Photonuclear database production method for improving photonuclear calculation accuracy of reactor

Abstract

The application discloses a method for manufacturing a photonuclear database for improving the calculation precision of a reactor photonuclear, and the method comprises the following steps: obtaining photonuclear data of a first plurality of nuclides and performing format conversion to obtain photonuclear data in a first data format; performing calculation on the photonuclear data of a second plurality of nuclides in the first plurality of nuclides, and comparing the photonuclear data of the second plurality of nuclides according to the photonuclear calculation results; obtaining photonuclear data in a second data format according to the comparison results of the photonuclear data and the photonuclear data in the first data format, obtaining a first photonuclear database according to the photonuclear data in the first data format and an index file, and obtaining a second photonuclear database according to the photonuclear data in the second data format; and performing reactor data test on the first and second photonuclear databases respectively to obtain corresponding database test results. Through iterative feedback, the application obtains a continuous-energy photonuclear database with high precision and high reliability, and can significantly improve the calculation precision and efficiency of the neutron-photon coupling transport in a reactor.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of database making, and particularly relates to a method for making a photonuclear database for improving the accuracy of photonuclear calculation of a reactor. BACKGROUND

[0002] At present, the continuous-energy photonuclear database used by the Monte Carlo program is mainly the photonuclear database LA150U developed by Los Alamos National Laboratory, which is made by using the cross section processing program to mount the evaluation nuclear database. The following are the disadvantages of the prior art:

[0003] The number of nuclides is small, and the data source is old. The LA150U photonuclear database only provides photonuclear data of 13 nuclides, such as 2H, 12C, 16O, 27Al, 28Si, 40Ca, 56Fe, 63Cu, 181Ta, 184W, 206Pb, 207Pb and 208Pb, and lacks photonuclear data of important nuclides such as U and Pu required for reactor physics calculation. In addition, the evaluation nuclear database of LA150U is derived from ENDF / B-VI.8 published by the United States in 2001, and the cross section processing program is NJOY99 version. The small number of nuclides, the old version of the evaluation nuclear database and the cross section processing program limit the improvement of the photonuclear calculation accuracy of the Monte Carlo program.

[0004] The data format is old. At present, most of the nuclear design programs use the database format of the decimal format such as ENDF, ACE, WIMS-D and MATXS designed in 1960. This data format is mainly suitable for the 80-column punch card computer at that time. However, this format has the disadvantages of poor human readability, limited numerical accuracy and poor scalability, making it difficult for new nuclear data researchers and users to read and use nuclear data, and the reading efficiency of the computer is poor. SUMMARY

[0005] The present application aims to at least solve one of the technical problems in the related art to some extent.

[0006] To this end, the purpose of the present application is to propose a photonuclear database production method for improving the accuracy of reactor photonuclear calculation. Compared with the ACE format LA150U photonuclear database produced based on the ENDF / B-VI.8 evaluated nuclear database and the NJOY99 cross section processing program, the differences between the present application and the existing photonuclear database LA150U mainly include the following three points: (a) the present application will use the ENDF / B-VIII.0 evaluated nuclear database and the NJOY2016 cross section processing program published by the United States in 2018 to develop the photonuclear database, realize the update of the photonuclear data and the addition of the nuclide species. (b) The database developed by the present application will use the advanced data structure HDF5 format to improve the calculation efficiency, readability and scalability of the photonuclear database. (c) Since the photonuclear reaction has the characteristics of high threshold energy, domestic research institutions mainly focus on high-energy physics problems such as accelerators. Therefore, the photonuclear database developed by the present application will be mounted on the domestic Monte Carlo calculation program RMC to test and verify different types of reactor benchmark problems, so as to analyze the accuracy and applicability of the photonuclear reaction in different types of reactors.

[0007] To achieve the above purpose, one aspect of the present application proposes a photonuclear database production method for improving the accuracy of reactor photonuclear calculation, comprising:

[0008] Obtaining photonuclear data of a first plurality of nuclides and performing format conversion to obtain photonuclear data in a first data format;

[0009] Calculating the photonuclear data of a second plurality of nuclides in the first plurality of nuclides, and comparing the photonuclear data of the second plurality of nuclides according to the photonuclear calculation results;

[0010] According to the photonuclear data comparison results and the first data format photonuclear data, second data format photonuclear data is obtained, and according to the first data format photonuclear data and the index file, a first photonuclear database is obtained, and according to the second data format photonuclear data, a second photonuclear database is obtained;

[0011] Respectively testing the first and second photonuclear databases for reactor data to obtain corresponding database test results.

