Cross section generation method and equipment based on flux moment homogenization and transport correction coupling, and storage medium
By performing Monte Carlo transport calculations and transport correction coupling in reactor components, high-precision multi-group cross sections are generated, which solves the problem of insufficient calculation accuracy of the total cross section in anisotropic problems and realizes efficient and compatible cross section data processing.
Patent Information
- Application Number
- CN202511865088.8
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-12-11
- Publication Date
- 2026-03-17
AI Technical Summary
Existing technologies cannot effectively address the insufficient computational accuracy of total cross-sections in anisotropic problems, and the data structures of high-order cross-sections are complex and computationally expensive, making them incompatible with mainstream reactor core computation programs.
Monte Carlo transport calculations were performed by establishing a geometric model of the reactor components. The flux moments and total reaction rate moments of each order of spherical harmonic functions were extracted. Combined with transport correction methods, high-precision multi-group cross sections were generated to achieve accurate characterization and compensation of the correlation of total cross section angles.
The generated multi-group cross sections exhibit high accuracy and compatibility in strongly anisotropic problems, and can be directly applied to mainstream reactor core calculation programs, reducing computational costs and improving computational efficiency.
Smart Images
Figure CN121683252A_ABST
Abstract
Description
TECHNICAL FIELD
[0001] The present application relates to the technical field of neutron transport numerical calculation, and in particular to a cross section generation method, device and storage medium based on flux moment homogenization and transport correction coupling. BACKGROUND
[0002] In reactor physics numerical calculation, two-step method is the mainstream calculation scheme in engineering design. The scheme firstly performs fine neutron transport calculation at local scale such as grid cell or assembly to generate macroscopic multi-group cross section; and then uses the cross section data for global calculation at reactor core scale to obtain key physical parameters such as power distribution, reactivity and the like. Therefore, generating macroscopic multi-group cross section which is both accurate and efficient is the basis for ensuring the accuracy of the entire core design.
[0003] To reduce the calculation cost of core-scale calculation, macroscopic multi-group cross section (referred to as cross section) in the form of zero-order Legendre expansion is usually used. The cross section only contains isotropic information, and discards all data related to neutron angle. This simplification is still acceptable in traditional large-scale light water reactors where neutron flux angle distribution is approximately isotropic, but in new-type reactors (such as small modular reactors, traveling wave reactors) or complex assemblies with strong absorbers and strong reflectors, neutron transport exhibits strong anisotropy. At this time, the use of cross section will introduce significant calculation errors. To improve the accuracy of
[0004] cross section in anisotropic problems, the industry widely uses the “transport correction” method. This method modifies the anisotropic part of the scattering cross section into the total cross section, so that the isotropic cross section is approximated to a linear anisotropic cross section. However, the traditional transport correction mainly deals with the anisotropy of the scattering cross section, and fails to fully consider that the total cross section itself also has angle dependence. In the strong anisotropic scenario, this limitation limits the correction effect. To directly correct the anisotropy of the total cross section, the “flux moment homogenization” technology is proposed. This technology uses the angle-dependent flux moment as the weight to derive high-order total cross section correction terms, thereby significantly improving the calculation accuracy in strong anisotropic problems (such as strong absorption materials, strong reflectors). However, the MHT technology generates cross section data in high-order form, which has complex data structure and high calculation cost. More importantly, it cannot be directly applied to mainstream core calculation programs that only support
[0005] cross section input. Although some advanced programs have supported high-order cross section, their calculation efficiency is low and stability needs to be verified, which is difficult to meet the practical needs of engineering design.
