Analysis method and apparatus for measurement uncertainty of power distribution of reactor core, and device

Abstract

An analysis method and apparatus for measurement uncertainty of power distribution of a reactor core, a device, a storage medium, and a product. The analysis method for measurement uncertainty of power distribution of a reactor core comprises: constructing a simulated operation state on the basis of an actual operation state of a reactor core, determining state parameters of the reactor core in the simulated operation state, and acquiring a group constant of the reactor core (S202); performing calculation on the basis of a material calculation subprogram and the state parameters to obtain material components of each fuel rod in the reactor core (S204); performing calculation on the basis of a power calculation subprogram and the material components of each fuel rod to obtain real power distribution of the reactor core, and acquiring detector reaction intensity of the reactor core (S206); on the basis of the state parameters and the group constant, determining power parameters of the reactor core in the simulated operation state, and performing flux graph simulation on the basis of the power parameters and the detector reaction intensity to obtain simulated power distribution of the reactor core (S208); and determining the measurement uncertainty of power distribution of the reactor core on the basis of a difference between the real power distribution and the simulated power distribution (S210).

Description

Analysis method, device and equipment for uncertainty analysis of core power distribution measurement

[0001] Related applications

[0002] This application claims priority to Chinese patent application number 2023107246764, filed on June 19, 2023, entitled “Analysis method, device and equipment for uncertainty in core power distribution measurement”, the entire text of which is hereby incorporated by reference. Technical Field

[0003] The present application relates to the field of reactor core measurement and protection technology, and in particular to a method, device, computer equipment and storage medium for analyzing uncertainty in core power distribution measurement. Background Art

[0004] The in-core neutron flux measurement system is generally used to measure the core power distribution or generate trigger signals for the core protection system based on the measurement results. The measurement results are reconstructed based on the actual measurement values ​​of some channels combined with the theoretical values.

[0005] Traditional technology mainly uses core calculation programs to perform sensitivity analysis, confirm the disturbance of each input uncertainty component on the calculation result, and give the uncertainty of the final measurement system through statistical methods. However, the power parameters used in the calculation process of traditional technology are all hypothetical theoretical parameters, which will cause the true power parameters of the core considered in the calculation to differ greatly from the actual parameters of the core, ultimately resulting in unreasonable measurement uncertainty.

[0006] Summary of the Invention

[0007] According to various embodiments disclosed in the present application, a method, apparatus, computer device, and computer-readable storage medium are provided for analyzing uncertainty in core power distribution measurement.

[0008] In a first aspect, the present application provides a method for analyzing uncertainty in core power distribution measurement, comprising:

[0009] constructing a simulated operating state based on the actual operating state of the core, determining state parameters of the core under the simulated operating state, and obtaining a group constant representing a grid cross-section value of the core;

[0010] performing material composition calculation 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 core;

[0011] Performing power calculation based on the power calculation subroutine in the precise calculation program and the material composition of each of the fuel rods to obtain the true power distribution of the core and the detector reaction intensity of the core;

[0012] determining a power parameter of the core in the simulated operating state based on the state parameter and the group constant, and performing a flux diagram simulation measurement based on the detector reaction intensity and the power parameter to obtain a simulated power distribution of the core; and

[0013] A measurement uncertainty of the power distribution of the core is determined based on a difference between the actual power distribution and the simulated power distribution.

[0014] In a second aspect, the present application provides a device for analyzing uncertainty in core power distribution measurement, comprising:

[0015] a state construction module, configured to construct a simulated operating state based on the actual operating state of the core, determine state parameters of the core under the simulated operating state, and obtain a group constant representing a grid cross-section value of the core;

[0016] a material composition calculation module, configured to calculate the material composition based on the material calculation subroutine in the precise calculation program and the state parameters, and obtain the material composition of each fuel rod in the core;

[0017] a real power distribution determination module, configured to perform power calculation based on the power calculation subroutine in the precise calculation program and the material composition of each of the fuel rods, thereby obtaining the real power distribution of the core and acquiring the detector reaction intensity of the core;

[0018] a simulated power distribution determination module, configured to determine a power parameter of the core in the simulated operating state based on the state parameter and the group constant, and perform a flux diagram simulation measurement based on the detector reaction intensity and the power parameter to obtain a simulated power distribution of the core; and

[0019] A measurement uncertainty determination module is used to determine the measurement uncertainty of the power distribution of the core based on the difference between the real power distribution and the simulated power distribution.

[0020] In a third aspect, the present application provides a computer device comprising a memory and one or more processors, wherein the memory stores computer-readable instructions, and the computer-readable instructions implement the steps of the above method when executed by the processor.

[0021] In a fourth aspect, the present application provides one or more non-volatile storage media storing computer-readable instructions, which implement the steps of the above method when executed by one or more processors.

[0022] In a fifth aspect, the present application provides a computer-readable instruction product, comprising computer-readable instructions, which implement the steps of the above method when executed by a processor. BRIEF DESCRIPTION OF THE DRAWINGS

[0023] In order to more clearly illustrate the embodiments of the present application or the technical solutions in the conventional technology, the following briefly introduces the drawings required for use in the embodiments or the conventional technology descriptions. Obviously, the drawings described below are merely embodiments of the present application. For ordinary technicians in this field, other drawings can be obtained based on the disclosed drawings without any creative work.

[0024] FIG1 is a diagram illustrating an application environment of a method for analyzing uncertainty in core power distribution measurement according to one or more embodiments.

[0025] FIG2 is a flow chart of a method for analyzing uncertainty in core power distribution measurement according to one or more embodiments.

[0026] FIG3 is a structural block diagram of a device for analyzing uncertainty in core power distribution measurement according to one or more embodiments.

[0027] FIG4 is a diagram of a computer device according to one or more embodiments. DETAILED DESCRIPTION

[0028] The following will be combined with the drawings in the embodiments of this application to clearly and completely describe the technical solutions in the embodiments of this application. Obviously, the embodiments described are only part of the embodiments of this application, not all of the embodiments. Based on the embodiments in this application, all other embodiments obtained by ordinary technicians in this field without making creative efforts are within the scope of protection of this application.