[0012] The photonuclear database production method for improving the accuracy of reactor photonuclear calculation according to the embodiment of the present application can further have the following additional technical features:

[0013] Further, in an embodiment of the present application, before the first data format photonuclear data is obtained, it further comprises: converting the decimal data in the evaluated nuclear database into binary data and converting the resonance parameters in the evaluated nuclear database into resonance self-screening cross section data by using the cross section processing program.

[0014] Further, in one embodiment of the present application, the calculation of the photo nuclear data of the second plurality of nuclides in the first plurality of nuclides, the comparison of the photo nuclear data of the second plurality of nuclides according to the photo nuclear calculation result, comprises: obtaining the second plurality of nuclides with a preset mass density in the first plurality of nuclides, and setting a fission photon point source in a geometric system of the second plurality of nuclides; performing photo nuclear data calculation on the second plurality of nuclides based on the fission photon point source, and obtaining multi-group photo nuclear cross section data of the geometric system according to the photo nuclear calculation result; and performing comparison of photo nuclear cross sections of the second plurality of nuclides based on the multi-group photo nuclear cross section data to obtain a photo nuclear cross section comparison result.

[0015] Further, in one embodiment of the present application, the obtaining of the second data format photo nuclear data according to the photo nuclear data comparison result and the first data format photo nuclear data, the obtaining of the first photo nuclear database according to the first data format photo nuclear data and the index file, and the obtaining of the second photo nuclear database according to the second data format photo nuclear data, comprises: processing the first plurality of nuclides by using the cross section processing program to obtain the first data format photo nuclear data and the corresponding index file; performing feature processing on the first data format photo nuclear data and the index file to obtain the first photo nuclear database; and converting the first data format photo nuclear data based on the photo nuclear data comparison result to obtain the second data format photo nuclear data, and merging the second data format photo nuclear data to obtain the second photo nuclear database.

[0016] To achieve the above object, the present application further provides a photo nuclear database production device for improving the photo nuclear calculation accuracy of a reactor, comprising:

[0017] a data acquisition module, configured to acquire photo nuclear data of a first plurality of nuclides and perform format conversion to obtain first data format photo nuclear data;

[0018] a data comparison module, configured to calculate photo nuclear data of a second plurality of nuclides in the first plurality of nuclides, and perform comparison of the photo nuclear data of the second plurality of nuclides according to a photo nuclear calculation result;

[0019] a database acquisition module, configured to obtain second data format photo nuclear data according to a photo nuclear data comparison result and the first data format photo nuclear data, obtain a first photo nuclear database according to the first data format photo nuclear data and an index file, and obtain a second photo nuclear database according to the second data format photo nuclear data;

[0020] a database test module, configured to perform reactor data test on the first and second photo nuclear databases respectively to obtain corresponding database test results.

[0021] The present application further provides a computer device, comprising a processor and a memory.

[0022] The processor runs a program corresponding to executable program code stored in the memory by reading the executable program code, to implement the light nucleus database production method for improving the light nucleus calculation accuracy of a reactor.

[0023] The fourth aspect of the present application provides a non-transitory computer-readable storage medium, which stores a computer program, and the program is executed by a processor to implement the light nucleus database production method for improving the light nucleus calculation accuracy of a reactor.

[0024] The light nucleus database production method for improving the light nucleus calculation accuracy of a reactor, the device, the equipment and the storage medium of the embodiment of the present application optimize the NJOY2016 program, realize the automatic generation of the multi-nucleus input card and the conversion of the HDF5 format data, thereby realizing the development of the new evaluation nuclear database, the multi-nucleus and the HDF5 format light nucleus data file; then, the light nucleus data comparison is realized based on the infinite medium example, and the corresponding light nucleus database is produced; in addition, the developed light nucleus database is tested and verified by shielding, criticality and reactor core examples, so as to analyze the calculation accuracy and efficiency of different light nucleus databases; finally, through iterative feedback, the continuous energy light nucleus database with high precision and high reliability is obtained.