[0006] In summary, existing technologies present a contradiction: traditional transport correction methods cannot effectively handle total cross-sectional anisotropy, while flux angular homogenization techniques, although capable of addressing total cross-sectional anisotropy, produce higher-order cross-sections that are not readily compatible with widely used and efficient methods. The cross-section core solver is incompatible. Currently, there is a lack of a method that can efficiently and accurately "compress" or "integrate" the anisotropic information of the total cross-section into the standard. The method in the section format significantly improves computational efficiency and program compatibility while ensuring computational efficiency. The calculation accuracy of cross sections in strongly anisotropic problems. Summary of the Invention
[0007] The purpose of this invention is to overcome the shortcomings of existing technologies and provide a cross-section generation method based on the coupling of flux moment homogenization and transport correction, comprising the following steps: S1: Establish a geometric model of the target reactor assembly or cell, determine the statistical region and statistical parameter types within the target geometric model, perform continuous energy Monte Carlo transport calculations on the target geometric model, and generate conventional [processes / methods] based on the neutron flux and reaction rate data obtained from the Monte Carlo transport calculations. Cross-sectional data; S2: Based on the statistical data from the Monte Carlo transport calculations, extract the flux moments and total reaction rate moments of each order of spherical harmonic functions, and calculate the total cross-sectional spherical harmonic function correction term using the flux moments and total reaction rate moments of each order of spherical harmonic functions. Introduce the total cross-sectional spherical harmonic function correction term into the conventional... The conventional scattering cross section in the cross section data is used to complete the flux moment homogenization correction; S3: Based on the statistical data, derive the first-order scattering matrix. Use a transport correction method to process the total cross section and the first-order scattering matrix to obtain the transport correction term. Then, based on the transport correction term and the total cross section spherical harmonic function correction term, adjust the conventional... The cross-sectional data is corrected to generate the final multi-group cross-section.
[0008] Preferably, in step S3, the transport correction method is used to process the total cross section and the first-order scattering matrix to obtain the transport correction term, including: Based on the k-th statistical region, and from the incident energy group First-order scattering cross section scattered into the outgoing energy group G and the neutron flux of each energy group and The transport correction terms for the k-th region and the G-th energy group are calculated using the internal scattering approximation formula. As shown below: .
[0009] Preferably, in step S3, the conventional method is adjusted according to the transport correction term and the total cross-section spherical harmonic function correction term. The cross-sectional data was corrected, including: According to the conventional total scattering cross section The transport correction term With the total cross-section spherical harmonic function correction term The comprehensive correction term was calculated. The calculation formula is as follows: ; According to the aforementioned comprehensive correction item For the conventional total cross section After making corrections, the corrected total cross-section is obtained. ; According to the transport correction item For the regular Zero-order scattering cross section After correction, the corrected zero-order scattering cross section is obtained. .
[0010] Preferably, according to the comprehensive correction term For the conventional total cross section After making corrections, the corrected total cross-section is obtained. ,include:
[0011] Preferably, according to the comprehensive correction term For the regular Zero-order scattering cross section After correction, the corrected zero-order scattering cross section is obtained. ,include: ,in, For Dirac delta function, Let E be the energy corresponding to the incident energy group, and let E' be the energy corresponding to the exit energy group G, if and only if E' = E. Otherwise, it is 0.
[0012] Preferably, in step S1, the generation of conventional Cross-sectional data, including: Based on the statistical results of Monte Carlo transport calculations, the neutron flux of the k-th statistical region and the G-th energy group is extracted. And the reaction rate of type x in the k-th statistical region and the G-th energy group. Among them, type x reactions include total reactions, absorption reactions, and fission reactions; Based on the neutron flux and the reaction rate of type x Calculate the x-type macroscopic cross section of the k-th statistical region and the G-th energy group. The calculation formula is as follows: ,in, Let x be a continuous energy cross section of type x at position r and energy E. The continuous energy seed flux at position r and energy E, the x-type macroscopic cross section includes the total cross section, the absorption cross section and the fission cross section; Extract the k-th statistical region, the Scattering reactivity of energy group And from the energy groups, statistically derived from continuous energy data. The transition probability of scattering to energy group G ; Based on the scattering reaction rate The transition probability and the Neutron flux of energy group Calculate the statistical region from the kth statistical region. Macroscopic scattering cross section from energy group to the Gth energy group As shown below; ,in, Let R be the continuous energy scattering cross section at position r and energy E. From energy at position r The probability distribution function of scattering to energy E.
