Method, device and equipment for modifying a reactor core neutronics model and storage medium

Abstract

The application relates to a method, device and equipment for correcting a reactor core neutron model and a storage medium. The method comprises the following steps: determining the measured fast-group neutron flux and the measured thermal-group neutron flux of each segment of a target reactor core according to the reactor core neutron model before correction and the measured power of the target reactor core; determining the equivalent cross-section parameter of each segment according to the state parameter of each segment; and determining the corrected reactor core neutron model according to the measured fast-group neutron flux, the measured thermal-group neutron flux and the equivalent cross-section parameter of each segment. The application can improve the accuracy of the correction of the reactor core neutron model, so that the theoretical power can be more accurately calculated based on the corrected model, and the nuclear reaction in the reactor core can be more accurately monitored.

Description

Technical Field

[0001] This application relates to the field of nuclear reactor technology, and in particular to a method, apparatus, device and storage medium for correcting a reactor core neutronics model. Background Technology

[0002] Nuclear reactions play a crucial role in nuclear power plants, with the reactor core being the heart of the process. Online core monitoring is one of the essential means of ensuring the safe operation of a nuclear power plant. Typically, core monitoring systems monitor the nuclear reaction within the reactor core by combining the theoretical power distribution calculated based on neutronics models with the power distribution measured by core detection instruments. If the deviation between the theoretical and measured power distributions exceeds a preset threshold, it indicates a potential risk to the nuclear reaction operation. Therefore, obtaining a more accurate theoretical power distribution is crucial for monitoring nuclear power plants.

[0003] In related technologies, a global optimization algorithm for the neutron equivalent cross-section deviation is used to adjust the neutronics model so that the theoretical power distribution can be calculated based on the adjusted neutronics model. However, the accuracy of the model adjustment method in related technologies is not very high. Summary of the Invention

[0004] Therefore, it is necessary to provide a method, apparatus, device, and storage medium for correcting the neutronics model in the reactor core, which can improve the accuracy of neutronics model correction, in order to address the above-mentioned technical problems.

[0005] Firstly, this application provides a method for modifying a reactor core neutronics model, including:

[0006] Based on the original core neutronics model and the measured power of the target core, the measured fast group neutron flux and the measured hot group neutron flux of each segment of the target core are determined.

[0007] The equivalent cross-sectional parameters of each segment are determined based on the state parameters of each segment.

[0008] Based on the measured fast group neutron flux, measured hot group neutron flux, and equivalent cross-sectional parameters of each segment, the modified core neutronics model is determined.

[0009] In one embodiment, a modified core neutronics model is determined based on the measured fast group neutron flux, the measured hot group neutron flux, and the equivalent cross-section parameters of each segment, including:

[0010] For each segment, the first leakage curvature parameter is determined based on the measured fast group neutron flux, the measured hot group neutron flux, and the equivalent cross-sectional parameters of the segment.

[0011] Based on the first leakage curvature parameter, the corrected core neutronics model is determined.

[0012] In one embodiment, a first leakage curvature parameter is determined based on the measured fast group neutron flux, the measured hot group neutron flux, and the equivalent cross-sectional parameters of the nodal, including:

[0013] Based on the measured fast group neutron flux, measured hot group neutron flux, equivalent cross-sectional parameters, and fast group leakage correction of the nodal, the fast group neutron equilibrium equation is determined, wherein the fast group leakage correction includes the first leakage curvature parameter.

[0014] Based on the measured fast group neutron flux, measured hot group neutron flux, equivalent cross-sectional parameters, and hot group leakage correction of the nodal, the hot group neutron balance equation is determined, wherein the hot group leakage correction includes the first leakage curvature parameter.

[0015] The first leakage curvature parameter is determined based on the fast group neutron balance equation and the hot group neutron balance equation.

[0016] In one embodiment, determining the modified core neutronics model based on the first leakage curvature parameter includes:

[0017] The fast group neutron balance equation and the hot group neutron balance equation are modified according to the first leakage curvature parameter to obtain the modified core neutronics model.

[0018] In one embodiment, determining the equivalent cross-sectional parameters of each segment based on the state parameters of each segment includes:

[0019] For each block, multiple state parameters corresponding to the block are determined based on a preset set of state parameters.

[0020] The equivalent cross-sectional parameters of the segment are determined based on multiple state parameters using a preset difference algorithm.

[0021] In one embodiment, the measured power of the target core includes the measured power of each segment of the target core. Based on the uncorrected core neutronics model and the measured power of the target core, the measured fast group neutron flux and the measured hot group neutron flux of each segment of the target core are determined, including:

[0022] For each node, the theoretical fast group neutron flux, theoretical hot group neutron flux, fast group macroscopic energy production cross section, and hot group macroscopic energy production cross section of the node are determined based on the original core neutronics model.

[0023] Based on the theoretical fast group neutron flux, the theoretical hot group neutron flux, the measured power, the macroscopic energy production cross section of the fast group, and the macroscopic energy production cross section of the hot group of the nodal, the measured fast group neutron flux and the measured hot group neutron flux of the nodal are determined.

[0024] In one embodiment, the method further includes:

[0025] The equivalent cross-sectional parameters of each perturbation node are determined based on the neutronics model of the perturbation core; the fast group neutron flux, the hot group neutron flux, and the power are measured.

[0026] The second leakage curvature parameter is determined based on the equivalent cross-sectional parameters of each perturbation nodal, the measured fast group neutron flux, the measured hot group neutron flux, and the measured power.

[0027] Based on the second leakage curvature parameter, the corrected neutronics model of the disturbed core is determined;

[0028] The correctness of the modified neutronics model of the disturbed core is determined based on the measured fast group neutron flux, measured hot group neutron flux, and measured power of each disturbed node.

[0029] In one embodiment, the correctness of the corrected perturbed core neutronics model is determined based on the measured fast group neutron flux, measured hot group neutron flux, and measured power of each perturbed node, including:

[0030] Based on the modified neutronics model of the disturbed core, the modified fast group neutron flux, modified hot group neutron flux and modified power of each disturbed node are determined.

[0031] Based on the differences between the measured fast group neutron flux and the corresponding corrected fast group neutron flux of each perturbation node, the differences between the measured hot group neutron flux and the corresponding corrected hot group neutron flux of each perturbation node, and the differences between the measured power and the corresponding corrected power of each perturbation node, the correctness of the corrected perturbation core neutronics model is determined.

[0032] In one embodiment, the correctness of the corrected perturbed core neutronics model is determined based on the differences between the measured fast group neutron flux and the corresponding corrected fast group neutron flux of each perturbed node, the differences between the measured hot group neutron flux and the corresponding corrected hot group neutron flux of each perturbed node, and the differences between the measured power and the corresponding corrected power of each perturbed node. This includes:

[0033] If the difference between the measured fast group neutron flux of each perturbed node and the corresponding corrected fast group neutron flux is less than a first preset threshold, the difference between the measured hot group neutron flux of each perturbed node and the corresponding corrected hot group neutron flux is less than a second preset threshold, and the difference between the measured power of each perturbed node and the corresponding corrected power is less than a third preset threshold, then the corrected perturbed core neutron model is determined to be correct.

[0034] In one embodiment, the method further includes:

[0035] The theoretical fast group neutron flux, theoretical hot group neutron flux, and theoretical power of each segment of the target core are determined based on the modified core neutronics model.

[0036] Secondly, this application also provides a correction device for a reactor core neutronics model, comprising:

[0037] The first determining module is used to determine the measured fast group neutron flux and the measured hot group neutron flux of each segment of the target core based on the core neutronics model before modification and the measured power of the target core.

[0038] The second determining module is used to determine the equivalent cross-sectional parameters of each segment based on the state parameters of each segment.

[0039] The third determination module is used to determine the corrected core neutronics model based on the measured fast group neutron flux, measured hot group neutron flux, and equivalent cross-sectional parameters of each segment.

