Method, device and apparatus for analyzing core power distribution measurement uncertainty

Abstract

The application relates to a reactor core power distribution measurement uncertainty analysis method, device, equipment, storage medium and product. The method comprises the following steps: constructing a simulation operation state based on an actual operation state of a reactor core, determining state parameters of the reactor core in the simulation operation state, and obtaining group constants of the reactor core; performing calculation based on a material calculation subprogram and the state parameters to obtain material compositions of each fuel rod in the reactor core; performing calculation based on a power calculation subprogram and the material compositions of each fuel rod to obtain a real power distribution of the reactor core and obtain detector reaction intensities of the reactor core; determining power parameters of the reactor core in the simulation operation state based on the state parameters and the group constants, and performing flux map simulation based on the power parameters and the detector reaction intensities to obtain a simulation power distribution of the reactor core; and determining a measurement uncertainty of the reactor core power distribution based on a difference between the real power distribution and the simulation power distribution. The method can improve the accuracy and acquisition speed of the reactor core power distribution measurement uncertainty.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of reactor core measurement and protection, and particularly relates to a method and device for analyzing uncertainty of core power distribution measurement, computer equipment, a storage medium and a computer program product. BACKGROUND

[0002] A core neutron flux measurement system is generally used for core power distribution measurement or triggering signals of a core protection system according to measurement results, and the measurement results are obtained by reconstructing actual measurement values of partial channels in combination with theoretical values.

[0003] In the conventional technology, a core calculation program is mainly used for sensitivity analysis to confirm disturbance of each input uncertainty component on a calculation result, and the final uncertainty of a measurement system is given by a statistical method. However, the power parameters used in the calculation process in the prior art are all hypothetical theoretical parameters, which will cause a large difference between the actual core power parameters considered in the calculation and the actual parameters of the core, and finally lead to unreasonable measurement uncertainty. SUMMARY

[0004] Therefore, it is necessary to provide a method and device for analyzing uncertainty of core power distribution measurement, computer equipment, a storage medium and a computer program product, which can improve the accuracy and acquisition speed of the analysis of the uncertainty of core power distribution measurement.

[0005] In a first aspect, the present application provides a method for analyzing uncertainty of core power distribution measurement, and the method comprises the following steps.

[0006] constructing a simulated operating state based on an actual operating state of a core, determining state parameters of the core in the simulated operating state, and obtaining group constants representing grid cross-section values of the core;

[0007] performing material composition calculation based on a material calculation subprogram in an accurate calculation program and the state parameters, to obtain material compositions of each fuel rod in the core;

[0008] performing power calculation based on a power calculation subprogram in the accurate calculation program and the material compositions of each fuel rod, to obtain a real power distribution of the core, and obtaining a detector reaction intensity of the core;

[0009] determining power parameters of the core in the simulated operating state based on the state parameters and the group constants, and performing flux map simulation measurement based on the detector reaction intensity and the power parameters, to obtain a simulated power distribution of the core;

[0010] determine a measurement uncertainty of the power distribution of the core based on a difference between the real power distribution and the simulated power distribution.

[0011] In one of the embodiments, the obtaining the group constants representing the mesh cross-section values of the core comprises:

[0012] obtaining assembly burnups and state parameters of the core in a simulated operating state;

[0013] determining assembly and reflector group constants of the core based on the assembly burnups and the state parameters.

[0014] In one of the embodiments, the determining the power parameters of the core in the simulated operating state based on the state parameters and the group constants comprises:

[0015] using a core nuclear design program to determine the power parameters of the core in the simulated operating state based on the state parameters and the group constants;

[0016] after the determining the power parameters of the core in the simulated operating state, comprising:

[0017] constructing a theoretical library realizing power distribution reconstruction of the core based on the power parameters;

[0018] performing flux map simulation measurement based on the theoretical library to obtain a simulated power distribution of the core.

[0019] In one of the embodiments, the performing material composition calculation based on the material calculation subprogram in the precise calculation program and the state parameters to obtain material compositions of fuel rods in the core comprises:

[0020] using a burnup calculation subprogram in a Monte Carlo program to calculate burnups of the assemblies of the core in the simulated operating state based on the state parameters to obtain the burnups of the assemblies;

[0021] using the material calculation subprogram in the Monte Carlo program to determine the material compositions of the fuel rods in the assemblies based on the burnups of the assemblies.

[0022] In one of the embodiments, the obtaining the detector reaction intensity of the core comprises:

[0023] obtaining a manufacturing error of the detector and a current algorithm error of the detector;

[0024] superimposing data representing uncertainty on the detector reaction intensity based on the manufacturing error and the current algorithm error to obtain the detector reaction intensity superimposed with the data representing uncertainty.

[0025] In one embodiment, the method further comprises:

[0026] constructing a plurality of simulated operating states of the core and state parameters of the core in each of the simulated operating states;

[0027] obtaining a power deviation between a real power distribution and a simulated power distribution of the core in each of the simulated operating states;

[0028] statistically analyzing the power deviation in each of the simulated operating states to obtain a measurement uncertainty of the power distribution of the core.

[0029] In a second aspect, the present application provides an analysis device for a measurement uncertainty of a core power distribution, the device comprising:

[0030] a state construction module configured to construct a simulated operating state based on an actual operating state of a core, determine state parameters of the core in the simulated operating state, and obtain group constants representing mesh cross-section values of the core;

[0031] a material composition calculation module configured to perform material composition calculation based on a material calculation subprogram in an accurate calculation program and the state parameters, and obtain material compositions of fuel rods in the core;

[0032] a real power distribution determination module configured to perform power calculation based on a power calculation subprogram in the accurate calculation program and the material compositions of the fuel rods, obtain a real power distribution of the core, and obtain detector reaction intensities of the core;

[0033] a simulated power distribution determination module configured to determine power parameters of the core in the simulated operating state based on the state parameters and the group constants, and perform flux map simulation measurement based on the detector reaction intensities and the power parameters to obtain a simulated power distribution of the core;

[0034] a measurement uncertainty determination module configured to determine a measurement uncertainty of the power distribution of the core based on a difference between the real power distribution and the simulated power distribution.

[0035] In a third aspect, the present application provides a computer device comprising a memory and a processor, wherein the memory stores a computer program, and the processor implements steps of the above method when executing the computer program.

[0036] In a fourth aspect, the present application provides a computer readable storage medium having a computer program stored thereon, wherein the computer program is executed by a processor to implement steps of the above method.