[0013] Preferably, in step S2, the extraction of flux moments and total reaction rate moments of each order spherical harmonic function, and the calculation of the total cross-sectional spherical harmonic function correction term using the flux moments and total reaction rate moments of each order spherical harmonic function, includes: Based on the statistical results of continuous energy Monte Carlo transport calculations, the flux moments of the k-th region, the G-th energy group, and the m-th term of the l-th order spherical harmonic function are directly extracted. and the corresponding total reaction rate moment ; The flux moments of the spherical harmonic functions corresponding to all terms m under the same order l With the total reaction rate moment After processing, the l-th order total cross-section spherical harmonic function correction term for the k-th statistical region and the G-th energy group is obtained. The calculation formula is as follows:
[0014] Preferably, in step S2, the total cross-sectional spherical harmonic function correction term is introduced into the conventional... The typical scattering cross section in the cross-sectional data includes: Calculate the l-th order total cross-sectional spherical harmonic function correction term for the k-th statistical region and the G-th energy group. Compared with the conventional total scattering cross section The difference is used to obtain the cross-sectional difference; The cross-sectional difference is applied to the k-th region using the Dirac delta function, from the incident energy group. The l-th order original scattering cross section scattered into the outgoing energy group G The above is used to update and obtain the corrected first-order higher-order scattering cross section. As shown below: ,in, Indicates the conventional The k-th region and energy group in the cross-sectional data To the l-th order primitive scattering cross section of energy group G, It is a Dirac delta function if and only if g = Its value is 1 if it is true, otherwise it is 0.
[0015] Based on the same concept, the present invention also provides a computer device, including a memory and one or more processors, wherein the memory stores computer code, and when the computer code is executed by the one or more processors, the one or more processors perform a cross-section generation method based on flux moment homogenization and transport correction coupling as described in any one of the embodiments.
[0016] Based on the same concept, the present invention also provides a storage medium storing computer-readable instructions, characterized in that, when the computer-readable instructions are executed by one or more processors, the one or more processors cause the one or more processors to perform the steps of a cross-section generation method based on flux moment homogenization and transport correction coupling as described in any one of the embodiments.
[0017] Compared with the prior art, the beneficial effects of the present invention are: This invention generates conventional reactors by establishing a geometric model of the target reactor assembly or cell and performing continuous energy Monte Carlo transport calculations, based on statistically obtained high-precision neutron flux and reaction rate data. Cross-sectional data achieves high fidelity in the initial stage of cross-section generation. The Monte Carlo method avoids the errors introduced by the approximation of indistinguishable resonance regions in deterministic methods and can accurately handle complex geometries, thus providing a reliable benchmark data foundation for subsequent corrections. This invention extracts the flux moments and total reactivity moments of each order of spherical harmonic functions based on Monte Carlo statistical data, calculates the correction term for the total cross-section spherical harmonic function accordingly, and then introduces it into a conventional scattering cross-section to complete the flux moment homogenization correction, achieving accurate characterization and compensation for the angular correlation of the total cross-section. It overcomes the inherent limitation of traditional transport correction methods that only handle the anisotropy of the scattering cross-section while ignoring the anisotropy of the total cross-section, significantly improving the physical completeness of cross-section data in strongly anisotropic problems (such as strongly absorbing materials and strongly reflective layers). This invention derives a transport correction term by deriving a first-order scattering matrix and performing transport corrections. This transport correction term is then coupled with the aforementioned total cross-section spherical harmonic function correction term to jointly address conventional... The cross-sectional data is systematically corrected to ultimately generate a novel multi-group cross-section. This coupled innovation achieves two core advantages: First, it deeply integrates the traditional transport correction's ability to handle scattering anisotropy with the flux moment homogenization's ability to handle overall cross-sectional anisotropy, producing a synergistic correction effect that makes the generated cross-section more robust. The formatted cross-section essentially contains the accuracy information of higher-order cross-sections; secondly, the final output cross-section maintains the standard. The data structure and interface of the cross-section are directly compatible with widely used interfaces that only support... The input of various high-efficiency core calculation programs fundamentally solves the problem in strongly anisotropic scenarios without sacrificing computational efficiency and engineering applicability. This solution addresses the industry challenge of insufficient accuracy in cross-section calculations and features high precision, high compatibility, and low cost. Attached Figure Description
[0018] Various other advantages and benefits will become apparent to those skilled in the art upon reading the following detailed description of preferred embodiments. The accompanying drawings are for illustrative purposes only and are not intended to limit the invention.