[0040] Thirdly, this application also provides a computer device including a memory and a processor, wherein the memory stores a computer program, and the processor executes the computer program to implement the steps of the method described in the first aspect.

[0041] Fourthly, this application also provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements the steps of the method described in the first aspect.

[0042] Fifthly, this application also provides a computer program product, including a computer program that, when executed by a processor, implements the steps of the method described in the first aspect.

[0043] The aforementioned method, apparatus, device, and storage medium for correcting the core neutronics model determine the measured fast group neutron flux and measured hot group neutron flux of each segment of the target core based on the original core neutronics model and the measured power of the target core; determine the equivalent cross-section parameters of each segment based on the state parameters of each segment; and determine the corrected core neutronics model based on the measured fast group neutron flux, measured hot group neutron flux, and equivalent cross-section parameters of each segment. Compared to the conventional method of adjusting the neutronics model through a global optimization algorithm based on the neutron equivalent cross-section deviation, the embodiments of this application determine the measured fast group neutron flux and hot group neutron flux of each segment based on the original core neutronics model and the measured power of the target core. By combining actual measurement data with theoretical data, the distribution of fast group neutron flux and hot group neutron flux in each segment can be accurately determined. Furthermore, the method of determining the equivalent cross-sectional parameters of each segment based on its state parameters is more accurate because the equivalent cross-sectional parameters differ under different state parameters. Moreover, by accurately measuring the fast group neutron flux, hot group neutron flux, and equivalent cross-sectional parameters of each segment, the corrected core neutronics model can be determined more precisely, thereby improving the accuracy of the model correction. This allows for more accurate calculation of theoretical power based on the corrected model, facilitating more accurate monitoring of nuclear reactions within the core. Attached Figure Description

[0044] To more clearly illustrate the technical solutions in the embodiments or related technologies of this application, the accompanying drawings used in the description of the embodiments or related technologies will be briefly introduced below. Obviously, the accompanying drawings described below are only some embodiments of this application. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0045] Figure 1 This is a schematic diagram illustrating the implementation environment of a method for correcting a core neutronics model in one embodiment of this application;

[0046] Figure 2 This is a flowchart illustrating a method for correcting a core neutronics model in one embodiment of this application.

[0047] Figure 3 This is a flowchart illustrating a method for correcting a core neutronics model in another embodiment of this application.

[0048] Figure 4 This is a flowchart illustrating a method for correcting a core neutronics model in another embodiment of this application.

[0049] Figure 5This is a flowchart illustrating a method for correcting a core neutronics model in another embodiment of this application.

[0050] Figure 6 This is a flowchart illustrating a method for correcting a core neutronics model in another embodiment of this application.

[0051] Figure 7 This is a flowchart illustrating a method for correcting a core neutronics model in another embodiment of this application.

[0052] Figure 8 This is a flowchart illustrating a method for correcting a core neutronics model in another embodiment of this application.

[0053] Figure 9 This is a schematic diagram of the structure of a correction device for a core neutronics model in one embodiment of this application;

[0054] Figure 10 This is an internal structural diagram of a computer device in one embodiment of this application. Detailed Implementation

[0055] To make the objectives, technical solutions, and advantages of this application clearer, the following detailed description is provided in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the scope of this application.

[0056] Figure 1 This is a schematic diagram illustrating the implementation environment of a method for correcting a reactor core neutronics model in one embodiment of this application, as shown below. Figure 1 As shown, the implementation environment of this application embodiment may include a terminal 10 and a server 11; wherein, the terminal 10 can communicate with the server 11 via a network. The terminal 10 may include, but is not limited to, various personal computers, laptops, smartphones, and tablets. The server 11 can be implemented using a standalone server or a server cluster composed of multiple servers. The data storage system can be integrated on the server 11 or located on the cloud or other network servers.

[0057] Combination Figure 1In the implementation environment shown in this embodiment, server 11 can determine the measured fast group neutron flux and measured hot group neutron flux of each segment of the target core based on the unmodified core neutronics model and the measured power of the target core; and determine the equivalent cross-sectional parameters of each segment based on the state parameters of each segment. Further, server 11 can determine the modified core neutronics model based on the measured fast group neutron flux, measured hot group neutron flux, and equivalent cross-sectional parameters of each segment. Further, server 11 can determine the theoretical fast group neutron flux, theoretical hot group neutron flux, and theoretical power of each segment of the target core based on the modified core neutronics model, and send these parameters to terminal 10.

[0058] In practical applications, monitoring and analyzing measured power can promptly detect anomalies within the reactor core and allow for corresponding measures to ensure the stable operation of the nuclear power plant. When the deviation between the theoretical power distribution and the measured power distribution exceeds a preset threshold, further measures are required. One approach is to reduce the power level to mitigate the impact of the large theoretical-to-measurement deviation, but this method would affect the economics of the nuclear power plant. Another approach is to adjust the neutronics model, thereby adjusting the theoretical power distribution and gradually reducing the theoretical-to-measurement deviation. Related technologies use a global optimization algorithm for neutron equivalent cross-section deviation to adjust the neutronics model, enabling the calculation of the theoretical power distribution based on the adjusted model. However, this method requires extensive computation to generate the neutron equivalent cross-section, resulting in high computational complexity and necessitating significant computational resources and time. Furthermore, the search results of this method depend on the setting and adjustment of initial parameters, requiring some manual intervention and leading to uncertainty in the results. Therefore, this method of adjusting neutronics model parameters may result in lower accuracy of neutronics model correction.

[0059] The core neutronics model correction method, apparatus, device, and storage medium provided in this application determine the measured fast group neutron flux and measured hot group neutron flux of each segment of the target core based on the core neutronics model before correction and the measured power of the target core; determine the equivalent cross-section parameters of each segment based on the state parameters of each segment; and determine the corrected core neutronics model based on the measured fast group neutron flux, measured hot group neutron flux, and equivalent cross-section parameters of each segment. Compared to the conventional method of adjusting the neutronics model through a global optimization algorithm based on the neutron equivalent cross-section deviation, this application determines the measured fast group neutron flux and hot group neutron flux of each segment based on the core neutronics model before correction and the measured power of the target core. By combining actual measurement data with theoretical data, the distribution of fast group neutron flux and hot group neutron flux in each segment can be accurately determined. Furthermore, the method of determining the equivalent cross-sectional parameters of each segment based on its state parameters is more accurate because the equivalent cross-sectional parameters differ under different state parameters. Moreover, by accurately measuring the fast group neutron flux, hot group neutron flux, and equivalent cross-sectional parameters of each segment, it is unnecessary to pre-set initial conditions and parameters, thus reducing artificially introduced uncertainties. This allows for a more accurate determination of the corrected core neutronics model, improving the accuracy of model correction. This, in turn, enables more accurate calculation of theoretical power based on the corrected model, facilitating more accurate monitoring of nuclear reactions within the core.

[0060] In one embodiment, Figure 2 This is a flowchart illustrating a method for correcting a core neutronics model in one embodiment of this application. This embodiment uses the application of this method to server 11 as an example for explanation. Figure 2 As shown, the method in this application embodiment may include the following steps:

[0061] Step S201: Based on the original core neutronics model and the measured power of the target core, determine the measured fast group neutron flux and the measured hot group neutron flux of each segment of the target core.

[0062] For example, the core neutronics model involved in the embodiments of this application refers to a mathematical model used to describe neutron transport and interaction in a nuclear reactor; the core neutronics model before modification is the model before modification.

[0063] For example, the measured power of the target reactor core involved in this application embodiment refers to the power value actually measured on the target reactor core (or simply the target core). In a nuclear reactor, power is an indicator of reactor energy output, which can be measured by measuring heat release or using other monitoring equipment. The monitoring equipment can be an online monitoring system for core power distribution. This online monitoring system uses multiple fixed neutron detectors and signal acquisition systems installed inside the nuclear power plant to collect and process data to obtain the measured power of the core. Of course, the measured power of the target reactor core can also be measured in other ways.