[0037] In a fifth aspect, the present application provides a computer program product comprising a computer program which, when executed by a processor, implements the steps of the method described above.

[0038] The analysis method, device, computer device, storage medium and computer program product of the core power distribution measurement uncertainty can make the state parameters of the constructed core simulation running state more consistent with the actual situation of the core operation, and can also solve the problem of data missing by the constructed simulation running state and the state parameters of the simulation running state in the case of lacking a large amount of reactor core measurement test data. The material composition of the fuel rod is determined based on the state parameters by using the material calculation subprogram, and the real power distribution of the core is determined based on the material composition of the fuel rod by using the power calculation subprogram, so that the two calculation processes are decoupled, the coupling relationship between the two steps does not affect the result and speed of the calculation, the speed and accuracy of the real power distribution are improved, and the accuracy of the core power distribution measurement uncertainty determined by the simulation power distribution and the real power distribution of the core is improved. BRIEF DESCRIPTION OF DRAWINGS

[0039] Figure 1 The application environment diagram of the core power distribution measurement uncertainty analysis method in an embodiment is shown in FIG. 1.

[0040] Figure 2 The flowchart of the core power distribution measurement uncertainty analysis method in an embodiment is shown in FIG. 2.

[0041] Figure 3 The structure block diagram of the core power distribution measurement uncertainty analysis device in an embodiment is shown in FIG. 3.

[0042] Figure 4 The internal structure diagram of the computer device in an embodiment is shown in FIG. 4. DETAILED DESCRIPTION

[0043] In order to make the purpose, technical scheme and advantages of the present application clearer, the present application will be further described in detail below with reference to the drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present application and do not limit the present application.

[0044] The core power distribution measurement uncertainty analysis method provided by the embodiments of the present application can be applied to, for example, Figure 1The application environment is shown. The terminal 102 communicates with the server 104 through the network. The data storage system can store the data required by the server 104 to process. The data storage system can be integrated on the server 104, or placed on the cloud or other network servers. The server 104 constructs the simulated operating state of the core according to the actual operating state of the core during the actual operation of the core, determines the state parameters of the core in the simulated operating state according to the actual operating state of the core, and further obtains the group constant representing the grid cross-section value in the core. The server 104 uses the material calculation subprogram in the precise calculation program to perform material composition calculation of the fuel rods based on the state parameters of the core in the simulated operating state, so as to obtain the material composition of each fuel rod in the core. The server 104 uses the power calculation subprogram in the precise calculation program to perform power calculation based on the obtained material composition of each fuel rod, so as to obtain the real power distribution of the core in the simulated operating state and the probe reaction intensity of the core. The server 104 calculates the power parameters of the core in the simulated operating state based on the state parameters of the simulated operating state and the group constant of the core, and performs flux map simulation measurement using the power parameters and the probe reaction intensity, so as to obtain the simulated power distribution of the core in the simulated operating state. The server 104 obtains the measurement uncertainty of the core power distribution according to the difference between the real power distribution and the simulated power distribution of the core in the simulated operating state. The terminal 102 can be, but is not limited to, various personal computers, notebook computers, tablet computers and the like. The server 104 can be implemented by an independent server or a server cluster composed of multiple servers.

[0045] In one embodiment, as shown in Figure 2 , a method for analyzing the measurement uncertainty of the core power distribution is provided. The method is applied to the server in Figure 1 for illustration, including the following steps:

[0046] Step 202, based on the actual operating state of the core, constructing the simulated operating state, determining the state parameters of the core in the simulated operating state, and obtaining the group constant representing the grid cross-section value of the core.

[0047] The state parameters include the burnup value BU(i,j) of each grid of the reactor core, the fuel temperature Tf(i,j), the moderator temperature Tm(i,j), the moderator density Dm(i,j), the 135Xe concentration Xe(i,j), the 149Sm concentration Sm(i,j), and the insertion position CR(m) of each group of control rods, where i is the grid number i=1,...,I in the radial direction of the core, j is the grid number in the axial direction of the core, j=1,...,J, m is the number of control rods of the core, m=1,...,M.

[0048] The actual operation state of the reactor core refers to various possible physical states of the reactor core in reality. The simulated operation state of the reactor core is constructed, and the state parameters of the simulated operation state need to conform to the actual situation. When constructing the simulated operation state of the reactor core, the simulated operation state is constructed based on the assembly burnup and reflector parameters of the reactor core in the actual operation state. The reflector parameters mainly include the boron concentration of the reactor core, the fuel temperature, the moderator temperature and water density, the control rod insertion state, the fuel depth, and the like. For example, the boron concentration at each position of the reactor core in the simulated state should be approximately equal, and the water density should not have a large position distribution gradient, and the like. The advantage of constructing the simulated operation state is that, in the case where a large amount of reactor core measurement test data is lacking, the measurement uncertainty of the reactor core measurement system in the power distribution and the like can be confirmed through a theoretical calculation scheme.

[0049] Before performing the power distribution measurement uncertainty analysis of the reactor core, the loading mode of the reactor core and the type of the in-core probe need to be determined. Since the measurement uncertainty is related to the loading of the reactor core, after the loading mode of the reactor core is determined, the basis for all analyses is determined, and the subsequent analyses are no longer changed. All analyses are carried out based on the loading mode of the reactor core, that is, the analysis mode of the power distribution measurement uncertainty of the reactor core is determined based on the loading mode of the reactor core. The loading mode of the reactor core mainly includes OUT-IN (output-input) loading, low leakage loading, and the like. The type of the probe mainly includes a movable micro fission chamber, a fixed self-powered probe, a pneumatic small ball, and the like.

[0050] Optionally, the server constructs a simulated operation state of the reactor core according to the assembly burnup and reflector parameters in the actual operation state process of the reactor core, and determines the burnup value, the fuel temperature, the moderator temperature, the moderator density, the 135Xe concentration, the 149Sm concentration, and the insertion position of each group of control rods of the reactor core at each grid in the simulated operation state of the reactor core by using a reactor core diffusion program. The server also obtains group constants representing the grid cross-section value of the reactor core.

[0051] In step 204, material composition calculation is performed based on the material calculation subprogram in the precise calculation program and the state parameters, to obtain the material composition of each fuel rod in the reactor core.

[0052] The precise calculation program mainly includes a Monte Carlo program, and a deterministic program comparable to the Monte Carlo program, and the like.