[0029] The method for analyzing the uncertainty of core power distribution measurement provided in an embodiment of the present application can be applied in the application environment shown in Figure 1. Terminal 102 communicates with server 104 via a network. A data storage system can store data that server 104 needs to process. The data storage system can be integrated with server 104, or placed on a cloud or other network server. Server 104 constructs a simulated operating state of the core based on the actual operating state of the core during actual operation, and determines the state parameters of the core under the simulated operating state based on the actual operating state of the core. Server 104 also obtains group constants that represent the grid cross-section values ​​in the core. Server 104 uses the material calculation subroutine in the precise calculation program to calculate the material composition of the fuel rods based on the state parameters of the core under the simulated operating state, thereby obtaining the material composition of each fuel rod in the core. Server 104 uses the power calculation subroutine in the precise calculation program to perform power calculation based on the obtained material composition of each fuel rod, thereby obtaining the actual power distribution of the core under the simulated operating state and the detector reaction strength of the core. Server 104 calculates the power parameters of the core under the simulated operating state based on the state parameters of the simulated operating state and the core's group constant. It then uses the power parameters and detector reaction intensity to simulate flux map measurements, thereby obtaining a simulated power distribution of the core under the simulated operating state. Server 104 obtains the measurement uncertainty of the core power distribution based on the difference between the actual power distribution of the core under the simulated operating state and the simulated power distribution. Terminal 102 may be, but is not limited to, various personal computers, laptops, tablet computers, and the like. Server 104 may be implemented as a standalone server or a server cluster consisting of multiple servers.

[0030] In one embodiment, as shown in FIG2 , a method for analyzing the uncertainty of core power distribution measurement is provided. The method is described by applying it to the server in FIG1 as an example, and includes the following steps:

[0031] Step 202 : constructing a simulated operating state based on the actual operating state of the core, determining the state parameters of the core in the simulated operating state, and obtaining a group constant representing a grid cross-section value of the core.

[0032] The state parameters include the burnup value BU(i,j), fuel temperature Tf(i,j), moderator temperature Tm(i,j), moderator density Dm(i,j), 135Xe concentration Xe(i,j), 149Sm(i,j), and the insertion position CR(m) of each set of control rods at each grid point in the reactor core, where i is the grid number in the radial direction of the core (i=1,...,I), j is the grid number in the axial direction of the core (j=1,...,J), and m is the number of control rods in the core (m=1,...,M).

[0033] The actual operating state of the core refers to the various possible physical states of the core in reality. The simulated operating state of the core is constructed, and its state parameters must conform to actual conditions. When constructing the simulated operating state of the reactor core, it is based on component burnup and reflector parameters under the actual operating state of the reactor core. Reflector parameters primarily include core boron concentration, fuel temperature, moderator temperature and water density, control rod insertion state, and fuel depth. For example, in the simulated state, the boron concentration at all locations in the core should be approximately equal, and the water density should not exhibit significant locational gradients. The advantage of constructing a simulated operating state is that, in the absence of extensive reactor core measurement test data, theoretical calculations can be used to confirm the measurement uncertainty of the core measurement system in aspects such as power distribution.

[0034] Before conducting uncertainty analysis of the core power distribution measurement, it is also necessary to determine the core loading method and the type of in-core detector. Since measurement uncertainty is related to core loading, once the core loading method is determined, the basis for all analyses is determined and will not change subsequently. All analyses are conducted based on the loading method, that is, the analysis method for determining the uncertainty of the core power distribution measurement is based on the core loading method. Among them, core loading methods mainly include OUT-IN (output-input) loading and low-leakage loading. Detector types mainly include movable micro-fission chambers, fixed self-powered detectors, pneumatic balls, and other types.

[0035] Optionally, the server constructs a simulated core operating state based on component burnup and reflector parameters during the core's actual operating state. It then uses a core diffusion program to determine the burnup, fuel temperature, moderator temperature, moderator density, xenon-135 concentration, samarium-149 concentration, and the insertion position of each control rod group at each grid point in the simulated operating state. The server also obtains group constants representing the grid cross-sectional values ​​of the core.

[0036] Step 204 : performing material composition calculation 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 core.

[0037] Among them, precise calculation programs mainly include Monte Carlo programs and deterministic programs with deviations comparable to those of Monte Carlo programs.

[0038] The material calculation subroutine, part of the precision calculation program, calculates the composition or ratio of each material remaining in the fuel rod. During the combustion process, the material in the fuel rod splits, for example, if one material splits into two, the amount of that material changes, necessitating the calculation of the composition of each material. Material composition refers to the composition of each material remaining in the fuel rod after combustion, and can also be understood as the ratio of each material to the remaining material.

[0039] Optionally, the server uses a material calculation subroutine in a 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.

[0040] Optionally, the server calculates the composition of the remaining material in each fuel rod in the core using a material calculation subroutine portion of a deterministic program having a deviation comparable to that of a Monte Carlo program, thereby obtaining the material composition of each fuel rod in the core.

[0041] Step 206 , performing power calculation based on the power calculation subroutine in the precise calculation program and the material composition of each fuel rod, obtaining the real power distribution of the core and acquiring the detector reaction intensity of the core.

[0042] The power calculation subroutine is a program in the precise calculation program used to calculate the value of the real power distribution of the core. The real power distribution represents the true value of the power distribution of the core under the simulated operation state.

[0043] Optionally, the server uses the power calculation subroutine part in the Monte Carlo program to calculate the real power distribution of the reactor core under the simulated operating state, thereby obtaining the real power distribution that characterizes the true value of the power distribution of the core under the simulated operating state, and obtains the detector reaction intensity of the core.

[0044] Optionally, the server uses the power calculation subroutine part in the deterministic program that is comparable to the Monte Carlo program deviation to calculate the real power distribution of the core under the simulated operating state, thereby obtaining the real power distribution that characterizes the true value of the power distribution of the core under the simulated operating state, and obtains the detector reaction intensity of the core.

[0045] Step 208 : Based on the state parameters and group constants, determine the power parameters of the core in the simulated operating state, and perform flux diagram simulation measurement based on the detector reaction intensity and power parameters to obtain the simulated power distribution of the core.

[0046] The power parameters mainly include the 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 under simulated operating conditions.

[0047] The flux diagram simulation uses polynomial fitting, spline fitting, weight coefficient and other methods to give a measurement value that is closer to the true value, that is, to give a simulated power distribution measurement value that is closer to the actual power distribution measurement value of the core.

