on the integral power of the thermal channels of each fuel assembly and the peak value of the axial linear power density. Determine the deviation nucleus boiling ratio of the target fuel assembly, and determine the deviation nucleus boiling ratio of the reactor core based on the deviation nucleus boiling ratio of the target fuel assembly; The step of determining the target fuel assembly from each of the fuel assemblies based on the integrated power of the thermal channels of each fuel assembly and the peak value of the axial linear power density includes: According to the order of the integral power, starting from the largest integral power, the first preset number of integral power is selected in sequence; The fuel assembly corresponding to the first preset number of integral power is selected as the first candidate fuel assembly; According to the order of the peak values of axial linear power density, starting from the largest peak value of axial linear power density, the second preset number of peak values of axial linear power density are selected in sequence. The fuel assembly corresponding to the peak axial linear power density of the second preset number is used as the second candidate fuel assembly; A target fuel assembly is determined from each of the fuel assemblies based on the first candidate fuel assembly and / or the second candidate fuel assembly.
2. The method according to claim 1, characterized in that, The step of determining the target fuel assembly from the fuel assemblies based on the first candidate fuel assembly and / or the second candidate fuel assembly includes: The union of the first candidate fuel assembly and the second candidate fuel assembly is taken as the target fuel assembly.
3. The method according to any one of claims 1-2, characterized in that, The determination of the integral power of the thermal channels of each fuel assembly based on the linear power density of each computational grid along the axial direction of each fuel assembly in the reactor core and the corresponding grid height includes: For each of the fuel assemblies, determine the product between the line power density of each computational grid of the fuel assembly and the grid height corresponding to the computational grid; The sum of the products corresponding to each of the computational grids is taken as the integral power of the thermal channel of the fuel assembly.
4. The method according to claim 1, characterized in that, The step of determining the peak axial linear power density of the thermal channel of each fuel assembly based on the linear power density of each computational grid of each fuel assembly includes: For each of the fuel assemblies, the maximum linear power density corresponding to the fuel assembly is taken as the peak value of the axial linear power density of the thermal channel of the fuel assembly.
5. A device for determining the deviation from the nucleus boiling ratio, characterized in that, The device includes: The first determining module is used to determine the integral power of the thermal channel of each fuel assembly based on the linear power density of each computational grid along the axial direction of each fuel assembly in the reactor core and the grid height corresponding to the computational grid. The second determining module is used to determine the peak value of the axial linear power density of the thermal channel of each fuel assembly based on the linear power density of each computational grid of each fuel assembly. The third determining module is used to determine a target fuel assembly from the fuel assemblies based on the integral power of the thermal channels of each fuel assembly and the peak value of the axial linear power density; determine the deviation nucleus boiling ratio of the target fuel assembly; and determine the deviation nucleus boiling ratio of the reactor core based on the deviation nucleus boiling ratio of the target fuel assembly. Specifically, the third determining module is used to select a first preset number of integral power components in order of magnitude, starting from the largest integral power; to select the fuel components corresponding to the first preset number of integral power components as first candidate fuel components; to select a second preset number of axial power density peak values in order of magnitude, starting from the largest axial power density peak value; to select the fuel components corresponding to the second preset number of axial power density peak values as second candidate fuel components; and to determine the target fuel component from the fuel components based on the first candidate fuel components and / or the second candidate fuel components.
6. The apparatus according to claim 5, characterized in that, The third determining module is specifically used to take the union of the first candidate fuel assembly and the second candidate fuel assembly as the target fuel assembly.
7. The apparatus according to any one of claims 5-6, characterized in that, The first determining module is specifically used to determine, for each of the fuel assemblies, the product between the line power density of each computational grid of the fuel assembly and the grid height corresponding to the computational grid; and to use the sum of the products corresponding to each computational grid as the integral power of the thermal channel of the fuel assembly.
8. The apparatus according to claim 5, characterized in that, The second determining module is specifically used to take the maximum linear power density corresponding to each fuel assembly as the peak value of the axial linear power density of the thermal channel of the fuel assembly.