[0064] For example, the measured fast group neutron flux in this application embodiment refers to the number of neutrons passing through a unit area per unit time within a fast neutron energy region, as measured by an online monitoring system. The measured hot group neutron flux of each block in this application embodiment refers to the number of neutrons passing through a unit area per unit time within a hot neutron energy region, as measured by an online monitoring system.

[0065] For example, in the embodiments of this application, the target core can be divided into multiple segments.

[0066] In this embodiment, the server can determine the measured fast group neutron flux and measured hot group neutron flux of each segment in the target core based on the original core neutronics model and the monitored target core measurement power. In this embodiment, by combining actual measurement data with theoretical data, the distribution of fast group neutron flux and hot group neutron flux in each segment can be accurately determined.

[0067] For example, the server can determine the theoretical parameters of each segment based on the original core neutronics model, and determine the measured fast group neutron flux and measured hot group neutron flux of each segment based on the theoretical parameters and the measured power of each segment.

[0068] Step S202: Determine the equivalent cross-sectional parameters of each segment based on the state parameters of each segment.

[0069] For example, the state parameters involved in the embodiments of this application may include, but are not limited to, at least one of the following: burnup, boron concentration, moderator density, effective fuel temperature, xenon concentration, and Pu / U ratio. Burnup refers to the degree of combustion of nuclear fuel in the reactor. Boron is a commonly used neutron absorbing material used in nuclear reactors to control neutron flux. By controlling the boron concentration in the reactor core, neutron absorption can be adjusted, thereby affecting the distribution of neutron flux. A moderator is a material used to slow down the velocity of neutrons. The density of the moderator affects the neutron slowing process, thus affecting the distribution of neutron flux. Effective fuel temperature refers to the temperature of the nuclear fuel, which affects the vibrational state of atomic nuclei in the fuel and the physical properties of the fuel material. Xenon is a short-lived radioactive nuclide and one of the fission products after nuclear fuel burnup. The presence of xenon affects the absorption and scattering behavior of neutrons, thereby affecting the distribution of neutron flux. The Pu / U ratio refers to the ratio of plutonium to uranium in the nuclear fuel. Plutonium is an important nuclear fuel fission product. Changes in the Pu / U ratio affect the cross-sectional area and absorption properties of fuel materials, which in turn affect the distribution of neutron flux.

[0070] In this step, the server can obtain the status parameters of each segment and determine the equivalent cross-sectional parameters of each segment based on the different status parameters in each segment.

[0071] For example, the equivalent cross-sectional parameters involved in the embodiments of this application may include, but are not limited to, at least one of the following: fast group diffusion coefficient, hot group diffusion coefficient, downward macroscopic scattering cross section, fast group macroscopic absorption cross section, hot group macroscopic absorption cross section, fast group macroscopic neutron generation cross section, hot group macroscopic neutron generation cross section, fast group macroscopic energy generation cross section, and hot group macroscopic energy generation cross section.

[0072] In this embodiment of the application, the equivalent cross-sectional parameters of each segment are determined based on the state parameters of each segment. Since the equivalent cross-sectional parameters are different under different state parameters, more accurate equivalent cross-sectional parameters can be obtained based on the state parameters.

[0073] Step S203: Determine the corrected core neutronics model based on the measured fast group neutron flux, measured hot group neutron flux, and equivalent cross-sectional parameters of each segment.

[0074] In this step, the server can determine the corrected core neutronics model based on the measured fast group neutron flux and measured hot group neutron flux of each block obtained in step S201 and the equivalent cross-section parameters obtained in step S202.

[0075] For example, the modified core neutronics model involved in the embodiments of this application may refer to the core neutronics model obtained after modifying the original core neutronics model.

[0076] In this embodiment of the application, the modified core neutronics model can be determined more accurately by measuring the fast group neutron flux, the hot group neutron flux, and the equivalent cross-sectional parameters of each segment.

[0077] In the aforementioned method for correcting the core neutronics model, the measured fast group neutron flux and measured hot group neutron flux of each segment of the target core are determined based on the original core neutronics model and the measured power of the target core. The equivalent cross-sectional parameters of each segment are determined based on its state parameters. Finally, the corrected core neutronics model is determined based on the measured fast group neutron flux, measured hot group neutron flux, and equivalent cross-sectional parameters of each segment. Therefore, in this embodiment, by determining the measured fast group neutron flux and hot group neutron flux of each segment based on the original core neutronics model and the measured power of the target core, and by combining actual measurement data with theoretical data, the distribution of fast group neutron flux and hot group neutron flux in each segment can be accurately determined. Furthermore, the method of determining the equivalent cross-sectional parameters of each segment based on its state parameters is more accurate because the equivalent cross-sectional parameters differ under different state parameters. Furthermore, by accurately measuring the fast group neutron flux, hot group neutron flux, and equivalent cross-sectional parameters of each segment, the corrected core neutronics model can be determined more accurately, thereby improving the accuracy of the model correction. This allows for more accurate calculation of theoretical power based on the corrected model, which is beneficial for more accurate monitoring of nuclear reactions within the core.

[0078] In one embodiment, based on the above embodiments, this application embodiment provides an exemplary description of the relevant content of step S203 in the above embodiments, which involves determining the modified core neutronics model based on the measured fast group neutron flux, measured hot group neutron flux, and equivalent cross-sectional parameters of each segment. For example... Figure 3 As shown, step S203 may include step S2031 and step S2032.

[0079] Step S2031: For each segment, determine the first leakage curvature parameter based on the measured fast group neutron flux, the measured hot group neutron flux, and the equivalent cross-sectional parameters of the segment.

[0080] For example, the first leakage curvature parameter involved in the embodiments of this application is a parameter used to indicate the degree of leakage of fast group neutrons and hot group neutrons between nodes.

[0081] In this step, the server can determine the fast group neutron balance equation and the hot group neutron balance equation based on the measured fast group neutron flux and hot group neutron flux, equivalent cross-sectional parameters, and corresponding leakage corrections, thereby determining the first leakage curvature parameter.

[0082] Optionally, the server can determine the fast group neutron balance equation based on the measured fast group neutron flux, measured hot group neutron flux, equivalent cross-sectional parameters, and fast group leakage correction of the node, wherein the fast group leakage correction includes the first leakage curvature parameter.

[0083] For example, the fast group leakage correction amount involved in the embodiments of this application can be expressed as: in, D is the first leakage curvature parameter of the nth segment; n,1 The derivative of the fast group diffusion coefficient of the nth segment; Let n be the measured fast group neutron flux of the nth block; n is an integer greater than 0.

[0084] Of course, the fast group leakage correction amount can also be expressed as other variations or equivalent formulas of the above formula.

[0085] For example, the fast group neutron equilibrium equation involved in the embodiments of this application can be expressed as:

[0086]

[0087] in, Σ is the fast group neutron flux on the surface of the nth block; a,n,1 Σ is the macroscopic absorption cross section of the fast group of the nth segment; r,n vΣ is the downward macroscopic scattering cross section of the nth segment; f,n,g Generates a cross section for the fast group macroscopic neutrons of the nth block; k eff Neutron coefficient; Let be the measured neutron flux of the hot group in the nth block. Further, This represents the net fast group neutron flux flowing out of the six surfaces of the nodal; This represents the fast group neutron flux that disappears due to absorption or transfer (slowing down from a fast group to a hot group); This represents the fast group neutron flux generated by fission.

[0088] Of course, the neutron equilibrium equation in fast groups can also be expressed as other variations or equivalent formulas of the above formula (1).

[0089] Furthermore, the server can determine the hot group neutron balance equation based on the measured fast group neutron flux, measured hot group neutron flux, equivalent cross-sectional parameters, and hot group leakage correction of the node, wherein the hot group leakage correction includes the first leakage curvature parameter.

[0090] For example, the heat cluster leakage correction amount involved in the embodiments of this application can be expressed as: Among them, D n,2 It is the derivative of the heat group diffusion coefficient of the nth segment.