[0025] Additional aspects and advantages of the present application will be in part apparent and in part pointed out hereinafter. BRIEF DESCRIPTION OF DRAWINGS

[0026] The above and / or additional aspects and advantages of the present application will become apparent and be readily appreciated from the following description, taken in conjunction with the accompanying drawings, in which:

[0027] Figure 1 The flow chart of the light nucleus database production method for improving the light nucleus calculation accuracy of a reactor according to the embodiment of the present application;

[0028] Figure 2 The flow chart of the light nucleus database production method for improving the light nucleus calculation accuracy of a reactor according to the embodiment of the present application; 226 The schematic diagram of the NJOY input card of the Ra nucleus light nucleus data processing;

[0029] Figure 3 The schematic diagram of the infinite large geometric system according to the embodiment of the present application;

[0030] Figure 4 The schematic diagram of the 2H light nucleus total cross section comparison of different light nucleus databases according to the embodiment of the present application;

[0031] Figure 5 The schematic diagram of the light nucleus HDF5 data of Fe according to the embodiment of the present application; 56 The schematic diagram of the light nucleus HDF5 data of Fe according to the embodiment of the present application;

[0032] Figure 6 Flow chart for making optical kernel ACE database according to the embodiment of the present application;

[0033] Figure 7 Flow chart for making optical kernel HDF5 database according to the embodiment of the present application;

[0034] Figure 8 OKTAVIAN-Al example geometry diagram according to the embodiment of the present application;

[0035] Figure 9 OKTAVIAN-Al example neutron leakage rate comparison diagram according to the embodiment of the present application;

[0036] Figure 10 OKTAVIAN-Al example neutron leakage rate relative deviation from experimental value diagram according to the embodiment of the present application;

[0037] Figure 11 OKTAVIAN-Al example photon leakage rate comparison diagram according to the embodiment of the present application;

[0038] Figure 12 OKTAVIAN-Al example photon leakage rate relative deviation from experimental value diagram according to the embodiment of the present application;

[0039] Figure 13 VENUS-2 example 1 / 4 core layout diagram according to the embodiment of the present application;

[0040] Figure 14 Optical kernel database making architecture diagram for improving reactor optical kernel calculation precision according to the embodiment of the present application;

[0041] Figure 15 Optical kernel database making device structure diagram for improving reactor optical kernel calculation precision according to the embodiment of the present application;

[0042] Figure 16 Computer device according to the embodiment of the present application. DETAILED DESCRIPTION

[0043] It should be noted that the embodiments in the present application and the features in the embodiments can be combined with each other without conflict. The present application will be described in detail below with reference to the accompanying drawings and in combination with the embodiments.

[0044] In the following, the technical solutions in the embodiments of the present application will be described clearly and completely with reference to the drawings in the embodiments of the present application. Obviously, the described embodiments are only a part but not all of the embodiments of the present application. Based on the embodiments in the present application, all other embodiments obtained by a person of ordinary skill in the art without creative work should belong to the protection scope of the present application.

[0045] The method, device and equipment for making a photonuclear database for improving the photonuclear calculation accuracy of a reactor and a storage medium are described below with reference to the accompanying drawings according to an embodiment of the present application.

[0046] Figure 1 is a flowchart of the method for making a photonuclear database for improving the photonuclear calculation accuracy of a reactor according to an embodiment of the present application.

[0047] As shown in Figure 1 , the method includes but is not limited to the following steps:

[0048] S1, obtain photonuclear data of a first plurality of nuclides and perform format conversion to obtain photonuclear data in a first data format.

[0049] It can be understood that the photonuclear data is updated to realize photonuclear data files of 163 nuclides in the ENDF / B-VIII.0 evaluated nuclear database.

[0050] Specifically, the versions of the evaluated nuclear database released by countries around the world are shown in Table 1, and the ENDF / B-VIII.0, ENDF / B-VII.1 developed by the United States and the CENDL-3.2 evaluated nuclear database developed by China are selected for photonuclear database development in the embodiments of the present application. In addition, the cross-section processing program NJOY2016 has a photonuclear data processing function, Figure 2 The NJOY input card for processing the photonuclear data of the Ra nuclide is shown in 226 . The moder module is a binary conversion module, and the main function is to convert the decimal data file in the evaluated nuclear database into a binary data file; the reconr is a resonance reconstruction module, and the main function is to convert the resonance parameters in the evaluated nuclear database into resonance self-shielding cross sections; the acer mode 5 is an ACE format data file generation module, and the main function is to convert the PENDF data file generated by the NJOY program into an ACE format data file; and the acer mode 7 is a data editing module, and the main function is to interpret the ACE data file generated by the acer mode 5 and convert it into a data format used for editing, comparison and drawing.