[0053] The material calculation subprogram is a program in the precise calculation program for calculating the composition or proportion of each material in the remaining material of the fuel rod. The materials in the fuel rod will split during the burning process, for example, one material splits into two materials, so the quantity of the material will change, and therefore the composition of each material needs to be calculated. The material composition refers to the composition of each material remaining in the fuel rod during the burning process, which can also be understood as the proportion of the quantity of each material in the quantity of the remaining material.

[0054] Optionally, the server uses the material calculation subprogram part in the Monte Carlo program to calculate the composition of the remaining material in each fuel rod in the core, thereby obtaining the material composition of each fuel rod in the core.

[0055] Optionally, the server uses the material calculation subprogram part in the deterministic program comparable to the deviation of the Monte Carlo program to calculate the composition of the remaining material in each fuel rod in the core, thereby obtaining the material composition of each fuel rod in the core.

[0056] Step 206, based on the power calculation subprogram in the precise calculation program and the material composition of each fuel rod, the power calculation is performed to obtain the true power distribution of the core, and the detector reaction intensity of the core is obtained.

[0057] The power calculation subprogram is a program in the precise calculation program for calculating the true power distribution of the core. The true power distribution represents the true value of the power distribution of the core in the simulated running state.

[0058] Optionally, the server uses the power calculation subprogram part in the Monte Carlo program to calculate the true power distribution of the core in the simulated running state, thereby obtaining the true power distribution representing the true value of the power distribution of the core in the simulated running state, and obtaining the detector reaction intensity of the core.

[0059] Optionally, the server uses the power calculation subprogram part in the deterministic program comparable to the deviation of the Monte Carlo program to calculate the true power distribution of the core in the simulated running state, thereby obtaining the true power distribution representing the true value of the power distribution of the core in the simulated running state, and obtaining the detector reaction intensity of the core.

[0060] Step 208, based on the state parameters and the group constants, the power parameters of the core in the simulated running state are determined, and based on the detector reaction intensity and the power parameters, the flux map simulation measurement is performed to obtain the simulated power distribution of the core.

[0061] The power parameters mainly include three-dimensional power distribution of the core, power peak factor, axial power deviation, and other parameter factors. The simulated power distribution represents the measured value of the power distribution of the core in the simulated running state.

[0062] The flux map simulation is to give a measured value close to the true value by using polynomial fitting, spline fitting, weight coefficient and other methods, that is, to give a simulated power distribution measurement value close to the true power distribution measurement value of the reactor core.

[0063] The detector reaction intensity refers to the activity value of the detector in the reactor core, which is the reaction intensity generated by the activation of the detector under neutron irradiation in the reactor core. It is related to the type of detector, but when the specification of the detector is determined, it is only related to the neutron flux in the reactor core. The value of the reaction intensity of the detector is the value after the manufacturing deviation of the detector and the deviation of the detector current algorithm are superimposed, so that the deviation of the on-site operation factor relative to the theoretical simulation can be considered, so that the calculated result is closer to the true situation. The detector reaction intensity is obtained when the true power distribution of the reactor core is calculated using a precise calculation program such as Monte Carlo. The detector reaction intensity is also determined by superimposing a value representing uncertainty on the basis of the initial detector reaction intensity obtained. For example, the initial reaction intensity of the detector obtained is A, but due to the manufacturing error of the detector and the error of the detector current algorithm, a data X representing uncertainty needs to be superimposed to obtain the final reaction intensity of the detector A+X.

[0064] Optionally, the server calculates the three-dimensional power distribution, power peak factor, axial power deviation and other power parameters of the reactor core in the simulated operating state according to the state parameters of the reactor core in the simulated operating state and the group constants representing the grid cross-section values of the reactor core. The server then uses polynomial fitting, spline fitting, weight coefficient and other methods to perform flux map simulation measurement based on the obtained power parameters and the obtained detector reaction intensity, to give a simulated power distribution measurement value close to the true power distribution measurement value of the reactor core.

[0065] In step 210, the measurement uncertainty of the power distribution of the reactor core is determined based on the difference between the true power distribution and the simulated power distribution.

[0066] Among them, the server can determine the measurement uncertainty of the power distribution of the reactor core according to the difference between the true power distribution and the simulated power distribution of the reactor core in the simulated operating state. The difference mainly includes the difference in enthalpy rise factor, hot spot factor, component power distribution, axial power and other parameters in the true power distribution and the simulated power distribution.

[0067] In the analysis method of the core power distribution measurement uncertainty, the actual operation state of the core is determined according to the actual operation state of the core, and the state parameters of the core in the simulated operation state are determined, so that the state parameters of the core in the simulated operation state are more consistent with the actual situation of the core operation, and the problem of data loss can be solved by the simulated operation state and the state parameters of the simulated operation state in the case that a large amount of reactor core measurement test data is lacking; by using the material calculation subprogram to determine the material composition of the fuel rod based on the state parameters, and then using the power calculation subprogram to determine the real power distribution of the core based on the material composition of the fuel rod, the two calculation processes can be decoupled, the coupling relationship between the two steps is avoided to affect the calculation result and speed, the speed and accuracy of obtaining the real power distribution are improved, and the accuracy of the measurement uncertainty of the core power distribution determined by the simulated power distribution and the real power distribution of the core is improved.

[0068] In one embodiment, the group constants representing the grid cross-section values of the core are obtained, including:

[0069] The assembly burnup and the state parameters of the core in the simulated operation state are obtained.

[0070] Based on the assembly burnup and the state parameters, the assembly and reflector group constants of the core are determined.

[0071] The assembly burnup refers to the burnup of the fuel assembly. The fuel of the nuclear power plant is uranium, and the effective component is uranium-235, with a content of about 3%. The nuclear fuel is sintered into a cylindrical uranium dioxide ceramic core block, stacked in a cladding tube made of zirconium alloy, and assembled into a fuel assembly according to certain rules, which can be used for nuclear power plants. Burnup is a measure of the consumption of nuclear fuel in the reactor.

[0072] The assembly and reflector parameters mainly include core boron concentration, fuel temperature, moderator temperature and water density, control rod insertion state, fuel depth and other parameter factors.

[0073] The assembly burnup, assembly and reflector parameters are determined based on the assembly transport calculation program in the traditional two-step method "assembly transport calculation + core diffusion calculation" core nuclear design program. The assembly transport calculation program is based on two-dimensional assembly geometry, uses multi-group basic nuclear data to solve multi-group neutron transport equation, and obtains the distribution of neutron flux density in space and energy in the assembly, i.e. the assembly burnup and reflector parameters.