[0091] For example, the neutron balance equation of the hot group involved in the embodiments of this application can be expressed as:

[0092]

[0093] in, Σ is the neutron flux of the thermal group on the surface of the nth segment; a,n,2 Let be the macroscopic absorption cross section of the heat group in the nth segment. Furthermore, This represents the net outflow of heat cluster neutron flux from the six surfaces of the nodal; This represents the thermal group neutron flux that disappears due to absorption.

[0094] Of course, the neutron equilibrium equation in the hot group can also be expressed as other variations or equivalent formulas of the above formula (2).

[0095] Furthermore, the server can determine the first leakage curvature parameter based on the fast group neutron balance equation and the hot group neutron balance equation.

[0096] For example, the server can transform the neutron equilibrium equation (1) of the fast group and the neutron equilibrium equation (2) of the hot group into a matrix solution form, which can be expressed as:

[0097] A n Φ n =0 (3)

[0098] Where, Φ n For the corresponding fast group and hot group neutron flux; A n This is the matrix obtained from all the coefficients of the fast group neutron balance equation (1) and the hot group neutron balance equation (2).

[0099] If matrix A n If the determinant of is zero, then equation (3) has a solution, namely the fast group neutron flux and the hot group neutron flux on the nth block. Therefore, let det(A n ) = 0 can be represented as:

[0100]

[0101] It should be noted that equation (4) has two solutions, but only one has physical meaning; the other solution leads to a negative group neutron flux distribution. Therefore, by making matrix A... n The first leakage curvature parameter B can be obtained by finding the determinant of the matrix to be zero and solving for the rank of the matrix. n 2 The value of .

[0102] Of course, formula (4) can also be expressed as other variations or equivalent formulas of the above formula (4).

[0103] As can be seen, in this embodiment of the application, the server can determine the fast group neutron balance equation and the hot group neutron balance equation by increasing the fast group leakage correction amount and the hot group leakage correction amount, so as to more accurately determine the first leakage curvature parameter.

[0104] Step S2032: Determine the corrected core neutronics model based on the first leakage curvature parameter.

[0105] In this step, the server can modify the neutron balance equation based on the first leakage curvature parameter, thereby obtaining the modified core neutronics model.

[0106] For example, the server can modify the fast group neutron balance equation and the hot group neutron balance equation according to the first leakage curvature parameter to obtain the modified core neutronics model.

[0107] In one possible implementation, if the original core neutronics model does not include leakage correction, the server can determine the fast group leakage correction and the hot group leakage correction based on the first leakage curvature parameter. Furthermore, the server can obtain the modified fast group neutron equilibrium equation by adding the fast group leakage correction to the original fast group neutron equilibrium equation, and the modified hot group neutron equilibrium equation by adding the hot group leakage correction to the original hot group neutron equilibrium equation, thus obtaining the modified core neutronics model.

[0108] In another possible implementation, if the original core neutronics model already has a leakage correction, the server can correct the fast group leakage correction in the original fast group neutron balance equation and the hot group leakage correction in the original hot group neutron balance equation according to the first leakage curvature parameter, thereby obtaining the corrected core neutronics model.

[0109] In summary, for each node, the server can determine the first leakage curvature parameter based on the measured fast group neutron flux, measured hot group neutron flux, and equivalent cross-section parameters of the node. Furthermore, the server can determine the corrected core neutronics model based on the first leakage curvature parameter. Since the measured fast group neutron flux, measured hot group neutron flux, and equivalent cross-section parameters in this embodiment are relatively accurate, the server in this embodiment can accurately determine the first leakage curvature parameter based on the measured fast group neutron flux, measured hot group neutron flux, and equivalent cross-section parameters of the node. Therefore, based on the accurate first leakage curvature parameter, an accurate corrected core neutronics model can be obtained, allowing for more accurate calculation of theoretical power based on the corrected model.

[0110] In one embodiment, Figure 4 This is a flowchart illustrating a method for correcting a core neutronics model in another embodiment of this application, as shown below. Figure 4 As shown, based on the above embodiments, this application provides an exemplary description of step S202, which involves determining the equivalent cross-sectional parameters of each segment based on the state parameters of each segment. For example... Figure 4 As shown, step S202 above includes step S2021 and step S2022.

[0111] Step S2021: For each segment, determine multiple state parameters corresponding to the segment based on a preset set of state parameters.

[0112] For example, the preset state parameter set involved in the embodiments of this application refers to an interpolation table pre-generated in the server. This state parameter set can cover all state parameter ranges corresponding to different cross-sectional parameters, and may include, but is not limited to, parameter ranges such as fuel consumption, boron concentration, moderator density, effective fuel temperature, xenon concentration, and Pu / U ratio.

[0113] In this step, for each segment, considering that the equivalent cross-sectional parameters include one or more cross-sectional parameters, the server can determine one or more state parameters corresponding to each cross-sectional parameter based on the preset set of state parameters.

[0114] For example, assuming that the preset state parameter set includes state parameters A1 and A2 corresponding to section parameter A, and state parameters B1, B2 and B3 corresponding to section parameter B, the server can determine state parameters A1 and A2 corresponding to section parameter A, and state parameters B1, B2 and B3 corresponding to section parameter B based on the preset state parameter set.

[0115] Step S2022: Determine the equivalent cross-sectional parameters of the block according to multiple state parameters and a preset interpolation algorithm.

[0116] For example, the preset interpolation algorithms involved in the embodiments of this application may include, but are not limited to, linear interpolation, polynomial interpolation, or spline interpolation. Linear interpolation assumes that the function between given data points has a linear relationship. Polynomial interpolation assumes that the function between given data points can be represented as a polynomial. Spline interpolation assumes that the function between given data points can be formed by concatenating multiple interpolation segments.

[0117] In this step, for each cross-sectional parameter of each segment, after the server determines one or more state parameters corresponding to the cross-sectional parameter according to the preset state parameter set, it can determine the cross-sectional parameter of the segment according to the preset interpolation algorithm.

[0118] For example, the macroscopic absorption cross section of a fast group may be related to fuel consumption, boron concentration, and moderator density in a preset set of state parameters; the macroscopic energy generation cross section of a hot group may be related to the effective fuel temperature, xenon concentration, and Pu / U ratio in a preset set of state parameters.

[0119] Optionally, for each section parameter of each block, the server can determine the section parameter of the block by using the following polynomial interpolation formula (5) based on one or more state parameters corresponding to the section parameter.

[0120]

[0121] Among them, SP1, SP2, and SP3 are the three state parameters of the node; c i,j Σ represents the expansion coefficient; Σ represents the cross-sectional parameter information of each segment.

[0122] Of course, the server can also determine the cross-sectional parameter of the segment by other variations or equivalent formulas of the above polynomial interpolation formula (5) based on one or more state parameters corresponding to the cross-sectional parameter.

[0123] In summary, for each segment, the server can select and determine multiple state parameters corresponding to different cross-sections from a preset set of state parameters, and determine the equivalent cross-sectional parameters of the segment according to a preset interpolation algorithm. In this embodiment, by using a preset set of state parameters, different state parameters suitable for different cross-sections can be selected. This takes into account the influence of different operating conditions on the cross-sectional parameters, thus more accurately determining the equivalent cross-sectional parameters of the segment. Furthermore, the server can accurately obtain the equivalent cross-sectional parameters of the segment in actual operation by following a preset interpolation algorithm, thereby improving the accuracy of model correction.

[0124] In one embodiment, Figure 5 This is a flowchart illustrating a method for correcting a core neutronics model in another embodiment of this application, as shown below. Figure 5 As shown, based on the above embodiments, this application provides an exemplary description of step S201, which involves determining the measured fast group neutron flux and measured hot group neutron flux of each segment of the target core based on the unmodified core neutronics model and the measured power of the target core. For example... Figure 5 As shown, the above step S201 includes step S2011 and step S2012.