[0019] Figure 1 This is a flowchart of the cross-section generation method based on the coupling of flux moment homogenization and transport correction according to the present invention; Figure 2 This is another flowchart of the cross-section generation method based on the coupling of flux moment homogenization and transport correction of the present invention. Detailed Implementation
[0020] To make the objectives, technical solutions, and advantages of this invention clearer, the invention will be further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention. Obviously, the described embodiments are only some, not all, of the embodiments described in this application. All other embodiments obtained by those skilled in the art based on the embodiments in this application without creative effort are within the scope of protection of this application.
[0021] Those skilled in the art will understand that, unless otherwise stated, the singular forms “a” and “an” used herein, and “the”, may also include the plural forms. It should be further understood that the term “comprising” as used in this specification means the presence of the stated features, integers, steps, operations, elements, and / or components, but does not exclude the presence or addition of one or more other features, integers, steps, operations, elements, components, and / or groups thereof.
[0022] First Embodiment Please see Figure 1 and Figure 2 As shown, this embodiment provides a cross-section generation method based on the coupling of flux moment homogenization and transport correction, which includes the following steps: S1: Establish a geometric model of the target reactor assembly or cell, determine the statistical region and statistical parameter types within the target geometric model, perform continuous energy Monte Carlo transport calculations on the target geometric model, and generate conventional [processes / methods] based on the neutron flux and reaction rate data obtained from the Monte Carlo transport calculations. Specifically, in this embodiment, the geometric model is constructed using a solid geometry method, with material type as the standard for dividing the statistical region. The statistical parameter types include neutron flux, various reaction rates, neutron scattering energy group transfer probability, higher-order spherical harmonic function reaction rate and higher-order scattering reaction rate. The reaction rate types include absorption reaction rate, scattering reaction rate, fission reaction rate, total reaction rate, and spallation reaction matrix.
[0023] Preferably, in step S1, a conventional method is generated. Cross-sectional data, including: Based on the statistical results of Monte Carlo transport calculations, the neutron flux of the k-th statistical region and the G-th energy group is extracted. And the reaction rate of type x in the k-th statistical region and the G-th energy group. Among them, type x reactions include total reactions, absorption reactions, and fission reactions; Based on neutron flux and type x reaction rate Calculate the x-type macroscopic cross section of the k-th statistical region and the G-th energy group. The calculation formula is as follows: ,in, Let x be a continuous energy cross section of type x at position r and energy E. The continuous energy seed flux at position r and energy E is given. The macroscopic cross section of type x includes the total cross section, the absorption cross section, and the fission cross section. Specifically, in this embodiment, the calculation principle is derived from the conservation of reaction rate. Extract the k-th statistical region, the Scattering reactivity of energy group And from the energy groups, statistically derived from continuous energy data. The transition probability of scattering to energy group G ; Based on scattering reaction rate Transition probability and the Neutron flux of energy group Calculate the statistical region from the kth statistical region. Macroscopic scattering cross section from energy group to the Gth energy group As shown below; ,in, Let R be the continuous energy scattering cross section at position r and energy E. From energy at position r The probability distribution function of scattering to energy E.
[0024] S2: Based on statistical data from Monte Carlo transport calculations, the flux moments and total reaction rate moments of each order of spherical harmonic functions are extracted. The total cross-sectional spherical harmonic function correction term is then calculated using these parameters and introduced into the conventional... The conventional scattering cross section in the cross section data is used to complete the flux moment homogenization correction.