[0074] Optionally, the server uses the assembly transport program to calculate the burnup of the fuel assemblies of the reactor core during the simulated operating state, and the boron concentration, fuel temperature, moderator temperature and water density, control rod insertion state, fuel depth and other parameter factors of the core of the reactor. Then, according to the obtained assembly burnup and state parameters, the assembly and reflector group constants of the reactor core are calculated.

[0075] In this embodiment, by using the assembly transport program to calculate the assembly burnup and state parameters of the reactor core in the simulated operating state, the accuracy of the assembly burnup and state parameters can be improved, thereby improving the accuracy of the assembly and reflector group constants determined based on the assembly burnup and reflector parameters.

[0076] In one embodiment, based on the state parameters and the group constants, the power parameters of the core in the simulated operating state are determined, including:

[0077] Using the core nuclear design program, the power parameters of the core in the simulated operating state are determined based on the state parameters and the group constants.

[0078] Based on the power parameters, a theoretical library for reconstructing the power distribution of the core is constructed.

[0079] Based on the theoretical library, a flux map simulation measurement is performed to obtain the simulated power distribution of the core.

[0080] The core nuclear design program is based on the core geometry and equivalent few-group homogenized cross-section parameters to solve the few-group neutron diffusion equation to obtain the few-group neutron flux distribution, power distribution of the whole core and the reactivity of the core. When generating the theoretical library, the theoretical library used by the core nuclear design program is superimposed with random uncertain data values considering the deviation of nuclear data, core design parameters such as power, control rod position, core inlet temperature, core burnup, etc. Thus, the deviation of the field operation factors relative to the theoretical simulation can be comprehensively considered, so that the calculation result is more accurate.

[0081] The power parameters mainly include the three-dimensional power distribution of the core, the power peak factor, the axial power deviation and other parameter factors. In addition to the power parameters, the theoretical library also includes the cross-section of the detector and the theoretically calculated activity. The parameters contained in the theoretical library are all theoretical calculation parameters used in the flux map simulation measurement process.

[0082] Optionally, the server uses the core nuclear design program to calculate the power parameters of the reactor core in the simulated running state according to the state parameters of the reactor core in the simulated running state and the group constants of the reactor core. After obtaining the power parameters, the server generates a theoretical library using the power parameters, the cross sections of the detectors, and the theoretically calculated activity, and uses the data in the theoretical library as the theoretically calculated parameters of the flux map simulation measurement to perform the flux map simulation measurement, thereby obtaining the simulated power distribution of the reactor core in the simulated running state.

[0083] In this embodiment, the flux map simulation measurement using the theoretical library constructed from the power parameters can obtain an accurate simulated power distribution of the core, thereby improving the accuracy of the uncertainty of the power distribution measurement of the core.

[0084] In one embodiment, the material composition calculation is performed based on the material calculation subprogram in the precise calculation program and the state parameters, to obtain the material composition of each fuel rod in the core, including:

[0085] The burnup of each component of the core in the simulated running state is calculated based on the state parameters using the burnup calculation subprogram in the Monte Carlo program, to obtain the burnup of each component.

[0086] The material composition of the fuel rods in each component is determined based on the burnup of each component using the material calculation subprogram in the Monte Carlo program.

[0087] The Monte Carlo program, also known as the statistical simulation method, is a method of using random numbers or more commonly pseudo-random numbers to solve calculation problems. The working principle of the Monte Carlo program is continuous sampling and gradual approximation. For example, in a black background picture with multiple white patterns and each white pattern being an irregular pattern, the area cannot be calculated by the side length formula, etc. The Monte Carlo method is to randomly dot the picture, and then obtain the color of the pixel point, thereby obtaining the area of the white pattern = white point number / total point number*total picture area. The Monte Carlo method can improve the speed of obtaining the component burnup, the material composition of the fuel rods, and the real power distribution based on the decoupling idea.

[0088] Optionally, the server uses the subprogram about the burnup calculation part in the Monte Carlo program to perform burnup calculation on the state parameters of the core in the simulated running state, thereby obtaining the burnup of each component of the core in the simulated running state. After obtaining the burnup of each component of the core in the simulated state, the server uses the subprogram about the material calculation part in the Monte Carlo program to perform material composition calculation on the obtained burnup of each component, thereby obtaining the material composition of the fuel rods in each component of the core in the simulated running state.

[0089] In the embodiment, by using different subprogram parts in the Monte Carlo program to calculate the burnup of each assembly and the material composition of the fuel rod, the two steps of burnup calculation and material composition calculation can be decoupled, so that the speed of the assembly burnup and the material composition of the fuel rod can be improved, and the speed of obtaining the real power distribution of the reactor core can be improved.

[0090] In one embodiment, obtaining the detector reaction intensity of the reactor core comprises:

[0091] Obtaining the manufacturing error of the detector and the current algorithm error of the detector.

[0092] Based on the manufacturing error and the current algorithm error, superimposing the data representing the uncertainty on the detector reaction intensity to obtain the detector reaction intensity superimposed with the data representing the uncertainty.

[0093] The manufacturing error of the detector refers to the deviation of the actual geometric parameters of the processed detector from the design geometric parameters. In actual production, the process factors affecting the machining accuracy are complex. For some machining error problems, it is not enough to use single factor analysis method, but it is necessary to use probability and statistics method for comprehensive analysis to find out the causes of machining error and eliminate it. When the manufacturing error cannot be eliminated, the adverse effects caused by the manufacturing error can be eliminated by superimposing the uncertainty.

[0094] The superimposition of the data representing the uncertainty on the detector reaction intensity refers to superimposing a value on the initial detector reaction intensity obtained. For example, the initial detector reaction intensity obtained is A, but due to the detector manufacturing error and the detector current algorithm error, a data X representing the uncertainty needs to be superimposed, so as to obtain the final detector reaction intensity A+X. For another example, the initial detector reaction intensity obtained is A, but due to the detector manufacturing error and the detector current algorithm error, a data -X representing the uncertainty needs to be superimposed, so as to obtain the final detector reaction intensity A-X.

[0095] Optionally, the server first obtains the manufacturing error of the detector in the manufacturing process and the error of the current algorithm in the detector. The server superimposes the data representing the uncertainty on the initial detector reaction intensity obtained according to the manufacturing error of the detector and the current algorithm error, so as to obtain the final detector reaction intensity used for calculating the real power distribution of the reactor core in the simulated running state.