[0048] Detector reactivity refers to the activity of in-core detectors. It is the intensity of the detector's reaction to neutron irradiation and activation within the core. It is dependent on the detector type, but, given the given detector specifications, is solely related to the core neutron flux. The detector reactivity is calculated by factoring in detector manufacturing variations and variations in the detector current algorithm. This allows for deviations from theoretical simulations due to field operational factors, resulting in a more realistic calculated result. The detector reactivity is obtained by calculating the true power distribution in the core using precise calculation programs such as Monte Carlo. The detector reactivity is determined by adding a value representing uncertainty to the initial detector reactivity. For example, the initial detector reactivity is A. However, due to variations in detector manufacturing and the detector current algorithm, a value representing uncertainty, X, is added to determine the final detector reactivity, A+X.

[0049] Optionally, the server calculates power parameters such as the three-dimensional core power distribution, power crest factor, and axial power deviation during the simulated operation state based on the core's state parameters during the simulated operation state and the group constant representing the core's grid cross-section values. Based on the obtained power parameters and the acquired detector reaction intensity, the server then simulates the flux map using methods such as polynomial fitting, spline fitting, and weight coefficients, providing a simulated power distribution measurement value that is relatively close to the actual power distribution measurement value of the core.

[0050] In step 210 , the measurement uncertainty of the power distribution of the core is determined based on the difference between the actual power distribution and the simulated power distribution.

[0051] The server determines the measurement uncertainty of the core power distribution based on the difference between the actual power distribution and the simulated power distribution under simulated operating conditions. This difference primarily includes differences in parameters such as the enthalpy rise factor, hot spot factor, component power distribution, and axial power between the actual and simulated power distributions.

[0052] In the above-mentioned analysis method of the uncertainty in the measurement of the core power distribution, by determining the core in the simulated operating state according to the actual operating state of the core, and determining the state parameters of the core in the simulated operating state, the state parameters of the constructed core in the simulated operating state can be made more consistent with the actual situation of the core operation. At the same time, in the absence of a large amount of reactor core measurement test data, the problem of missing data can be solved by the constructed simulated operating state and the state parameters of the simulated operating state; by first using the material calculation subroutine to determine the material composition of the fuel rod based on the state parameters, and then using the power calculation subroutine 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 to avoid the coupling relationship between the two steps affecting the calculation results and speed, thereby improving the speed and accuracy of obtaining the real power distribution, thereby improving the accuracy of the measurement uncertainty of the core power distribution determined by the simulated power distribution and the real power distribution of the power core.

[0053] In one embodiment, obtaining a group constant representing a grid cross-section value of the core includes obtaining component burnup and state parameters of the core under simulated operating conditions, and determining component and reflector group constants of the core based on the component burnup and state parameters.

[0054] Assembly burnup refers to the burnup of the fuel assembly. Nuclear power plants use uranium, the active ingredient of which is approximately 3% uranium-235. The nuclear fuel is sintered into cylindrical uranium dioxide ceramic pellets, which are then stacked in zirconium alloy cladding tubes to form slender fuel rods. These fuel rods are then assembled into fuel assemblies according to specific rules for use in nuclear power plants. Burnup is a measure of the nuclear fuel consumption in a reactor.

[0055] The component and reflector parameters mainly include core boron concentration, fuel temperature, moderator temperature and water density, control rod insertion status, fuel depth and other parameter factors.

[0056] Module burnup, module, and reflector parameters are determined using the module transport calculation program within the traditional two-step "module transport calculation + core diffusion calculation" core design process. Based on two-dimensional module geometry and utilizing multi-group fundamental nuclear data, the module transport calculation program solves multi-group neutron transport equations to determine the spatial and energy distribution of the neutron flux density within the module, thereby obtaining the module burnup and reflector parameters.

[0057] Optionally, the server uses an assembly transport program to calculate the fuel assembly burnup during the simulated reactor core operation, as well as parameters such as the reactor core boron concentration, fuel temperature, moderator temperature and water density, control rod insertion state, and fuel depth. Based on the obtained assembly burnup and state parameters, the server then calculates the reactor core assembly and reflector group constants.

[0058] In this embodiment, by using a component transport program to calculate the component fuel consumption and state parameters of the reactor core in a simulated operating state, the accuracy of the component fuel consumption and state parameters can be improved, thereby improving the accuracy of the component and reflector group constants determined based on the component fuel consumption and reflector parameters.

[0059] In one embodiment, determining power parameters of a reactor core in a simulated operating state based on state parameters and group constants includes: using a core design program to determine the power parameters of the reactor core in the simulated operating state based on the state parameters and group constants; constructing a theoretical library for reconstructing the power distribution of the reactor core based on the power parameters; and performing flux diagram simulation measurements based on the theoretical library to obtain a simulated power distribution of the reactor core.

[0060] The core design program solves the few-swarm neutron diffusion equation based on core geometry and equivalent few-swarm homogenized cross-sectional parameters to derive the few-swarm neutron flux distribution, power distribution, and core reactivity for the entire core. When generating the theoretical library, factors such as deviations in nuclear data and core design parameters such as power, control rod positions, core inlet temperature, and core burnup are taken into account. Random uncertainty values ​​are superimposed on the theoretical library used by the core design program. This allows for comprehensive consideration of deviations from theoretical simulations due to field operational factors, resulting in more accurate calculation results.

[0061] Power parameters primarily include parameters such as the core's three-dimensional power distribution, power crest factor, and axial power deviation. In addition to power parameters, the theoretical library also includes detector cross-sections and theoretically calculated activity. The parameters in the theoretical library are all theoretically calculated parameters used in flux map simulation measurements.

[0062] Optionally, the server uses a core design program to calculate the power parameters of the reactor core under the simulated operating state based on the state parameters of the reactor core under the simulated operating state and the group constant of the reactor core. After obtaining the power parameters, the server generates a theoretical library using the power parameters, the detector cross section, and the theoretically calculated activity. The server then uses the data in the theoretical library as theoretical calculation parameters for the flux map simulation measurement, performs the flux map simulation measurement, and thereby obtains a simulated power distribution of the reactor core under the simulated operating state.

[0063] In this embodiment, by using a theoretical library constructed from power parameters to perform flux diagram simulation measurement, an accurate simulated power distribution of the core can be obtained, thereby improving the accuracy of the uncertainty of the power distribution measurement of the core.

[0064] In one embodiment, after determining the power parameters of the core in the simulated operating state, the method includes: obtaining a cross section of a detector, and generating a theoretical library for reconstructing the power distribution of the core based on the power parameters and the cross section of the detector.