[0025] Preferably, in step S2, the flux moments and total reaction rate moments of each order spherical harmonic function are extracted, and the total cross-sectional spherical harmonic function correction term is calculated using the flux moments and total reaction rate moments of each order spherical harmonic function, including: Based on the statistical results of continuous energy Monte Carlo transport calculations, the flux moments of the k-th region, the G-th energy group, and the m-th term of the l-th order spherical harmonic function are directly extracted. and the corresponding total reaction rate moment ; Flux moments of spherical harmonic functions with all terms m corresponding to the same order l With the total reaction rate moment After processing, the l-th order total cross-section spherical harmonic function correction term for the k-th statistical region and the G-th energy group is obtained. The calculation formula is as follows:
[0026] Preferably, in step S2, the total cross-section spherical harmonic function correction term is introduced into the conventional... The typical scattering cross section in the cross-sectional data includes: Calculate the l-th order total cross-sectional spherical harmonic function correction term for the k-th statistical region and the G-th energy group. Compared with the conventional total scattering cross section The difference is used to obtain the cross-sectional difference; The cross-sectional difference is applied to the k-th region via the Dirac delta function, from the incident energy group. The l-th order original scattering cross section scattered into the outgoing energy group G The above is used to update and obtain the corrected first-order higher-order scattering cross section. As shown below: ,in, Indicates regular The k-th region and energy group in the cross-sectional data To the l-th order primitive scattering cross section of energy group G, It is a Dirac delta function if and only if g = Its value is 1 if it is true, otherwise it is 0.
[0027] S3: Based on statistical data, the first-order scattering matrix is derived. A transport correction method is used to process the total cross section and the first-order scattering matrix to obtain the transport correction term. Based on the transport correction term and the total cross section spherical harmonic function correction term, the conventional... The cross-sectional data is corrected to generate the final multi-group cross-section.
[0028] More preferably, calculate the correction term at position r and energy E. As shown below:
[0029] Based on the correction term The total cross section at position r and energy E is corrected to obtain the corrected total cross section. As shown below: According to the revision Correcting position r, energy from The 0th order scattering cross section to E is corrected to obtain the 0th order scattering cross section. ; Specifically, in this embodiment, To correct the value at position r, the energy is changed from... The 0th order scattering cross section to E.
[0030] Preferably, in step S3, a transport correction method is used to process the total cross section and the first-order scattering matrix to obtain a transport correction term, including: Based on the k-th statistical region, and from the incident energy group First-order scattering cross section scattered into the outgoing energy group G and the neutron flux of each energy group and The transport correction terms for the k-th region and the G-th energy group are calculated using the internal scattering approximation formula. As shown below: Specifically, in this embodiment, the correction item is... Discretization of the formula for transport correction terms formula.
[0031] Preferably, in step S3, the conventional method is adjusted based on the transport correction term and the total cross-section spherical harmonic function correction term. The cross-sectional data was corrected, including: According to the conventional total scattering cross section Transport Correction Items With the total cross-section spherical harmonic function correction term The comprehensive correction term was calculated. The calculation formula is as follows: ; According to the comprehensive correction item For conventional total cross-section After making corrections, the corrected total cross-section is obtained. ; According to the transport correction For the regular Zero-order scattering cross section After correction, the corrected zero-order scattering cross section is obtained. Specifically, in this embodiment, the modified multi-group cross section is a high-precision, highly adaptable, and low-cost multi-group cross section.
[0032] Preferably, based on the comprehensive correction term For conventional total cross-section After making corrections, the corrected total cross-section is obtained. ,include:
[0033] Preferably, based on the comprehensive correction term For the regular Zero-order scattering cross section After correction, the corrected zero-order scattering cross section is obtained. ,include: ,in, For Dirac delta function, Let E be the energy corresponding to the incident energy group, and let E' be the energy corresponding to the exit energy group G, if and only if E' = E. Otherwise, it is 0.
[0034] Second Embodiment Based on the same concept, the present invention also provides a computer device, including a memory and one or more processors, wherein the memory stores computer code, and when the computer code is executed by one or more processors, the one or more processors cause the one or more processors to perform the steps of a cross-section generation method based on flux moment homogenization and transport correction coupling in the first embodiment.