[0096] In the embodiment, by considering the manufacturing error of the detector and the current algorithm error of the detector when determining the detector reaction intensity, the finally determined detector reaction intensity can be more accurate, so as to improve the accuracy of the simulated power distribution based on the detector reaction intensity and the power parameter.

[0097] In one embodiment, the method for analyzing the uncertainty of the core power distribution measurement further comprises:

[0098] constructing a plurality of simulated operating states of the core and state parameters of the core in each simulated operating state.

[0099] obtaining a power deviation between the real power distribution and the simulated power distribution of the core in each simulated operating state.

[0100] statistically analyzing the power deviation in each simulated operating state to obtain the uncertainty of the power distribution measurement of the core.

[0101] The statistical analysis methods mainly include descriptive statistics, hypothesis testing, reliability analysis, contingency table analysis, correlation analysis, variance analysis, regression analysis, cluster analysis, and double 95 principle, etc. For example, according to the distribution of the deviation results in the plurality of simulated operating states, the final uncertainty of the power measurement is determined according to the double 95 principle. The double 95 principle means that 95% of the data points are enveloped and have a 95% confidence level.

[0102] Optionally, the server constructs a simulated operating state representing each operating state of the core according to a plurality of situations that may occur during the operation of the core. The server obtains the power deviation of the core in each simulated operating state according to the real power distribution and the simulated power distribution of the core in each simulated operating state. The server applies statistical analysis to the power deviation of the core in each simulated operating state using the double 95 principle, and finally obtains the uncertainty of the power distribution measurement of the core.

[0103] In this embodiment, by constructing a plurality of simulated operating states of the core, and then determining the uncertainty of the power distribution measurement of the core according to the statistical analysis results of the power deviation of the core in each simulated operating state, the occurrence of accidental phenomena caused by a single test can be avoided, so that the uncertainty of the core power measurement obtained finally is more accurate and the error is reduced.

[0104] The application also provides an application scenario of the method for analyzing the uncertainty of the core power distribution measurement. Specifically, the method for analyzing the uncertainty of the core power distribution measurement is applied as follows in the application scenario: for a certain reactor fuel management, confirming the loading mode of the reactor core and the type of the in-core probe. According to various possible physical operating states of the core, i.e. actual operating states, the assembly burnup and state parameter calculation of the core under different simulated operating states are carried out using “assembly transport calculation + core diffusion calculation”, mainly including the parameters such as core boron concentration, fuel temperature, moderator temperature and water density, control rod insertion state, fuel depth, etc. And according to the obtained assembly burnup and state parameters, the assembly used for core calculation and the reflector group constant are obtained. According to various actual operating states of the core, a plurality of simulated operating states of the core are constructed, and the burnup value BU(i,j), the fuel temperature Tf(i,j), the moderator temperature Tm(i,j), the moderator density Dm(i,j), the 135Xe concentration Xe(i,j), the 149Sm concentration Sm(i,j) and the insertion position CR(m) of each group of control rods at each grid of the core under each simulated operating state are specified, to simulate the core characteristics under different actual operating states. Wherein i is the grid number i = 1,...,I in the radial direction of the core, j is the grid number j = 1,...,J in the axial direction of the core, and m is the number of control rods of the core, m = 1,...,M. Using the core diffusion program in the core nuclear design program, the core calculation is carried out according to the state parameters of the core under each simulated state and the group constant of the core, to obtain the power parameters such as the three-dimensional power distribution of the core, the power peak factor and the axial power deviation of the core under each simulated state. According to the obtained power parameters of the core under each simulated state and the cross section of the probe, the theoretical library required to realize the in-core power distribution reconstruction is generated. The assembly burnup calculation is carried out on the various simulated operating states of the core using the material composition calculation subprogram in the Monte Carlo program, so as to obtain the material composition of each fuel rod in the burnup process. Based on the material composition of each fuel rod, the real power distribution of the core under each simulated state and the reaction intensity of the in-core probe are calculated using the power calculation subprogram in the Monte Carlo program. Using the flux map processing program, the generated theoretical library and the reaction intensity data of the probe are used to carry out flux map simulation measurement, to obtain a simulated power distribution close to the real power distribution. The deviations of each parameter in the simulated power distribution and the real power distribution under various simulated operating states are counted, and statistical methods are applied to finally obtain the uncertainty of the core power distribution measurement.

[0105] It should be understood that although the steps in the flowcharts involved in the embodiments described above are shown in sequence according to the arrows, the steps are not necessarily executed in the order indicated by the arrows. Unless otherwise specified herein, the execution of the steps is not strictly limited in sequence, and the steps can be executed in other sequences. Moreover, at least some of the steps in the flowcharts involved in the embodiments described above can include multiple steps or multiple stages, which are not necessarily executed at the same time, but can be executed at different times, and the execution sequence of the steps or stages is not necessarily sequential, but can be executed alternately or alternately with at least part of other steps or steps or stages in other steps.

[0106] Based on the same inventive concept, the embodiments of the present application also provide a reactor core power distribution measurement uncertainty analysis device for implementing the reactor core power distribution measurement uncertainty analysis method described above. The implementation scheme for solving the problem provided by the device is similar to the implementation scheme described in the above method, so the specific limitations in one or more reactor core power distribution measurement uncertainty analysis device embodiments provided below can refer to the limitations of the reactor core power distribution measurement uncertainty analysis method described above, which will not be repeated here.

[0107] In one embodiment, as shown in Figure 3 a reactor core power distribution measurement uncertainty analysis device is provided, comprising:

[0108] The state construction module 302 is configured to construct a simulated operating state based on an actual operating state of the reactor core, determine state parameters of the reactor core in the simulated operating state, and obtain group constants representing grid cross-section values of the reactor core.

[0109] The material composition calculation module 304 is configured to perform material composition calculation based on a material calculation subprogram in the precise calculation program and the state parameters, to obtain material compositions of the fuel rods in the reactor core.

[0110] The true power distribution determination module 306 is configured to perform power calculation based on a power calculation subprogram in the precise calculation program and the material compositions of the fuel rods, to obtain a true power distribution of the reactor core, and to obtain a detector reaction intensity of the reactor core.

[0111] The simulated power distribution determination module 308 is configured to determine power parameters of the reactor core in the simulated operating state based on the state parameters and the group constants, and to perform flux map simulation measurement based on the detector reaction intensity and the power parameters, to obtain a simulated power distribution of the reactor core.