[0065] Among them, when generating the theoretical library for realizing the power distribution reconstruction of the core, the theoretically calculated activity will also be used, that is, the reaction intensity generated by the detector being activated by neutron irradiation in the core.

[0066] Optionally, the server obtains a detector cross-section for detecting the core and the intensity of a reaction generated by neutron irradiation activation within the core. Based on the detector interface, the intensity of the reaction, and the power parameters, the server generates a theoretical library for reconstructing the power distribution of the core.

[0067] In this embodiment, a theoretical library is generated by utilizing power parameters, detector cross-section, and theoretically calculated activity, so that when the theoretical library is used to perform flux diagram simulation measurements, an accurate simulated power distribution of the core can be obtained, thereby improving the accuracy of the uncertainty measurement of the core power distribution.

[0068] In one embodiment, generating a theoretical library for reconstructing the power distribution of a reactor core includes determining uncertainty data values ​​to be added to the theoretical library based on deviations in nuclear data in the core and deviations in core design parameters. Adding the uncertainty data values ​​to the theoretical library yields the theoretical library after adding the uncertainty data values.

[0069] Among them, the core design parameter deviation refers to the deviation of power, control rod position, core inlet temperature, core burnup, etc.

[0070] Optionally, the server obtains deviations in the core nuclear data and deviations in core design parameters such as power, control rod position, core inlet temperature, and core burnup. Based on the deviations in the nuclear data and the deviations in core design parameters such as power, control rod position, core inlet temperature, and core burnup, the server determines uncertainty data values ​​to be added to the theoretical library. The server adds the uncertainty data values ​​to the corresponding data in the theoretical library, thereby obtaining a theoretical library with the added uncertainty data values.

[0071] In this embodiment, random uncertainty data values ​​are superimposed on the theoretical library used in the core design program, so that the deviation of on-site operating factors from theoretical simulation can be comprehensively considered, making the calculated results more accurate.

[0072] In one embodiment, performing material composition calculation based on a material calculation subroutine in a precise calculation program and state parameters to obtain the material composition of each fuel rod in the core includes: using a burnup calculation subroutine in a Monte Carlo program to calculate the burnup of each component in a simulated operating state of the core based on the state parameters to obtain the burnup of each component; and using the material calculation subroutine in the Monte Carlo program to determine the material composition of the fuel rods in each component based on the burnup of each component.

[0073] Monte Carlo algorithms, also known as statistical simulation methods, use random numbers, or more commonly, pseudo-random numbers, to solve computational problems. Monte Carlo algorithms work by continuous sampling and gradual approximation. For example, if a black image contains multiple white shapes, each of which is irregular, its area cannot be calculated using edge length formulas. The Monte Carlo method, however, randomly dots the image and then determines the color of the pixel. The result is the area of ​​the white shape: number of white dots / total number of dots * total image area. Based on the principle of decoupling, the Monte Carlo method can accelerate the process of determining component burnup, fuel rod material composition, and true power distribution.

[0074] Optionally, the server uses a subroutine within the Monte Carlo program for burnup calculation to perform burnup calculations on the core's state parameters under the simulated operating state, thereby obtaining the burnup of each component under the simulated operating state. After obtaining the burnup of each component under the simulated operating state, the server uses a subroutine within the Monte Carlo program for material calculation to perform material composition calculations on the obtained burnup of each component, thereby obtaining the material composition of the fuel rods within each component under the simulated operating state.

[0075] In this embodiment, by using different subroutines in the Monte Carlo program to calculate the burnup of each component and the material composition of the fuel rods, the two steps of burnup calculation and material composition calculation can be decoupled, thereby increasing the speed of component burnup and fuel rod material composition calculation, thereby increasing the speed of obtaining the true power distribution of the reactor core.

[0076] In one embodiment, obtaining the detector reaction strength of the core includes obtaining a manufacturing error of the detector and an error in a current algorithm of the detector. Based on the manufacturing error and the error in the current algorithm, data representing uncertainty is superimposed on the detector reaction strength to obtain the detector reaction strength with the data superimposed on it.

[0077] Detector manufacturing error refers to the deviation of the actual geometric parameters of the processed detector from the designed geometric parameters. In actual production, the process factors that influence machining accuracy are complex. Certain machining error issues cannot be resolved solely through single-factor analysis. Instead, a comprehensive analysis using probabilistic statistical methods is required to identify the causes of the machining error and eliminate them. When manufacturing error cannot be eliminated, the adverse effects of manufacturing error can be mitigated by superimposing uncertainties.

[0078] Superimposing uncertainty data on the detector's reaction intensity refers to adding a value to the initial detector reaction intensity. For example, the initial detector reaction intensity obtained is A, but due to detector manufacturing errors and errors in the detector current algorithm, it is necessary to superimpose uncertainty data X to obtain the final detector reaction intensity A+X. For another example, the initial detector reaction intensity obtained is A, but due to detector manufacturing errors and errors in the detector current algorithm, it is necessary to superimpose uncertainty data -X to obtain the final detector reaction intensity AX.

[0079] Optionally, the server first obtains manufacturing errors and current algorithm errors in the detectors. Based on these errors, the server adds a value representing uncertainty to the initial detector response strength, ultimately determining the detector response strength used to calculate the true power distribution of the core under simulated operating conditions.

[0080] In this embodiment, by taking into account the manufacturing error of the detector and the error of the detector's current algorithm when determining the detection reaction intensity, the final determined reaction intensity of the detector can be made more accurate, thereby improving the accuracy of the simulated power distribution obtained based on the detector reaction intensity and power parameters.

[0081] In one embodiment, obtaining the detector reaction strength of the core includes: obtaining the neutron flux in the core when the specifications of the detectors in the core are determined, and determining the detector reaction strength based on the neutron flux.

[0082] Detector specifications can be understood as the detector type or model. Neutron flux refers to the number of neutrons passing through a unit area per unit time and is a key metric for reactor performance. Neutron flux is equal to the product of neutron density and average velocity, and is typically expressed in "neutrons / square centimeter-second." Neutron flux can be categorized as thermal neutron flux and fast neutron flux, depending on neutron energy. Neutron flux distribution measurements are crucial for safe reactor operation, fuel management, determination of maximum allowable power, conduct of various experiments, and sample irradiation.

[0083] Optionally, the server obtains the type or model of the detector, and when the type or model of the detector is determined, obtains the neutron flux in the core. The server calculates the reaction intensity of the detector based on the obtained neutron flux in the core.