[0035] Based on the same concept, the present invention also provides a storage medium storing computer-readable instructions, characterized in that, when the computer-readable instructions are executed by one or more processors, the one or more processors cause the one or more processors to perform the steps of a cross-section generation method based on flux moment homogenization and transport correction coupling as described in any one of the embodiments.
[0036] It is understood that, for the aforementioned cross-section generation method based on the coupling of flux moment homogenization and transport correction, if all of these are implemented as software functional modules and sold or used as independent products, they can be stored in a computer-readable storage medium. Based on this understanding, the technical solution of this invention, in essence, or the part that contributes to the prior art, or all or part of the technical solution, can be embodied in the form of a software product. This computer software product is stored in a storage medium and includes several instructions to cause a computer device (which may be a personal computer server or a network device, etc.) to execute all or part of the steps of the methods of the various embodiments of this invention. The aforementioned storage medium includes: USB flash drives, portable hard drives, read-only memory (ROM), random access memory (RAM), magnetic disks, optical disks, and other media capable of storing program code.
[0037] Computer-readable storage media may include data signals propagated in baseband or as part of a carrier wave, carrying readable program code. Such propagated data signals may take various forms, including but not limited to electromagnetic signals, optical signals, or any suitable combination thereof. A readable storage medium may also be any readable medium other than a readable storage medium that can transmit, propagate, or transfer a program for use by or in connection with an instruction execution system, apparatus, or device. The program code contained on the readable storage medium may be transmitted using any suitable medium, including but not limited to wireless, wired, optical fiber, RF, etc., or any suitable combination thereof.
[0038] The above description is merely a preferred embodiment of the present invention. The scope of protection of the present invention is not limited to the above embodiments. All technical solutions falling within the scope of the present invention's concept are within the scope of protection of the present invention. It should be noted that for those skilled in the art, any improvements and modifications made without departing from the principles of the present invention should also be considered within the scope of protection of the present invention.
Claims
1. A cross section generation method based on flux moment homogenization coupled with transport correction, characterized in that, The method comprises the following steps: S1: establishing a geometric model of a target reactor assembly or cell, determining a statistical region and a statistical parameter type inside the target geometric model, performing a continuous-energy Monte Carlo transport calculation on the target geometric model, generating conventional cross-section data based on neutron flux and reaction rate data statistically obtained from the Monte Carlo transport calculation cross-section data; S2: based on the statistical data of the Monte Carlo transport calculation, extracting each order spherical harmonic flux moment and total reaction rate moment, and calculating a total cross section spherical harmonic correction term through the each order spherical harmonic flux moment and the total reaction rate moment, introducing the total cross section spherical harmonic correction term into the conventional cross section data to complete the flux moment homogenization correction; S3: based on the statistical data, deriving a first-order scattering matrix, processing the total cross section and the first-order scattering matrix by using a transport correction method to obtain a transport correction term, and correcting the conventional cross section data according to the transport correction term and the total cross section spherical harmonic function correction term to generate a final multigroup cross section. cross section data to generate a final multigroup cross section.
2. The cross section generation method based on flux moment homogenization coupled with transport correction according to claim 1, characterized in that, In step S3, the total cross section and the first-order scattering matrix are processed by using the transport correction method to obtain a transport correction term, which comprises: Based on the kth statistical region, the first-order scattering cross section of the incident energy group scattered to the outgoing energy group G , and the neutron flux of each energy group and , the transport correction term of the kth region and the Gth energy group is calculated by the internal scattering approximation formula as follows: 。 3. The cross section generation method based on flux moment homogenization coupled with transport correction according to claim 2, characterized in that, In step S3, the conventional cross-section data is corrected according to the transport correction term and the total cross-section spherical harmonic function correction term, including: cross-section data is corrected according to the transport correction term and the total cross-section spherical harmonic function correction term, including: According to the conventional scattering total cross section , the transport correction term and the total cross section spherical harmonic function correction term , the comprehensive correction term is calculated , and the calculation formula is as follows: ； According to the comprehensive correction term The conventional total cross section Is corrected to obtain a corrected total cross section ; According to the transport correction term To the conventional Zero-order scattering cross section The modified zero-order scattering cross section is obtained by correcting .