[0125] Step S2011: For each node, determine the theoretical fast group neutron flux, theoretical hot group neutron flux, fast group macroscopic energy production cross section, and hot group macroscopic energy production cross section of the node based on the original core neutronics model.

[0126] For example, in the embodiments of this application, the theoretical fast group neutron flux refers to the number of neutrons passing through a unit area per unit time in the fast neutron energy region calculated according to the core neutronics model before modification; the theoretical hot group neutron flux refers to the number of neutrons passing through a unit area per unit time in the hot neutron energy region calculated according to the core neutronics model before modification.

[0127] For example, in the embodiments of this application, the macroscopic energy generation section of fast groups refers to the process in which neutrons interact with atomic nuclei in nuclear reactor fuel and generate energy in a high-energy region; the macroscopic energy generation section of hot groups refers to the process in which neutrons interact with atomic nuclei in nuclear reactor fuel and generate energy in a lower-energy region.

[0128] In this step, for each node, the server can calculate the theoretical fast group neutron flux, theoretical hot group neutron flux, fast group macroscopic energy production cross section, and hot group macroscopic energy production cross section of the node based on the original core neutronics model.

[0129] Step S2012: Determine the measured fast group neutron flux and the measured hot group neutron flux of the node based on the theoretical fast group neutron flux, the theoretical hot group neutron flux, the measured power, the fast group macroscopic energy generation cross section, and the hot group macroscopic energy generation cross section of the node.

[0130] In this step, for each node, the server can determine the measured fast group neutron flux and the measured hot group neutron flux of the node based on the node's theoretical fast group neutron flux, theoretical hot group neutron flux, measured power, fast group macroscopic energy generation cross section, and hot group macroscopic energy generation cross section.

[0131] For example, in the embodiments of this application, it is assumed that the original core neutronics model can effectively predict the local neutron energy spectrum, that is, the relationship between the theoretical fast group neutron flux, the theoretical hot group neutron flux, the measured fast group neutron flux, and the measured hot group neutron flux can be expressed as:

[0132]

[0133] in, For theoretical fast group neutron flux; This represents the neutron flux in the theoretical hot group.

[0134] Of course, formula (6) can also be expressed as other variations or equivalent formulas of the above formula (6).

[0135] Based on the measured power of the segment, we can obtain:

[0136]

[0137] Where, κΣf,n,1 Generate a cross section for the macroscopic energy of the fast group of the nth block; κΣ f,n,2 The cross section for generating macroscopic energy of the heat group in the nth segment; The measured power of the nth segment.

[0138] Of course, formula (7) can also be expressed as other variations or equivalent formulas of the above formula (7).

[0139] For each block, the server can calculate the measured fast group neutron flux and the measured hot group neutron flux of the block according to formulas (6) and (7).

[0140] In summary, for each node, the server can calculate the theoretical fast group neutron flux, theoretical hot group neutron flux, fast group macroscopic energy production cross section, and hot group macroscopic energy production cross section of the node based on the unmodified core neutronics model. Furthermore, the server can determine the measured fast group neutron flux and measured hot group neutron flux of the node based on these parameters. In this embodiment, the theoretical neutron flux can be accurately calculated using the unmodified core neutronics model, and the measured neutron flux can be calculated more accurately by combining the theoretical neutron flux with the actual measured power. This application relies solely on the measured power and does not require other high-quality data, thus improving the accuracy of the neutronics model.

[0141] In one embodiment, Figure 6 This is a flowchart illustrating a method for correcting a core neutronics model in another embodiment of this application, as shown below. Figure 6 As shown, based on the above embodiments, this application provides an exemplary description of the verification of the model correction method for the above-mentioned core neutronics model correction method. For example... Figure 6 As shown, the method in this application embodiment may further include steps S601, S602, S603 and S604.

[0142] Step S601: Determine the equivalent cross-sectional parameters of each perturbation node, measure the fast group neutron flux, measure the hot group neutron flux, and measure the power based on the perturbation core neutron model.

[0143] In this step, the server can pre-establish a perturbed core neutronics model and determine the equivalent cross-sectional parameters of each perturbed node, measure the fast group neutron flux, measure the hot group neutron flux, and measure the power based on the perturbed core neutronics model.

[0144] For example, the perturbed core neutronics model involved in the embodiments of this application is used to indicate a model established based on perturbed analysis of core design and operating parameters. By establishing a perturbed model, changes that may occur during actual operation can be simulated and evaluated. The equivalent cross-sectional parameters of each perturbed node refer to the equivalent cross-sectional parameters determined according to the perturbed core neutronics model; the measured fast group neutron flux of each perturbed node refers to the measured fast group neutron flux determined according to the perturbed core neutronics model; the measured hot group neutron flux of each perturbed node refers to the measured hot group neutron flux determined according to the perturbed core neutronics model; and the measured power of each perturbed node refers to the measured power determined according to the perturbed core neutronics model.

[0145] Step S602: Determine the second leakage curvature parameter based on the equivalent cross-sectional parameters of each perturbation node, the measured fast group neutron flux, the measured hot group neutron flux, and the measured power.

[0146] In this step, the server can determine the fast group neutron balance equation and the hot group neutron balance equation based on the equivalent cross-sectional parameters of each perturbed node obtained from the perturbed core neutronics model, the measured fast group neutron flux, the measured hot group neutron flux, and the measured power. Furthermore, the server can determine the second leakage curvature parameter based on the fast group neutron balance equation and the hot group neutron balance equation.

[0147] It should be understood that the method by which the server determines the second leakage curvature parameter can refer to the method described above for determining the first leakage curvature parameter, and will not be repeated here.

[0148] For example, the second leakage curvature parameter involved in the embodiments of this application is used to indicate the degree of leakage of fast group neutrons and hot group neutrons between nodes in a disturbed core neutronics model.

[0149] Step S603: Determine the corrected neutronics model of the disturbed core based on the second leakage curvature parameter.

[0150] For example, the modified perturbed core neutronics model involved in the embodiments of this application is used to indicate the modified perturbed core neutronics model.

[0151] In this step, the server can correct the fast group leakage correction in the perturbed fast group neutron balance equation and the hot group leakage correction in the perturbed hot group neutron balance equation according to the second leakage curvature parameter, thereby obtaining the corrected perturbed core neutronics model.

[0152] Step S604: Determine whether the corrected neutronics model of the disturbed core is correct based on the measured fast group neutron flux, measured hot group neutron flux and measured power of each disturbed node.

[0153] In this step, the server can calculate the corrected fast group neutron flux, corrected hot group neutron flux, and corrected power of each perturbation block based on the obtained corrected perturbation core neutronics model, thereby determining whether the corrected perturbation core neutronics model is correct.

[0154] In summary, in this embodiment, the server can pre-establish a perturbed core neutronics model, and determine the equivalent cross-sectional parameters of each perturbed node, measure the fast group neutron flux, measure the hot group neutron flux, and measure the power based on the perturbed core neutronics model. The server can determine the perturbed fast group neutron balance equation and the perturbed hot group neutron balance equation, thereby determining the second leakage curvature parameter. Further, the server can modify the perturbed fast group neutron balance equation and the perturbed hot group neutron balance equation based on the second leakage curvature parameter, respectively, to obtain a modified perturbed core neutronics model. Based on the obtained modified perturbed core neutronics model, the modified fast group neutron flux, modified hot group neutron flux, and modified power of each perturbed node are calculated, thereby determining whether the modified perturbed core neutronics model is correct. As can be seen, the embodiments of this application can provide predictions and assessments of the reactor core's response and performance by establishing a perturbed core neutronics model. By determining the perturbed fast group neutron balance equations and the perturbed hot group neutron balance equations, the fast group neutron flux and the hot group neutron flux can be obtained more accurately. By modifying the perturbed neutron balance equations, a modified perturbed core neutronics model can be obtained accurately, thereby improving the accuracy of model correction. Furthermore, based on the modified perturbed neutronics model, theoretical power can be calculated more accurately, and the actual situation and measurement data within the reactor core can be reflected more accurately.