[0112] ​​​​​​​The measurement uncertainty determination module 310 is configured to determine the measurement uncertainty of the power distribution of the core based on the difference between the true power distribution and the simulated power distribution.

[0113] In one embodiment, the state construction module comprises:

[0114] The parameter acquisition unit is configured to acquire the assembly burnup and the state parameter of the core in the simulated operating state.

[0115] The group constant determination unit is configured to determine the assembly and reflector group constants of the core based on the assembly burnup and the state parameter.

[0116] In one embodiment, the simulated power distribution determination module comprises:

[0117] The power parameter determination unit is configured to determine the power parameter of the core in the simulated operating state based on the state parameter and the group constant using the core nuclear design program.

[0118] The single theory library generation unit is configured to construct a theory library for reconstructing the power distribution of the core based on the power parameter.

[0119] The first simulated power distribution determination unit is configured to obtain the simulated power distribution of the core by performing flux map simulation measurement based on the theory library.

[0120] In one embodiment, the material composition calculation module comprises:

[0121] The burnup calculation unit is configured to calculate the burnup of each assembly of the core in the simulated operating state based on the state parameter using a burnup calculation subprogram in the Monte Carlo program, to obtain the burnup of each assembly.

[0122] The material composition calculation unit is configured to determine the material composition of the fuel rod in each assembly based on the burnup of each assembly using a material calculation subprogram in the Monte Carlo program.

[0123] In one embodiment, the reaction intensity acquisition unit comprises:

[0124] The error acquisition subunit is configured to acquire the manufacturing error of the detector and the current algorithm error of the detector.

[0125] The reaction intensity acquisition subunit is configured to obtain the reaction intensity of the detector superimposed with the data representing the uncertainty based on the manufacturing error and the current algorithm error of the detector.

[0126] In one embodiment, the analysis device for the measurement uncertainty of the power distribution of the core further comprises:

[0127] The state parameter determination unit is configured to construct a plurality of simulated operating states of the core and state parameters of the core in each simulated operating state.

[0128] The power deviation determination unit is configured to obtain a power deviation between the actual power distribution and the simulated power distribution of the core in each simulated operating state.

[0129] The measurement uncertainty determination unit is configured to statistically analyze the power deviation in each simulated operating state to obtain the measurement uncertainty of the power distribution of the core.

[0130] Each module in the analysis device for the measurement uncertainty of the power distribution of the core can be realized by software, hardware, or a combination thereof. Each module can be embedded in or independent of a processor in a computer device in a hardware form, or can be stored in a memory in a computer device in a software form, so as to be called and executed by a processor to perform the operation corresponding to each module.

[0131] In one embodiment, a computer device, which can be a server, has an internal structure as shown in Figure 4 The computer device includes a processor, a memory, an input / output interface (I / O), and a communication interface. The processor, the memory, and the input / output interface are connected through a system bus, and the communication interface is connected to the system bus through the input / output interface. The processor of the computer device is configured 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 operating system and the computer program in the non-volatile storage medium to run. The database of the computer device is configured to store an actual operating state of the core, simulated operating states of the core, state parameters of the core in the simulated operating states, group constants representing the grid cross-section values of the core, power parameters of the core in the simulated operating states, simulated power distributions of the core, an accurate calculation program, material compositions of each fuel rod, actual power distributions of the core, measurement uncertainties of the power distribution of the core, assembly burnups and reflector parameters of the core in the actual operating state, a theoretical library, a Monte Carlo program, detector reaction intensities of the core in the simulated operating states, manufacturing errors of the detectors, and current algorithm error data of the detectors. The input / output interface of the computer device is configured to exchange information between the processor and external devices. The communication interface of the computer device is configured to communicate with external terminals through a network connection. The computer program is executed by the processor to implement an analysis method for the measurement uncertainty of the power distribution of the core.

[0132] Those skilled in the art can understand that, Figure 4The structure shown in the figure is only a block diagram of part of the structure related to the scheme of the present application, and does not constitute a limitation on the computer device to which the scheme of the present application is applied. The specific computer device can include more or fewer components than those shown in the figure, or combine certain components, or have a different arrangement of components.

[0133] In one embodiment, a computer device is provided, comprising a memory and a processor, the memory storing a computer program, and the processor implementing the following steps when executing the computer program:

[0134] Based on the actual operating state of the core, a simulated operating state is constructed, the state parameters of the core in the simulated operating state are determined, and the group constants representing the grid cross-section values of the core are obtained; based on the material calculation subprogram in the precise calculation program and the state parameters, material composition calculation is performed to obtain the material composition of each fuel rod in the core; based on the power calculation subprogram in the precise calculation program and the material composition of each fuel rod, power calculation is performed to obtain the true power distribution of the core and obtain the detector reaction intensity of the core; based on the state parameters and the group constants, the power parameters of the core in the simulated operating state are determined, and based on the detector reaction intensity and the power parameters, flux map simulation measurement is performed to obtain the simulated power distribution of the core; based on the difference between the true power distribution and the simulated power distribution, the measurement uncertainty of the power distribution of the core is determined.

[0135] In one embodiment, the processor further implements the following steps when executing the computer program:

[0136] The assembly burnup and the state parameters of the core in the simulated operating state are obtained; based on the assembly burnup and the state parameters, the assembly and reflector group constants of the core are determined.

[0137] In one embodiment, the processor further implements the following steps when executing the computer program:

[0138] Using the core nuclear design program, the power parameters of the core in the simulated operating state are determined based on the state parameters and the group constants; based on the power parameters, a theoretical library for reconstructing the power distribution of the core is constructed; based on the theoretical library, flux map simulation measurement is performed to obtain the simulated power distribution of the core.

[0139] In one embodiment, the processor further implements the following steps when executing the computer program:

[0140] Using the burnup calculation subprogram in the Monte Carlo program, the burnup of each assembly of the core in the simulated operating state is calculated based on the state parameters to obtain the burnup of each assembly; using the material calculation subprogram in the Monte Carlo program, the material composition of the fuel rods in each assembly is determined based on the burnup of each assembly.

[0141] In one embodiment, the processor, when executing the computer program, also implements the following steps:

[0142] Obtaining manufacturing errors of the detector and current algorithm errors of the detector; based on the manufacturing errors and the current algorithm errors, superimposing data of the characterization uncertainty on the reaction intensity of the detector to obtain the reaction intensity of the detector superimposed with the characterization uncertainty.