[0084] In this embodiment, by obtaining the neutron flux in the core when the specifications of the detector in the core are determined, the reaction intensity of the detector can be determined based on the neutron flux.

[0085] In one embodiment, the method for analyzing core power distribution measurement uncertainty further includes: constructing multiple simulated operating states of the core and state parameters of the core in each simulated operating state; obtaining a power deviation between the actual power distribution of the core and the simulated power distribution in each simulated operating state; and performing a statistical analysis on the power deviation in each simulated operating state to obtain the measurement uncertainty of the core power distribution.

[0086] Statistical analysis methods primarily include descriptive statistics, hypothesis testing, reliability analysis, contingency table analysis, correlation analysis, variance analysis, regression analysis, cluster analysis, and the double 95 principle. For example, the double 95 principle can be used to determine the uncertainty of the final power measurement based on the distribution of deviation results under multiple simulation conditions. The double 95 principle means that 95% of the data points must be included with a 95% confidence level.

[0087] Optionally, the server constructs simulated operating states representing each core operating condition based on various possible scenarios during core operation. Based on the actual and simulated power distributions of the core in each simulated operating condition, the server determines the core power deviation in each simulated operating condition. The server applies statistical analysis to the core power deviation in each simulated operating condition using the double 95 principle, ultimately determining the uncertainty of the core power distribution measurement.

[0088] In this embodiment, by constructing multiple simulated operating states of the core and then determining the uncertainty of the power distribution measurement of the core based on 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, thereby making the uncertainty of the core power measurement finally obtained more accurate and reducing errors.

[0089] The present application also provides an application scenario, which applies the above-mentioned analysis method of the uncertainty of the core power distribution measurement. The application of the analysis method of the uncertainty of the core power distribution measurement in this application scenario is as follows: for a certain reactor fuel management, confirm the loading method of the reactor core and the type of detector in the core. According to the various possible physical operating states of the core, that is, the actual operating state, "component transport calculation + core diffusion calculation" is used to carry out the calculation of component fuel consumption and state parameters of the core under different simulated operating states, mainly including core boron concentration, fuel temperature, moderator temperature and water density, control rod insertion state, fuel depth and other parameters. And based on the obtained component fuel consumption and state parameters, obtain the components used in the core calculation and the reflector group constants. Based on various actual core operating states, multiple simulated core operating states were constructed. The core burnup values ​​BU(i,j), fuel temperature Tf(i,j), moderator temperature Tm(i,j), moderator density Dm(i,j), xenon 135 concentration Xe(i,j), samarium 149 concentration Sm(i,j), and the insertion position CR(m) of each control rod group were specified at each grid point in each simulated operating state to simulate the core characteristics under different actual operating states. Here, i is the radial grid number (i=1,...,I), j is the axial grid number (j=1,...,J), and m is the number of control rods (m=1,...,M). Using the core diffusion program within the core design program, core calculations were performed based on the core state parameters and core group constants for each simulated state. Power parameters such as the three-dimensional core power distribution, power crest factor, and axial power deviation were obtained for each simulated state. Based on the obtained core power parameters, detector cross-sections, and theoretically calculated activity under various simulated conditions, a theoretical library was generated to reconstruct the in-core power distribution. The material composition calculation subroutine within the Monte Carlo program was used to calculate component burnup for each simulated core operating state, thereby determining the material composition of each fuel rod during the burnup process. The power calculation subroutine within the Monte Carlo program, based on the material composition of each fuel rod, was used to calculate the actual power distribution of the core under each simulated state and the reactivity of the in-core detectors. Using the generated theoretical library and detector reactivity data, a flux map processing program was used to simulate flux map measurements, resulting in a simulated power distribution that closely matched the actual power distribution. The deviations between the various parameters in the simulated and actual power distributions under various simulated operating conditions were statistically analyzed, and statistical methods were applied to ultimately determine the uncertainty of the core power distribution measurement.

[0090] It should be understood that, although the various steps in the flowcharts involved in the various embodiments described above are displayed in sequence according to the instructions of the arrows, these steps are not necessarily executed in sequence in the order indicated by the arrows. Unless otherwise specified herein, there is no strict order restriction on the execution of these steps, and these steps can be executed in other orders. Moreover, at least a portion of the steps in the flowcharts involved in the various embodiments described above can include multiple steps or multiple stages, and these steps or stages are not necessarily executed and completed at the same time, but can be executed at different times, and the execution order of these steps or stages is not necessarily to be carried out in sequence, but can be executed in turn or alternately with other steps or at least a portion of steps or stages in other steps.

[0091] Based on the same inventive concept, embodiments of the present application also provide a core power distribution measurement uncertainty analysis device for implementing the aforementioned core power distribution measurement uncertainty analysis method. The solution provided by this device is similar to the solution described in the aforementioned method. Therefore, the specific limitations of one or more embodiments of the core power distribution measurement uncertainty analysis device provided below can be found in the limitations of the core power distribution measurement uncertainty analysis method described above and will not be further elaborated here.

[0092] In one embodiment, as shown in FIG3 , a device for analyzing uncertainty in core power distribution measurement is provided, comprising:

[0093] The state construction module 302 is used to construct a simulated operating state based on the actual operating state of the core, determine the state parameters of the core under the simulated operating state, and obtain group constants representing the grid cross-section values ​​of the core.

[0094] The material composition calculation module 304 is used to perform material composition calculation 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 core.

[0095] The real power distribution determination module 306 is used to perform power calculation based on the power calculation subroutine in the precise calculation program and the material composition of each fuel rod to obtain the real power distribution of the core and the detector reaction intensity of the core.

[0096] The simulated power distribution determination module 308 is used to determine the power parameters of the core in the simulated operating state based on the state parameters and group constants, and perform flux diagram simulation measurement based on the detector reaction intensity and power parameters to obtain the simulated power distribution of the core.

[0097] 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 actual power distribution and the simulated power distribution.

[0098] In one embodiment, the state building module includes:

[0099] The parameter acquisition unit is used to obtain the component burnup and status parameters of the core under the simulated operating state.

[0100] The group constant determination unit is used to determine the core component and reflector group constants based on the component burnup and state parameters.

[0101] In one embodiment, the simulated power distribution determination module includes:

[0102] The power parameter determination unit is used to determine the power parameters of the core under the simulated operating state based on the state parameters and group constants using the core design program.

[0103] The theoretical library generation unit is used to construct a theoretical library for realizing power distribution reconstruction of the core based on power parameters.