[0155] In one embodiment, Figure 7 This is a flowchart illustrating a method for correcting a core neutronics model in another embodiment of this application, as shown below. Figure 7 As shown, based on the above embodiments, this application provides an exemplary description of whether the corrected perturbed core neutronics model is correctly determined in step S604 of the above embodiments based on the measured fast group neutron flux, measured hot group neutron flux, and measured power of each perturbed node. For example... Figure 7 As shown, step S604 may include step S6041 and step S6042.

[0156] Step S6041: Based on the modified neutronics model of the disturbed core, determine the modified fast group neutron flux, modified hot group neutron flux, and modified power of each disturbed node.

[0157] For example, in the embodiments of this application, the corrected fast group neutron flux of each perturbation block is used to indicate the fast group neutron flux calculated according to the corrected perturbation core neutronics model; the corrected hot group neutron flux of each perturbation block is used to indicate the hot group neutron flux calculated according to the corrected perturbation core neutronics model; and the corrected power of each perturbation block is used to indicate the corrected power calculated according to the corrected perturbation core neutronics model.

[0158] In this step, the server can determine the corrected fast group neutron flux, corrected hot group neutron flux, and corrected power of each perturbation node based on the corrected perturbation core neutronics model.

[0159] S6042, the server determines whether the corrected neutronics model of the disturbed core is correct based on the difference between the measured fast group neutron flux and the corresponding corrected fast group neutron flux of each disturbed node, the difference between the measured hot group neutron flux and the corresponding corrected hot group neutron flux of each disturbed node, and the difference between the measured power and the corresponding corrected power of each disturbed node.

[0160] In one possible implementation, if the difference between the measured fast group neutron flux of each perturbed node and the corresponding corrected fast group neutron flux is less than a first preset threshold, the difference between the measured hot group neutron flux of each perturbed node and the corresponding corrected hot group neutron flux is less than a second preset threshold, and the difference between the measured power of each perturbed node and the corresponding corrected power is less than a third preset threshold, then the corrected perturbed core neutron model is determined to be correct.

[0161] For example, the first preset threshold involved in the embodiments of this application can represent the allowable range of the difference between the measured fast group neutron flux of each perturbation block and the corresponding corrected fast group neutron flux. If the difference is less than the first preset threshold, the corrected model can be considered correct in terms of fast group neutron flux.

[0162] For example, the second preset threshold involved in the embodiments of this application can represent the allowable range of the difference between the measured hot-group neutron flux of each perturbation node and the corresponding corrected hot-group neutron flux. If the difference is less than the second preset threshold, the corrected model can be considered correct in terms of hot-group neutron flux.

[0163] For example, the third preset threshold involved in the embodiments of this application can represent the allowable range of the difference between the measured power and the corresponding corrected power of each perturbation block. If the difference is less than the third preset threshold, the corrected model can be considered correct in terms of power.

[0164] In another possible implementation, if the difference between the measured fast group neutron flux of each perturbed node and the corresponding corrected fast group neutron flux is not less than a first preset threshold, the difference between the measured hot group neutron flux of each perturbed node and the corresponding corrected hot group neutron flux is not less than a second preset threshold, or the difference between the measured power of each perturbed node and the corresponding corrected power is not less than a third preset threshold, then the corrected perturbed core neutronics model is determined to be incorrect.

[0165] For example, the difference between the measured fast group neutron flux of each perturbation block and the corresponding modified fast group neutron flux is less than a first preset threshold, which can be expressed as:

[0166]

[0167] in, The corrected fast group neutron flux for each perturbation node; The measured fast group neutron flux for each perturbation node; This is the first preset threshold.

[0168] It should be understood that, for each perturbation block, the maximum value of the difference between the measured fast group neutron flux and the corrected fast group neutron flux is selected as the difference between the measured fast group neutron flux and the corrected fast group neutron flux of the perturbation block.

[0169] Of course, formula (8) can also be expressed as other variations or equivalent formulas of the above formula (8).

[0170] For example, the difference between the measured hot group neutron flux of each perturbation node and the corresponding corrected hot group neutron flux is less than a second preset threshold, which can be expressed as:

[0171]

[0172] in, The corrected heat group neutron flux for each perturbation node; The measured neutron flux of the thermal cluster for each perturbation node; This is the second preset threshold.

[0173] It should be understood that, for each perturbation block, the maximum value of the difference between the measured hot group neutron flux and the corrected hot group neutron flux is selected as the difference between the measured hot group neutron flux and the corrected hot group neutron flux of the perturbation block.

[0174] Of course, formula (9) can also be expressed as other variations or equivalent formulas of the above formula (9).

[0175] For example, the difference between the measured power and the corresponding corrected power of each perturbation node is less than a third preset threshold, which can be expressed as:

[0176] max(|P R -P M |)<ε P (10)

[0177] Among them, P R P represents the correction power for each disturbance node. M The measured power of each disturbance node; ε P This is the third preset threshold.

[0178] It should be understood that, for each perturbation block, the maximum value among the differences between the measured power of the perturbation and the corresponding corrected power is selected as the difference between the measured power and the corresponding corrected power of each perturbation block.

[0179] Of course, formula (10) can also be expressed as other variations or equivalent formulas of the above formula (10).

[0180] In summary, the server can determine the corrected fast group neutron flux, corrected hot group neutron flux, and corrected power of each perturbed node based on the corrected perturbed core neutronics model. Furthermore, the server can determine the correctness of the corrected perturbed core neutronics model based on the differences between the measured fast group neutron flux and the corresponding corrected fast group neutron flux of each perturbed node, the differences between the measured hot group neutron flux and the corresponding corrected hot group neutron flux of each perturbed node, and the differences between the measured power and the corresponding corrected power of each perturbed node. Therefore, in this embodiment, by using the corrected perturbed core neutronics model, the server can accurately calculate the corrected fast group neutron flux and the corrected hot group neutron flux of each perturbed node, and the corrected neutron flux will more accurately reflect the neutron distribution in the actual core. Furthermore, by comparing with three preset thresholds, if the differences are all less than their respective preset thresholds, the corrected model can be considered correct, thereby improving the accuracy of model correction.

[0181] In one embodiment, Figure 8 This is a flowchart illustrating a method for correcting a core neutronics model in another embodiment of this application. Based on the above embodiment, the method for correcting a core neutronics model in this embodiment may further include the following steps.

[0182] S801. Determine the theoretical fast group neutron flux, theoretical hot group neutron flux, and theoretical power of each segment of the target core based on the modified core neutronics model.

[0183] In this embodiment of the application, the server can recalculate the theoretical fast group neutron flux, theoretical hot group neutron flux, and theoretical power of each segment of the target core based on the modified core neutronics model.

[0184] Thus, through the above implementation method, the server can more accurately calculate the theoretical fast group neutron flux, theoretical hot group neutron flux and theoretical power of each segment based on the modified core neutronics model, which is beneficial for more accurate monitoring of nuclear reactions in the core.

[0185] It should be understood that although the steps in the flowcharts of the above embodiments are shown sequentially according to the arrows, these steps are not necessarily executed in the order indicated by the arrows. Unless explicitly stated herein, there is no strict order restriction on the execution of these steps, and they can be executed in other orders. Moreover, at least some steps in the flowcharts of the above embodiments may include multiple steps or multiple stages. These steps or stages are not necessarily completed at the same time, but can be executed at different times. The execution order of these steps or stages is not necessarily sequential, but can be performed alternately or in turn with other steps or at least some of the steps or stages of other steps.

[0186] Based on the same inventive concept, this application also provides a core neutronics model correction apparatus for implementing the above-described core neutronics model correction method. The solution provided by this apparatus is similar to the implementation described in the above-described method. Therefore, the specific limitations in one or more core neutronics model correction apparatus embodiments provided below can be found in the limitations of the core neutronics model correction method described above, and will not be repeated here.