[0143] In one embodiment, the processor, when executing the computer program, also implements the following steps:

[0144] Constructing a plurality of simulated operating states of the core and state parameters of the core in each simulated operating state; obtaining power deviations between the real power distribution and the simulated power distribution of the core in each simulated operating state; and statistically analyzing the power deviations in each simulated operating state to obtain the measurement uncertainty of the power distribution of the core.

[0145] In one embodiment, a computer readable storage medium is provided, and the computer readable storage medium stores a computer program, and the computer program, when executed by a processor, implements the following steps:

[0146] Based on the actual operating state of the core, a simulated operating state is constructed, state parameters of the core in the simulated operating state are determined, and group constants representing the grid cross-section values of the core are obtained; based on the material calculation subprogram in the precise calculation program and the state parameters, material composition calculation is performed to obtain the material composition of each fuel rod in the core; based on the power calculation subprogram in the precise calculation program and the material composition of each fuel rod, power calculation is performed to obtain the real power distribution of the core and obtain the detector reaction intensity of the core; based on the state parameters and the group constants, the power parameters of the core in the simulated operating state are determined, and based on the detector reaction intensity and the power parameters, flux map simulation measurement is performed to obtain the simulated power distribution of the core; and based on the difference between the real power distribution and the simulated power distribution, the measurement uncertainty of the power distribution of the core is determined.

[0147] In one embodiment, the processor, when executing the computer program, also implements the following steps:

[0148] Obtaining assembly burnups and state parameters of the core in the simulated operating state; and based on the assembly burnups and the state parameters, determining the assembly and the reflector group constants of the core.

[0149] In one embodiment, the processor, when executing the computer program, also implements the following steps:

[0150] Using the core nuclear design program, based on the state parameters and the group constants, determining the power parameters of the core in the simulated operating state; based on the power parameters, constructing a theoretical library for realizing power distribution reconstruction of the core; and based on the theoretical library, performing flux map simulation measurement to obtain the simulated power distribution of the core.

[0151] In one embodiment, the processor, when executing the computer program, also implements the following steps:

[0152] The burnup of each assembly of the core in the simulated operating state is calculated based on the state parameters using a burnup calculation subprogram in the Monte Carlo program, and the burnup of each assembly is obtained; the material composition of the fuel rods in each assembly is determined based on the burnup of each assembly using a material calculation subprogram in the Monte Carlo program.

[0153] In one embodiment, the processor, when executing the computer program, also implements the following steps:

[0154] The manufacturing error of the detector and the current algorithm error of the detector are obtained; the detector reaction intensity of the data superimposed with the characterization uncertainty is obtained based on the manufacturing error and the current algorithm error.

[0155] In one embodiment, the processor, when executing the computer program, also implements the following steps:

[0156] A plurality of simulated operating states of the core and the state parameters of the core in each simulated operating state are constructed; the power deviation between the true power distribution and the simulated power distribution of the core in each simulated operating state is obtained; the measurement uncertainty of the power distribution of the core is obtained by statistically analyzing the power deviation in each simulated operating state.

[0157] In one embodiment, a computer program product is provided, comprising a computer program which, when executed by a processor, implements the following steps:

[0158] The simulated operating state is constructed based on the actual operating state of the core, the state parameters of the core in the simulated operating state are determined, and the group constant representing the grid cross-section value of the core is obtained; the material composition of each fuel rod in the core is calculated based on the material calculation subprogram in the precise calculation program and the state parameters, and the true power distribution of the core is obtained based on the power calculation subprogram in the precise calculation program and the material composition of each fuel rod; the power parameters of the core in the simulated operating state are determined based on the state parameters and the group constant, and the flux map simulation measurement is performed based on the detector reaction intensity and the power parameters, so as to obtain the simulated power distribution of the core; the measurement uncertainty of the power distribution of the core is determined based on the difference between the true power distribution and the simulated power distribution.

[0159] In one embodiment, the processor, when executing the computer program, also implements the following steps:

[0160] Obtain assembly burnup and state parameters of the core in the simulated operation state; determine assembly and reflector group constants of the core based on the assembly burnup and state parameters.

[0161] In one embodiment, the processor, when executing the computer program, also implements the following steps:

[0162] Determine power parameters of the core in the simulated operation state based on the state parameters and the group constants using a core nuclear design program; construct a theoretical library for realizing power distribution reconstruction of the core based on the power parameters; and perform flux map simulation measurement based on the theoretical library to obtain a simulated power distribution of the core.

[0163] In one embodiment, the processor, when executing the computer program, also implements the following steps:

[0164] Calculate the burnup of each assembly of the core in the simulated operation state based on the state parameters using a burnup calculation subprogram in the Monte Carlo program to obtain the burnup of each assembly; and determine the material composition of the fuel rods in each assembly based on the burnup of each assembly using a material calculation subprogram in the Monte Carlo program.

[0165] In one embodiment, the processor, when executing the computer program, also implements the following steps:

[0166] Obtain manufacturing errors of the detectors and current algorithm errors of the detectors; obtain the detector reaction intensity of the data superimposed with the characterization uncertainty based on the manufacturing errors and the current algorithm errors of the detectors.

[0167] In one embodiment, the processor, when executing the computer program, also implements the following steps:

[0168] Construct a plurality of simulated operation states of the core and state parameters of the core in each simulated operation state; obtain power deviations between true power distributions and simulated power distributions of the core in each simulated operation state; and statistically analyze the power deviations in each simulated operation state to obtain measurement uncertainty of the power distribution of the core.

[0169] It should be noted that the user information (including but not limited to user equipment information, user personal information, etc.) and data (including but not limited to data for analysis, stored data, displayed data, etc.) involved in the present application are all information and data authorized by the user or authorized by all parties, and the collection, use and processing of the relevant data need to comply with relevant laws, regulations and standards of relevant countries and regions.