[0104] The first simulated power distribution determination unit is used to perform flux diagram simulation measurement based on the theoretical library to obtain the simulated power distribution of the core.

[0105] In one embodiment, the material composition calculation module includes:

[0106] The burnup calculation unit is used to calculate the burnup of each component of the core in the simulated operating state based on the state parameters using the burnup calculation subroutine in the Monte Carlo program to obtain the burnup of each component.

[0107] The material composition calculation unit is used to determine the material composition of the fuel rods in each assembly based on the burnup of each assembly using the material calculation subroutine in the Monte Carlo program.

[0108] In one embodiment, the reaction intensity acquisition unit includes:

[0109] The error acquisition subunit is used to acquire the manufacturing error of the detector and the current algorithm error of the detector.

[0110] The reaction intensity acquisition subunit is used to superimpose data representing uncertainty on the reaction intensity of the detector based on manufacturing error and current algorithm error, so as to obtain the detector reaction intensity with the data representing uncertainty superimposed.

[0111] In one embodiment, the device for analyzing uncertainty in core power distribution measurement further comprises:

[0112] The state parameter determination unit is used to construct multiple simulated operating states of the core and the state parameters of the core in each simulated operating state.

[0113] The power deviation determination unit is used to obtain the power deviation between the actual power distribution and the simulated power distribution of the core in each simulated operating state.

[0114] The measurement uncertainty determination unit is used to perform statistical analysis on the power deviation under each simulated operating state to obtain the measurement uncertainty of the power distribution of the core.

[0115] Each module in the aforementioned core power distribution measurement uncertainty analysis device can be implemented in whole or in part via software, hardware, or a combination thereof. Each module can be embedded in or independent of a processor within a computer device in the form of hardware, or can be stored in a computer device memory in the form of software, allowing the processor to call and execute the corresponding operations of each module.

[0116] In one embodiment, a computer device is provided, which may be a server, and its internal structure diagram may be 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 via a system bus, and the communication interface is connected to the system bus via the input / output interface. The processor of the computer device is used to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, computer-readable instructions and a database. The internal memory provides an environment for the operation of the operating system and computer-readable instructions in the non-volatile storage medium. The computer device's database is used to store the actual operating state of the core, simulated operating state of the core, state parameters of the core under simulated operating state, group constants representing grid cross-section values ​​of the core, power parameters of the core under simulated operating state, simulated power distribution of the core, precise calculation programs, material composition of each fuel rod, true power distribution of the core, measurement uncertainty of the core power distribution, component burnup and reflector parameters of the core under actual operating state, theoretical libraries, Monte Carlo programs, detector reaction intensity under simulated operating state, detector manufacturing errors, and detector current algorithm error data. The computer device's input / output interface is used to exchange information between the processor and external devices. The computer device's communication interface is used to communicate with external terminals via a network connection. When executed by the processor, the computer-readable instructions implement a method for analyzing core power distribution measurement uncertainty.

[0117] Those skilled in the art will understand that the structure shown in FIG4 is merely a block diagram of a portion of the structure related to the solution of the present application, and does not constitute a limitation on the computer device to which the solution of the present application is applied. The specific computer device may include more or fewer components than shown in the figure, or combine certain components, or have a different arrangement of components.

[0118] In one embodiment, a computer device is provided, including a memory and one or more processors. The memory stores computer-readable instructions, and when the computer-readable instructions are executed by the processors, the one or more processors perform the following steps:

[0119] A 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 constants representing the grid cross-section values ​​of the core are obtained; material composition calculations are performed based on the material calculation subroutine and state parameters in the precise calculation program to obtain the material composition of each fuel rod in the core; power calculations are performed 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 core and obtain the detector reaction intensity of the core; the power parameters of the core in the simulated operating state are determined based on the state parameters and group constants, and flux diagram simulation measurements are performed based on the detector reaction intensity and power parameters to obtain the simulated power distribution of the core; and 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.

[0120] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0121] Obtaining component burnup and state parameters of the core under simulated operating conditions; and determining component and reflector group constants of the core based on the component burnup and state parameters.

[0122] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0123] Using a core design program, the power parameters of the core under simulated operating conditions are determined based on state parameters and group constants. Based on the power parameters, a theoretical library is constructed to reconstruct the power distribution of the core. Based on the theoretical library, flux diagram simulation measurements are performed to obtain the simulated power distribution of the core.

[0124] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0125] The burnup calculation subroutine in the Monte Carlo program is used to calculate the burnup of each component of the core in a simulated operating state based on the state parameters to obtain the burnup of each component; and the material calculation subroutine in the Monte Carlo program is used to determine the material composition of the fuel rods in each component based on the burnup of each component.

[0126] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0127] Obtaining the manufacturing error of the detector and the current algorithm error of the detector; and based on the manufacturing error and the current algorithm error, superimposing data representing uncertainty on the reaction intensity of the detector to obtain the detector reaction intensity of the superimposed data representing uncertainty.

[0128] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0129] Construct multiple simulated operating states of the core and the state parameters of the core in each simulated operating state; obtain the power deviation between the real power distribution and the simulated power distribution of the core in each simulated operating state; and perform statistical analysis on the power deviation in each simulated operating state to obtain the measurement uncertainty of the power distribution of the core.

[0130] In one embodiment, one or more non-volatile storage media storing computer-readable instructions, when executed by one or more processors, cause the one or more processors to perform the following steps:

[0131] A 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 constants representing the grid cross-section values ​​of the core are obtained; material composition calculations are performed based on the material calculation subroutine and state parameters in the precise calculation program to obtain the material composition of each fuel rod in the core; power calculations are performed 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 core and obtain the detector reaction intensity of the core; the power parameters of the core in the simulated operating state are determined based on the state parameters and group constants, and flux diagram simulation measurements are performed based on the detector reaction intensity and power parameters to obtain the simulated power distribution of the core; and 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.

[0132] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0133] Obtaining component burnup and state parameters of the core under simulated operating conditions; and determining the components and reflector group constants of the core based on the component burnup and state parameters.

[0134] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0135] Using a core design program, the power parameters of the core under simulated operating conditions are determined based on state parameters and group constants. Based on the power parameters, a theoretical library is constructed to reconstruct the power distribution of the core. Based on the theoretical library, flux diagram simulation measurements are performed to obtain the simulated power distribution of the core.