[0187] In one embodiment, Figure 9 This is a schematic diagram of a core neutronics model correction device in one embodiment of this application. The core neutronics model correction device provided in this embodiment can be applied to computer equipment. Figure 9 As shown, the core neutronics model correction device of this application embodiment includes: a first determining module 10, a second determining module 11, and a third determining module 12, wherein:

[0188] The first determining module 10 is used to determine the measured fast group neutron flux and the measured hot group neutron flux of each segment of the target core based on the core neutronics model before modification and the measured power of the target core.

[0189] The second determining module 11 is used to determine the equivalent cross-sectional parameters of each segment based on the state parameters of each segment.

[0190] The third determining module 12 is used to determine the modified core neutronics model based on the measured fast group neutron flux, measured hot group neutron flux, and equivalent cross-sectional parameters of each segment.

[0191] The core neutronics model correction device provided in this embodiment can execute the above method embodiment, and its implementation principle and technical effect are similar, so it will not be described again here.

[0192] In one embodiment, the third determining module 12 includes: a first determining unit and a second determining unit, wherein:

[0193] The first determining unit, for each segment, is used to determine the first leakage curvature parameter based on the measured fast group neutron flux, the measured hot group neutron flux, and the equivalent cross-sectional parameters of the segment.

[0194] The second determining unit is used to determine the modified core neutronics model based on the first leakage curvature parameter.

[0195] The core neutronics model correction device provided in this embodiment can execute the above method embodiment, and its implementation principle and technical effect are similar, so it will not be described again here.

[0196] In one embodiment, the first determining unit is specifically used for:

[0197] Based on the measured fast group neutron flux, measured hot group neutron flux, equivalent cross-sectional parameters, and fast group leakage correction of the nodal, the fast group neutron equilibrium equation is determined, wherein the fast group leakage correction includes the first leakage curvature parameter.

[0198] Based on the measured fast group neutron flux, measured hot group neutron flux, equivalent cross-sectional parameters, and hot group leakage correction of the nodal, the hot group neutron balance equation is determined, wherein the hot group leakage correction includes the first leakage curvature parameter.

[0199] The first leakage curvature parameter is determined based on the fast group neutron balance equation and the hot group neutron balance equation.

[0200] The core neutronics model correction device provided in this embodiment can execute the above method embodiment, and its implementation principle and technical effect are similar, so it will not be described again here.

[0201] In one embodiment, the second determining unit is specifically used for:

[0202] The fast group neutron balance equation and the hot group neutron balance equation are modified according to the first leakage curvature parameter to obtain the modified core neutronics model.

[0203] In one embodiment, the second determining module 11 is specifically used for:

[0204] For each segment, multiple state parameters corresponding to the segment are determined based on a preset set of state parameters; and the equivalent cross-sectional parameters of the segment are determined based on the multiple state parameters using a preset interpolation algorithm.

[0205] The core neutronics model correction device provided in this embodiment can execute the above method embodiment, and its implementation principle and technical effect are similar, so it will not be described again here.

[0206] In one embodiment, the first determining module 10 is specifically used for:

[0207] For each node, the theoretical fast group neutron flux, theoretical hot group neutron flux, fast group macroscopic energy production cross section, and hot group macroscopic energy production cross section of the node are determined based on the original core neutronics model.

[0208] Based on the theoretical fast group neutron flux, the theoretical hot group neutron flux, the measured power, the macroscopic energy production cross section of the fast group, and the macroscopic energy production cross section of the hot group of the nodal, the measured fast group neutron flux and the measured hot group neutron flux of the nodal are determined.

[0209] The core neutronics model correction device provided in this embodiment can execute the above method embodiment, and its implementation principle and technical effect are similar, so it will not be described again here.

[0210] In one embodiment, the correction device for the core neutronics model further includes: a fourth determination module, a fifth determination module, a sixth determination module, and a seventh determination module.

[0211] The fourth determination module is used to determine the equivalent cross-sectional parameters of each perturbation node, measure the fast group neutron flux, measure the hot group neutron flux, and measure the power based on the perturbation core neutronics model.

[0212] The fifth determining module is used to determine the second leakage curvature parameter based on the equivalent cross-sectional parameters of each perturbation node, the measured fast group neutron flux, the measured hot group neutron flux, and the measured power.

[0213] The sixth determination module is used to determine the corrected neutronics model of the disturbed core based on the second leakage curvature parameter;

[0214] The seventh determination module is used to determine whether the corrected neutronics model of the disturbed core is correct based on the measured fast group neutron flux, measured hot group neutron flux and measured power of each disturbed node.

[0215] The core neutronics model correction device provided in this embodiment can execute the above method embodiment, and its implementation principle and technical effect are similar, so it will not be described again here.

[0216] In one embodiment, the seventh determining module includes a third determining unit and a fourth determining unit.

[0217] The third determining unit is used to determine the corrected fast group neutron flux, corrected hot group neutron flux and corrected power of each perturbation block based on the corrected perturbation core neutronics model.

[0218] The fourth determining unit is used to determine whether the corrected neutronics model of the disturbed core is correct based on the difference between the measured fast group neutron flux and the corresponding corrected fast group neutron flux of each disturbed node, the difference between the measured hot group neutron flux and the corresponding corrected hot group neutron flux of each disturbed node, and the difference between the measured power and the corresponding corrected power of each disturbed node.

[0219] The core neutronics model correction device provided in this embodiment can execute the above method embodiment, and its implementation principle and technical effect are similar, so it will not be described again here.

[0220] In one embodiment, the fourth determining unit is specifically used for:

[0221] If the difference between the measured fast group neutron flux of each perturbed node and the corresponding corrected fast group neutron flux is less than a first preset threshold, the difference between the measured hot group neutron flux of each perturbed node and the corresponding corrected hot group neutron flux is less than a second preset threshold, and the difference between the measured power of each perturbed node and the corresponding corrected power is less than a third preset threshold, then the corrected perturbed core neutron model is determined to be correct.

[0222] The core neutronics model correction device provided in this embodiment can execute the above method embodiment, and its implementation principle and technical effect are similar, so it will not be described again here.

[0223] In one embodiment, the correction device for the above-mentioned core neutronics model further includes:

[0224] The eighth determination module is used to determine the theoretical fast group neutron flux, theoretical hot group neutron flux, and theoretical power of each segment of the target core based on the modified core neutronics model.

[0225] The core neutronics model correction device provided in this embodiment can execute the above method embodiment, and its implementation principle and technical effect are similar, so it will not be described again here.

[0226] Each module in the aforementioned core neutronics model correction device can be implemented entirely or partially through software, hardware, or a combination thereof. These modules can be embedded in hardware within or independently of the processor in a computer device, or stored in software within the memory of a computer device, so that the processor can invoke and execute the operations corresponding to each module.

[0227] In one exemplary embodiment, a computer device is provided, which may be a server, and its internal structure diagram may be as follows: Figure 10 As shown, this computer device may include a processor, memory, input / output (I / O) interfaces, and a communication interface. The processor, memory, and I / O interfaces are connected via a system bus, and the communication interface is also connected to the system bus via the I / O interfaces. The processor provides computational and control capabilities. The memory includes non-volatile storage media and internal memory. The non-volatile storage media stores the operating system, computer programs, and a database. The internal memory provides the environment for the operating system and computer programs stored in the non-volatile storage media to run. The I / O interfaces are used for exchanging information between the processor and external devices. The communication interface is used for communicating with external terminals via a network connection. When the computer program is executed by the processor, it implements a method for correcting a reactor core neutronics model.

[0228] Those skilled in the art will understand that Figure 10 The structure shown is merely a block diagram of a portion of the structure related to the present application and does not constitute a limitation on the computer device to which the present application is applied. Specific computer devices may include more or fewer components than those shown in the figure, or combine certain components, or have different component arrangements.

[0229] In one embodiment, a computer device is provided, including a memory and a processor. The memory stores a computer program, and when the processor executes the computer program, it implements the technical solution of the server in the above-described embodiment of the method for correcting the core neutronics model of this application. The implementation principle and technical effect are similar, and will not be repeated here.