[0170] Those skilled in the art can understand that all or part of the processes in the above-mentioned embodiment methods can be completed by instructing the relevant hardware through a computer program. The computer program can be stored in a non-volatile computer readable storage medium, and when the computer program is executed, the processes of the above-mentioned embodiments of the methods can be included. Any reference to memory, database or other medium used in the embodiments provided in the present application can include at least one of non-volatile and volatile memory. Non-volatile memory can include read-only memory (Read-Only Memory, ROM), magnetic tape, floppy disk, flash memory, optical storage, high-density embedded non-volatile memory, resistive memory (ReRAM), magnetoresistive random access memory (Magnetoresistive Random Access Memory, MRAM), ferroelectric memory (Ferroelectric Random Access Memory, FRAM), phase change memory (Phase Change Memory, PCM), graphene memory, etc. Volatile memory can include random access memory (Random Access Memory, RAM) or external cache memory, etc. As an illustration but not limitation, RAM can be in various forms, such as static random access memory (Static Random Access Memory, SRAM) or dynamic random access memory (Dynamic Random Access Memory, DRAM), etc. The database involved in the embodiments provided in the present application can include at least one of a relational database and a non-relational database. The non-relational database can include a distributed database based on a block chain, etc., without being limited thereto. The processor involved in the embodiments provided in the present application can be a general-purpose processor, a central processing unit, a graphics processing unit, a digital signal processor, a programmable logic device, a data processing logic device based on quantum computing, etc., without being limited thereto.

[0171] Any combination of the technical features of the above embodiments can be made. In order to make the description simple, all possible combinations of the technical features in the above embodiments are not described, however, as long as the combination of the technical features does not exist contradictory, it should be considered as the scope of the present application.

[0172] The above embodiments only express several implementation manners of the present application, and the description is more specific and detailed, but it should not be understood as a limitation on the scope of the patent of the present application. It should be pointed out that for ordinary skilled in the art, without departing from the concept of the present application, a number of modifications and improvements can be made, which are within the scope of protection of the present application. Therefore, the protection scope of the present application should be subject to the appended claims.

Claims

1. A method for analyzing the measurement uncertainty of reactor core power distribution, characterized in that, The method includes: Based on the actual operating state of the reactor core, a simulated operating state is constructed to determine the state parameters of the reactor core under the simulated operating state, and the group constants characterizing the grid cross-section values ​​of the reactor core are obtained. The state parameters include the burnup value, fuel temperature, moderator temperature, moderator density, xenon concentration, samarium concentration, and the insertion position of each set of control rods at each grid of the reactor core. The material composition is calculated based on the material calculation subroutine in the precise calculation program and the state parameters to obtain the material composition of each fuel rod in the reactor core; the precise calculation program includes a Monte Carlo program or a deterministic program with a deviation comparable to that of the Monte Carlo program; Based on the power calculation subroutine in the precise calculation program and the material composition of each fuel rod, the power calculation is performed to obtain the true power distribution of the reactor core and the detector response intensity of the reactor core is obtained. Based on the state parameters and the group constant, the power parameters of the reactor core under the simulated operating state are determined, and flux map simulation measurement is performed based on the detector response intensity and the power parameters to obtain the simulated power distribution of the reactor core; the power parameters include the three-dimensional power distribution of the reactor core, the power peak factor, and the axial power deviation. The measurement uncertainty of the power distribution of the reactor core is determined based on the difference between the actual power distribution and the simulated power distribution.

2. The method according to claim 1, characterized in that, The process of obtaining the group constants characterizing the grid cross-section values ​​of the core includes: Obtain component burnup and status parameters of the reactor core under simulated operating conditions; Based on the component burnup and the state parameters, the component and reflector group constants of the reactor core are determined.

3. The method according to claim 1, characterized in that, Determining the power parameters of the reactor core under the simulated operating state based on the state parameters and the group constant includes: Using a core design program, the power parameters of the core under the simulated operating conditions are determined based on the state parameters and the group constant. After determining the power parameters of the reactor core under simulated operating conditions, the process includes: Based on the power parameters, a theoretical library for reconfiguring the power distribution of the reactor core is constructed. Flux diagram simulation measurements were performed based on the aforementioned theoretical library to obtain the simulated power distribution of the reactor core.

4. The method according to claim 1, characterized in that, The material composition calculation, based on the material calculation subroutine in the precise calculation program and the state parameters, yields the material composition of each fuel rod in the reactor core, including: Using the burnup calculation subroutine in the Monte Carlo program, the burnup of each component of the reactor core in the simulated operating state is calculated based on the state parameters to obtain the burnup of each component. Using the material calculation subroutine in the Monte Carlo program, the material composition of the fuel rods in each component is determined based on the fuel consumption of each component.

5. The method according to claim 1, characterized in that, The detection response intensity of the reactor core is obtained by: The manufacturing error of the detector and the current algorithm error of the detector are obtained; Based on the manufacturing error and the current algorithm error, the detector response intensity is superimposed with data representing uncertainty to obtain the detector response intensity superimposed with the data representing uncertainty.

6. The method according to claim 1, characterized in that, The method further includes: Construct multiple simulated operating states of the reactor core and state parameters of the reactor core in each of the simulated operating states; Obtain the power deviation between the actual power distribution and the simulated power distribution of the reactor core under each simulated operating state; Statistical analysis is performed on the power deviation under each of the simulated operating conditions to obtain the measurement uncertainty of the power distribution of the reactor core.

7. An analytical apparatus for measuring uncertainty in reactor core power distribution, characterized in that, The device includes: The state construction module is used to construct a simulated operating state based on the actual operating state of the reactor core, determine the state parameters of the reactor core under the simulated operating state, and obtain the group constants characterizing the grid cross-sectional values ​​of the reactor core; the state parameters include the burnup value, fuel temperature, moderator temperature, moderator density, xenon concentration, samarium concentration, and the insertion position of each set of control rods at each grid of the reactor core. The material composition calculation module is used to calculate the material composition based on the material calculation subroutine in the accurate calculation program and the state parameters, so as to obtain the material composition of each fuel rod in the reactor core; the accurate calculation program includes a Monte Carlo program or a deterministic program with a deviation comparable to that of the Monte Carlo program; The true power distribution determination module is used to perform power calculations based on the power calculation subroutine in the precise calculation program and the material composition of each fuel rod, to obtain the true power distribution of the reactor core and acquire the detector response intensity of the reactor core. The simulated power distribution determination module is used to determine the power parameters of the reactor core under the simulated operating state based on the state parameters and the group constant, and to perform flux map simulation measurement based on the detector response intensity and the power parameters to obtain the simulated power distribution of the reactor core; the power parameters include the three-dimensional power distribution of the reactor core, the power peak factor, and the axial power deviation; The measurement uncertainty determination module is used to determine the measurement uncertainty of the power distribution of the reactor core based on the difference between the actual power distribution and the simulated power distribution.

8. A computer device comprising a memory and a processor, wherein the memory stores a computer program, characterized in that, When the processor executes the computer program, it implements the steps of the method according to any one of claims 1 to 6.

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

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

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