[0136] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0137] The burnup calculation subroutine in the Monte Carlo program is used to calculate the burnup of each component of the core in a simulated operating state based on the state parameters to obtain the burnup of each component; and the material calculation subroutine in the Monte Carlo program is used to determine the material composition of the fuel rods in each component based on the burnup of each component.

[0138] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0139] Obtaining the manufacturing error of the detector and the current algorithm error of the detector; and based on the manufacturing error and the current algorithm error, superimposing data representing uncertainty on the reaction intensity of the detector to obtain the detector reaction intensity of the superimposed data representing uncertainty.

[0140] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0141] Construct multiple simulated operating states of the core and the state parameters of the core in each simulated operating state; obtain the power deviation between the real power distribution and the simulated power distribution of the core in each simulated operating state; and perform statistical analysis on the power deviation in each simulated operating state to obtain the measurement uncertainty of the power distribution of the core.

[0142] In one embodiment, a computer-readable instruction product is provided, comprising computer-readable instructions that, when executed by a processor, implement the following steps:

[0143] A 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 constants representing the grid cross-section values ​​of the core are obtained; material composition calculations are performed based on the material calculation subroutine and state parameters in the precise calculation program to obtain the material composition of each fuel rod in the core; power calculations are performed 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 core and obtain the detector reaction intensity of the core; the power parameters of the core in the simulated operating state are determined based on the state parameters and group constants, and flux diagram simulation measurements are performed based on the detector reaction intensity and power parameters to obtain the simulated power distribution of the core; and 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.

[0144] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0145] Obtaining component burnup and state parameters of the core under simulated operating conditions; and determining the components and reflector group constants of the core based on the component burnup and state parameters.

[0146] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0147] Using a core design program, the power parameters of the core under simulated operating conditions are determined based on state parameters and group constants. Based on the power parameters, a theoretical library is constructed to reconstruct the power distribution of the core. Based on the theoretical library, flux diagram simulation measurements are performed to obtain the simulated power distribution of the core.

[0148] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0149] The burnup calculation subroutine in the Monte Carlo program is used to calculate the burnup of each component of the core in a simulated operating state based on the state parameters to obtain the burnup of each component; and the material calculation subroutine in the Monte Carlo program is used to determine the material composition of the fuel rods in each component based on the burnup of each component.

[0150] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0151] Obtaining the manufacturing error of the detector and the current algorithm error of the detector; and based on the manufacturing error and the current algorithm error, superimposing data representing uncertainty on the reaction intensity of the detector to obtain the detector reaction intensity of the superimposed data representing uncertainty.

[0152] In one embodiment, when the processor executes the computer-readable instructions, the processor further implements the following steps:

[0153] Construct multiple simulated operating states of the core and the state parameters of the core in each simulated operating state; obtain the power deviation between the real power distribution and the simulated power distribution of the core in each simulated operating state; and perform statistical analysis on the power deviation in each simulated operating state to obtain the measurement uncertainty of the power distribution of the core.

[0154] It should be noted that the user information (including but not limited to user device information, user personal information, etc.) and data (including but not limited to data used for analysis, stored data, displayed data, etc.) involved in this application are all information and data authorized by the user or fully authorized by all parties, and the collection, use and processing of relevant data must comply with the relevant laws, regulations and standards of relevant countries and regions.

[0155] Those skilled in the art will appreciate that all or part of the processes in the above-mentioned embodiment methods can be implemented by instructing the relevant hardware through computer-readable instructions. The computer-readable instructions can be stored in a non-volatile computer-readable storage medium. When the computer-readable instructions are executed, they can include the processes of the embodiments of the above-mentioned methods. Among them, any reference to memory, database or other media used in the embodiments provided in this application may include at least one of non-volatile and volatile memory. Non-volatile memory may include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical memory, high-density embedded non-volatile memory, resistive random access memory (ReRAM), magnetic random access memory (MRAM), ferroelectric random access memory (FRAM), phase change memory (PCM), graphene memory, etc. Volatile memory may include random access memory (RAM) or external cache memory, etc. By way of illustration and not limitation, RAM can be in various forms, such as static random access memory (SRAM) or dynamic random access memory (DRAM). The database involved in the various embodiments provided herein may include at least one of a relational database and a non-relational database. Non-relational databases may include, but are not limited to, distributed databases based on blockchains. The processor involved in the various embodiments provided herein may be, but are not limited to, a general-purpose processor, a central processing unit, a graphics processing unit, a digital signal processor, a programmable logic unit, a data processing logic unit based on quantum computing, and the like.

[0156] The technical features of the above-mentioned embodiments can be combined arbitrarily. In order to make the description concise, not all possible combinations of the technical features in the above-mentioned embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0157] The above-described embodiments merely represent several implementation methods of the present application. While the descriptions are relatively specific and detailed, they should not be construed as limiting the scope of the patent application. It should be noted that a person of ordinary skill in the art may make various modifications and improvements without departing from the spirit of the present application, and these modifications and improvements fall within the scope of protection of the present application. Therefore, the scope of protection of the present patent application shall be determined by the appended claims.

Claims

1. A method for analyzing uncertainty in core power distribution measurement, characterized in that: The method comprises: Building a simulated operating state based on the actual operating state of the core, determining the state parameters of the core under the simulated operating state, and obtaining a group constant representing a grid cross-section value of the core; Perform material composition calculation 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 core; Performing power calculation based on the power calculation subroutine in the precise calculation program and the material composition of each of the fuel rods to obtain the real power distribution of the core and the detector reaction intensity of the core; Determining a power parameter of the core in the simulated operating state based on the state parameter and the group constant, and performing a flux diagram simulation measurement based on the detector reaction intensity and the power parameter to obtain a simulated power distribution of the core; and Based on the difference between the actual power distribution and the simulated power distribution, a measurement uncertainty of the power distribution of the core is determined.

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

3. The method according to claim 1, characterized in that The determining, based on the state parameter and the group constant, the power parameter of the core in the simulated operation state comprises: Using a core design program, based on the state parameters and the group constants, determining the power parameters of the core under the simulated operating state; After determining the power parameter of the core in the simulated operation state, the method further comprises: Based on the power parameters, construct a theoretical library for realizing power distribution reconstruction of the core; and A flux diagram simulation measurement is performed based on the theoretical library to obtain a simulated power distribution of the core.