4. The cross section generation method based on flux moment homogenization coupled with transport correction according to claim 3, characterized in that, According to the comprehensive correction term The conventional total cross section The modified total cross section , comprising: 。 5. The cross section generation method based on flux moment uniformization coupled with transport correction according to claim 3, characterized in that, According to the comprehensive correction term To the conventional Zero-order scattering cross section The zero-order scattering cross section is corrected to obtain a corrected zero-order scattering cross section , comprising: ， wherein is the Dirac delta function, is the energy corresponding to the incident energy group, E is the energy corresponding to the exit energy group G, and , otherwise 0.
6. The cross section generation method based on flux moment uniformization coupled with transport correction according to claim 1, wherein, In step S1, the generation of the regular cross-sectional data, comprising: According to the statistical result of the Monte Carlo transport calculation, the neutron flux of the kth statistical region and the Gth energy group is extracted and the x type reaction rate of the kth statistical region and the Gth energy group wherein the x type reaction includes total reaction, absorption reaction and fission reaction; based on the neutron flux and the x-type reaction rate calculating the x-type macroscopic cross section of the kth statistical region, the Gth energy group The calculation formula is as follows: ， wherein, is the x-type continuous energy cross section at position r, energy E, is the continuous energy seed flux at position r, energy E, the x-type macroscopic cross section comprising the total cross section, absorption cross section, and fission cross section; extracting the kth statistical region, the scattering reaction rate of the energy group and the transition probability from the energy group scattered to the energy group G, obtained by statistically processing the continuous energy data based on the scattering reaction rate , the transfer probability and the group neutron flux , calculate the macroscopic scattering cross section from the group to the G group in the k statistical region , as follows: where, is the continuous energy scattering cross section at position r, energy E, is the probability distribution function of scattering from energy to energy E at position r.
7. The cross section generation method based on flux moment uniformization coupled with transport correction according to claim 1, characterized in that, In step S2, the total cross section spherical harmonic flux moment and the total reaction rate moment are extracted, and the total cross section spherical harmonic correction term is calculated based on the total cross section spherical harmonic flux moment and the total reaction rate moment, which comprises: Based on the statistical results of continuous energy Monte Carlo transport calculation, the flux moments of the kth region, the Gth energy group, the lth order and the mth term of spherical harmonics are directly extracted and the corresponding total reaction rate moments ; The spherical harmonic flux matrix corresponding to all item numbers m under the same order number l The total reaction rate matrix The total cross section spherical harmonic correction term of the kth statistical area and the Gth energy group of the lth order is obtained by processing The calculation formula is as follows: 。 8. The cross section generation method based on flux moment homogenization coupled with transport correction according to claim 7, characterized in that, In step S2, the total cross-section spherical harmonic function correction term is introduced into the conventional The conventional scattering cross-section in the cross-section data, including: calculating the total cross-section spherical harmonics modification term of the kth statistical region, the Gth energy group, and the lth order The difference between the conventional scattering total cross-section and the calculated total cross-section gives the cross-section difference; The cross section difference is applied to the k-th region by a Dirac delta function from the incident energy group The 1st order primary scattering cross section scattered to the exit energy group G The 1st order primary scattering cross section scattered to the exit energy group G The 1st order primary scattering cross section scattered to the exit energy group G ， wherein denotes the conventional k-th region, energy group l-th order raw scattering cross section to energy group G, is the Dirac delta function, and has the value 1 if and only if g= 1 otherwise. 9.A computer device comprising a memory and one or more processors, wherein the memory stores computer code, and the computer code, when executed by the one or more processors, causes the one or more processors to perform the steps of the cross section generation method based on flux moment homogenization and transport correction coupling according to any one of claims 1-8.
10. A storage medium storing computer readable instructions, wherein, The computer readable instructions, when executed by one or more processors, cause one or more processors to perform the steps of the cross section generation method based on flux moment homogenization and transport correction coupling according to any one of claims 1-8.