[0230] In one embodiment, a computer-readable storage medium is provided, on which a computer program is stored. When the computer program is executed by a processor, it implements the technical solution of the server in the above-described embodiment of the method for correcting the core neutronics model of this application. Its implementation principle and technical effect are similar, and will not be repeated here.

[0231] In one embodiment, a computer program product is provided, including a computer program that, when executed by a processor, implements the technical solution regarding the server in the above-described embodiment of the method for correcting the core neutronics model of this application. The implementation principle and technical effects are similar and will not be repeated here.

[0232] Those skilled in the art will understand that all or part of the processes in the methods of the above embodiments can be implemented by a computer program instructing related hardware. The computer program can be stored in a non-volatile computer-readable storage medium. When executed, the computer program can include the processes of the embodiments of the above methods. Any references to memory, databases, or other media used in the embodiments provided in this application can include at least one of non-volatile and volatile memory. Non-volatile memory can include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical memory, high-density embedded non-volatile memory, resistive random access memory (ReRAM), magnetic random access memory (MRAM), ferroelectric random access memory (FRAM), phase change memory (PCM), graphene memory, etc. Volatile memory can include random access memory (RAM) or external cache memory, etc. By way of illustration and not limitation, RAM can take many forms, such as Static Random Access Memory (SRAM) or Dynamic Random Access Memory (DRAM). The processors involved in the embodiments provided in this application can be general-purpose processors, central processing units, graphics processing units, digital signal processors, programmable logic devices, quantum computing-based data processing logic devices, etc., and are not limited thereto.

[0233] The technical features of the above embodiments can be combined in any way. For the sake of brevity, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0234] The above embodiments are merely illustrative of several implementation methods of this application, and their descriptions are relatively specific and detailed. However, they should not be construed as limiting the scope of this application. It should be noted that those skilled in the art can make various modifications and improvements without departing from the concept of this application, and these all fall within the protection scope of this application. Therefore, the protection scope of this application should be determined by the appended claims.

Claims

1. A method for correcting a reactor core neutronics model, characterized in that, The method includes: Based on the original core neutronics model and the measured power of the target core, the measured fast group neutron flux and the measured hot group neutron flux of each segment of the target core are determined. The equivalent cross-sectional parameters of each segment are determined based on the state parameters of each segment. Based on the measured fast group neutron flux of each segment, the measured hot group neutron flux, and the equivalent cross-section parameters, the corrected core neutronics model is determined. The method further includes: The equivalent cross-sectional parameters of each perturbation node are determined based on the neutronics model of the perturbation core; the fast group neutron flux, the hot group neutron flux, and the power are measured. The second leakage curvature parameter is determined based on the equivalent cross-sectional parameters of each perturbation node, the measured fast group neutron flux, the measured hot group neutron flux, and the measured power. Based on the second leakage curvature parameter, the corrected neutronics model of the disturbed core is determined; The correctness of the modified perturbed core neutronics model is determined based on the measured fast group neutron flux, measured hot group neutron flux, and measured power of each perturbed node.

2. The method according to claim 1, characterized in that, The step of determining the modified core neutronics model based on the measured fast group neutron flux of each segment, the measured hot group neutron flux, and the equivalent cross-section parameters includes: For each segment, a first leakage curvature parameter is determined based on the measured fast group neutron flux, the measured hot group neutron flux, and the equivalent cross-sectional parameters of the segment. The corrected core neutronics model is determined based on the first leakage curvature parameter.

3. The method according to claim 2, characterized in that, The step of determining the first leakage curvature parameter based on the measured fast group neutron flux of the segment, the measured hot group neutron flux, and the equivalent cross-sectional parameter includes: Based on the measured fast group neutron flux of the nodal, the measured hot group neutron flux, the equivalent cross-section parameter, and the fast group leakage correction, the fast group neutron balance equation is determined, wherein the fast group leakage correction includes the first leakage curvature parameter. The hot group neutron balance equation is determined based on the measured fast group neutron flux of the nodal, the measured hot group neutron flux, the equivalent cross section parameter, and the hot group leakage correction, wherein the hot group leakage correction includes the first leakage curvature parameter. The first leakage curvature parameter is determined based on the fast group neutron balance equation and the hot group neutron balance equation.

4. The method according to claim 3, characterized in that, The step of determining the corrected core neutronics model based on the first leakage curvature parameter includes: The fast group neutron balance equation and the hot group neutron balance equation are modified according to the first leakage curvature parameter to obtain the modified core neutronics model.

5. The method according to any one of claims 1-4, characterized in that, The step of determining the equivalent cross-sectional parameters of each segment based on the state parameters of each segment includes: For each segment, multiple state parameters corresponding to the segment are determined according to a preset set of state parameters; The equivalent cross-sectional parameters of the segment are determined according to the multiple state parameters and a preset interpolation algorithm.

6. The method according to any one of claims 1-4, characterized in that, The measured power of the target reactor core includes the measured power of each segment of the target reactor core. The step of determining the measured fast group neutron flux and measured hot group neutron flux of each segment of the target reactor core based on the uncorrected core neutronics model and the measured power of the target reactor core includes: For each node, the theoretical fast group neutron flux, theoretical hot group neutron flux, fast group macroscopic energy production cross section, and hot group macroscopic energy production cross section of the node are determined according to the original core neutronics model. The measured fast group neutron flux and the measured hot group neutron flux of the node are determined based on the theoretical fast group neutron flux, the theoretical hot group neutron flux, the measured power, the fast group macroscopic energy generation cross section, and the hot group macroscopic energy generation cross section of the node.

7. The method according to claim 1, characterized in that, The determination of whether the corrected perturbed core neutronics model is correct based on the measured fast group neutron flux, measured hot group neutron flux, and measured power of each perturbed node includes: Based on the modified perturbed core neutronics model, the modified fast group neutron flux, modified hot group neutron flux, and modified power of each perturbed node are determined. The correctness of the corrected perturbed core neutronics model is determined based on the differences between the measured fast group neutron flux and the corresponding corrected fast group neutron flux of each perturbed node, the differences between the measured hot group neutron flux and the corresponding corrected hot group neutron flux of each perturbed node, and the differences between the measured power and the corresponding corrected power of each perturbed node.

8. The method according to claim 7, characterized in that, The step of determining whether the corrected perturbed core neutronics model is correct based on the differences between the measured fast group neutron flux and the corresponding corrected fast group neutron flux of each perturbed node, the differences between the measured hot group neutron flux and the corresponding corrected hot group neutron flux of each perturbed node, and the differences between the measured power and the corresponding corrected power of each perturbed node includes: If the difference between the measured fast group neutron flux and the corresponding corrected fast group neutron flux of each perturbed node is less than a first preset threshold, the difference between the measured hot group neutron flux and the corresponding corrected hot group neutron flux of each perturbed node is less than a second preset threshold, and the difference between the measured power and the corresponding corrected power of each perturbed node is less than a third preset threshold, then the corrected perturbed core neutron model is determined to be correct.

9. The method according to any one of claims 1-4, characterized in that, The method further includes: The theoretical fast group neutron flux, theoretical hot group neutron flux, and theoretical power of each segment of the target core are determined based on the modified core neutronics model.

10. A core neutronics model correction apparatus, used to execute the core neutronics model correction method according to any one of claims 1-9, characterized in that, The device includes: The first determining module is used to determine the measured fast group neutron flux and the measured hot group neutron flux of each segment of the target core based on the core neutronics model before modification and the measured power of the target core. The second determining module is used to determine the equivalent cross-sectional parameters of each segment based on the state parameters of each segment. The third determining module is used to determine the corrected core neutronics model based on the measured fast group neutron flux of each segment, the measured hot group neutron flux, and the equivalent cross-section parameters.

11. A computer device, comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, 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 9.

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

13. A computer program product, comprising a computer program, characterized in that, When executed by a processor, the computer program implements the steps of the method according to any one of claims 1 to 9.

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