4. The method according to claim 3, characterized in that After determining the power parameter of the core in the simulated operation state, the method further comprises: obtaining the cross section of the detector; and Based on the power parameters and the cross-section of the detector, a theoretical library for realizing power distribution reconstruction of the core is generated.

5. The method according to claim 4, characterized in that The generating of a theoretical library for realizing the power distribution reconstruction of the core includes: Determining the data value of uncertainty to be superimposed on the theoretical library based on the deviation of the nuclear data in the core and the deviation of the core design parameters; and The data value of the uncertainty is superimposed on the theoretical library to obtain the theoretical library after the data value of the uncertainty is superimposed.

6. The method according to claim 1, characterized in that The material composition calculation is performed 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 core, including: Using a burnup calculation subroutine in a Monte Carlo program, based on the state parameters, the burnup of each component of the core in the simulated operation state is calculated to obtain the burnup of each component; and The material composition of the fuel rods in each of the assemblies is determined based on the burnup of each of the assemblies using a material calculation subroutine in the Monte Carlo program.

7. The method according to claim 1, characterized in that The obtaining of the detector reaction intensity of the core includes: Obtaining a manufacturing error of the detector and a current algorithm error of the detector; and Based on the manufacturing error and the current algorithm error, the data representing the uncertainty is superimposed on the reaction intensity of the detector to obtain the reaction intensity of the detector on which the data representing the uncertainty is superimposed.

8. The method according to claim 1, characterized in that The obtaining of the detector reaction intensity of the core includes: When the specifications of the detectors in the core are determined, obtaining the neutron flux in the core; and Based on the neutron flux, a reaction intensity of the detector is determined.

9. The method according to claim 1, characterized in that: The method further comprises: constructing a plurality of simulated operating states of the core and state parameters of the core in each of the simulated operating states; Obtaining a power deviation between a real power distribution and a simulated power distribution of the core in each of the simulated operating states; and A statistical analysis is performed on the power deviation under each of the simulated operating states to obtain the measurement uncertainty of the power distribution of the core.

10. A device for analyzing uncertainty in core power distribution measurement, characterized in that: The device comprises: A state construction module, used to construct a simulated operation state based on the actual operation state of the core, determine the state parameters of the core under the simulated operation state, and obtain a group constant representing a grid cross-section value of the core; A material composition calculation module, used to calculate the material composition 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 core; A real power distribution determination module, used to perform power calculation based on the power calculation subroutine in the precise calculation program and the material composition of each of the fuel rods, obtain the real power distribution of the core, and acquire the detector reaction intensity of the core; a simulated power distribution determination module, configured to determine the power parameter of the core in the simulated operation state based on the state parameter and the group constant, and to perform a flux diagram simulation measurement based on the detector reaction intensity and the power parameter to obtain a simulated power distribution of the core; and A measurement uncertainty determination module is used to determine the measurement uncertainty of the power distribution of the core based on the difference between the real power distribution and the simulated power distribution.

11. The device according to claim 10, characterized in that The state building module includes: A parameter acquisition unit, used to obtain the component burnup and state parameters of the core under the simulated operation state; and A group constant determination unit is used to determine the group constants of the components and reflector layer of the core based on the component burnup and the state parameters.

12. The device according to claim 10, characterized in that The simulated power distribution determination module comprises: a power parameter determination unit, configured to determine the power parameter of the core under the simulated operation state based on the state parameter and the group constant using a core design program; a theoretical library generating unit, configured to construct a theoretical library for realizing power distribution reconstruction of the core based on the power parameter; and The first simulated power distribution determination unit is used to perform flux diagram simulation measurement based on the theoretical library to obtain the simulated power distribution of the core.

13. The device according to claim 12, characterized in that The theoretical library generation unit comprises: A cross-section acquisition subunit, used to acquire the cross-section of the detector; and The theoretical library generation subunit is used to generate a theoretical library for realizing power distribution reconstruction of the core based on the power parameters and the cross section of the detector.

14. The device according to claim 13, characterized in that The theoretical library generation subunit comprises: A data determination subunit, used to determine the data value of uncertainty to be superimposed on the theoretical library based on the deviation of the nuclear data in the core and the deviation of the core design parameters; and The data superposition subunit is used to superimpose the data value of the uncertainty onto the theoretical library to obtain the theoretical library after superimposing the data value of the uncertainty.

15. The device according to claim 10, characterized in that The material composition calculation module includes: A fuel consumption calculation unit is used to calculate the fuel consumption based on the state parameters using a fuel consumption calculation subroutine in a Monte Carlo program. Calculating the burnup of each component of the core in the simulated operating state to obtain the burnup of each component; and A material composition calculation unit is used to determine the material composition of the fuel rods in each of the assemblies based on the burnup of each of the assemblies using a material calculation subroutine in the Monte Carlo program.

16. The device according to claim 10, characterized in that The reaction intensity acquisition unit comprises: an error acquisition subunit, used to acquire a manufacturing error of the detector and a current algorithm error of the detector; and The reaction intensity acquisition subunit is used to superimpose data representing uncertainty on the reaction intensity of the detector based on the manufacturing error and the current algorithm error, so as to obtain the detector reaction intensity superimposed with the data representing uncertainty.

17. The device according to claim 10, characterized in that The reaction intensity acquisition unit comprises: a flux acquisition subunit, configured to acquire the neutron flux in the core when the specifications of the detectors in the core are determined; and The intensity acquisition subunit is used to determine the reaction intensity of the detector based on the neutron flux.

18. The device according to claim 10, characterized in that The device also includes: a state parameter determination unit, used for constructing a plurality of simulated operating states of the core and a state parameter of the core in each of the simulated operating states; a power deviation determining unit, configured to obtain a power deviation between a real power distribution and a simulated power distribution of the core in each of the simulated operating states; and The measurement uncertainty determination unit is used to perform statistical analysis on the power deviation under each of the simulated operating states to obtain the measurement uncertainty of the power distribution of the core.

19. A computer device comprising a memory and a processor, wherein the memory stores computer-readable instructions, characterized in that: When the processor executes the computer-readable instructions, the steps of the method according to any one of claims 1 to 9 are implemented.

20. A computer-readable storage medium having computer-readable instructions stored thereon, characterized in that: When the computer readable instructions are executed by a processor, the steps of the method according to any one of claims 1 to 9 are implemented.

21. A computer-readable instruction product comprising computer-readable instructions, characterized in that: When the computer readable instructions are executed by a processor, the steps of the method according to any one of claims 1 to 9 are implemented.

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