[0051] Table 1

[0052]

[0053] S2, performing calculation on photo-nuclear data of a second plurality of nuclides in the first plurality of nuclides, and comparing photo-nuclear data of the second plurality of nuclides according to the photo-nuclear calculation results.

[0054] It can be understood that the photo-nuclear data comparison is mainly photo-nuclear data comparison of important nuclides (such as H, Fe, U and Pu).

[0055] It can be understood that for the multi-group nuclear database used by the deterministic program, the number of energy groups and the energy group structure are fixed (such as WIMS69, XMAS172 and SHEM281 groups, etc.), and the multi-group cross-section data comparison of different nuclides can be directly performed; for the ACE format continuous energy point nuclear database used by the Monte Carlo program, the number of energy points in different evaluation nuclear databases is inconsistent, for example 182 The number of energy points of W in CENDL-3.2, ENDF / B-VIII.0, ENDF / B-VII.1 and LA150U photo-nuclear databases is 27554, 78429, 78429 and 78439 respectively. Therefore, in order to realize the continuous energy point photo-nuclear data comparison of different nuclides, special processing is required.

[0056] Specifically, the main research idea of the present application is to use a system with an approximately infinite geometric size, uniformly filled with nuclides with a mass density of 1.0 g / cm 3 , and a isotropic and uniformly distributed fission photon point source is arranged at the geometric center, so as to perform photo-nuclear calculation by using the Monte Carlo program RMC, and the multi-group photo-nuclear cross-section data of the system is counted by the energy group merging method, and finally the photo-nuclear cross-section comparison of different nuclides is realized.

[0057] As an example, Figure 3 an infinite geometric system is shown, the spherical radius is 10 9 cm, a photon point source with an energy of 100 MeV is arranged at the center of the sphere, and four different materials (such as H, O, Fe, U) are used as the reaction medium, and the mass density is 1 g / cm 3 . Figure 4 Then the H photo-nuclear total cross-section comparison of different photo-nuclear databases is mainly shown. 2

[0058] S3, obtaining second data format photo-nuclear data according to the photo-nuclear data comparison results and the first data format photo-nuclear data, obtaining the first photo-nuclear database according to the first data format photo-nuclear data and the index file, and obtaining the second photo-nuclear database according to the second data format photo-nuclear data.

[0059] ​It can be understood that the H5 format of the photo nuclear data is developed, the H5 format of the photo nuclear data file of the ENDF / B-VIII.0 evaluation nuclear database is realized, the photo nuclear database is developed, the photo nuclear data files and index files of 163 nuclides are combined, and the ACE and H5 format of the photo nuclear database of the ENDF / B-VIII.0 evaluation nuclear database is realized.

[0060] Specifically, the application adopts the HDF5 data structure for continuous-energy photo nuclear database development, the HDF5 data structure is developed by the University of Illinois at Urbana-Champaign, is a common cross-platform data storage file, can store different types of images and digital data, and can be transmitted on different types of machines, and has a function library for processing the file format uniformly. Compared with the ACE data structure, the HDF5 data structure has high reading speed and small memory occupation, and the data structure has good coupling with the modern programming language Python. Figure 5 It is shown that 56 The photo nuclear HDF5 data of Fe.

[0061] Further, for the nuclear database used by the reactor physics calculation program, generally, the nuclear data file of a single nuclide is made by the cross section processing program NJOY2016, and then the nuclear data files of all nuclides are aggregated to obtain the final nuclear database. However, the nuclide types in the evaluation nuclear database are more, and a specific nuclear database merging auxiliary program needs to be developed to realize the merging of multi-nuclide nuclear data files and the generation of the nuclear database. For example, the WIMS-D and MATXS multi-group nuclear database opened the corresponding nuclear database auxiliary processing program WILLIE and TRANSX. Therefore, it is necessary to develop an auxiliary processing program for the merging of continuous-energy photo nuclear database.

[0062] As an example, the application realizes the integrated automatic generation of continuous-energy photo nuclear database based on a Python development script, and a main function flowchart of the script is shown in Figure 6 and Figure 7 . Figure 6 The production process of the photo nuclear ACE database is shown: firstly, the NJOY input card automatic generation is realized for all nuclides provided by the evaluation nuclear database; then, the NJOY program is called for processing to generate multi-nuclide photo nuclear ACE data files and index files; finally, all photo nuclear ACE data files and index files are classified, stored and named in a large batch, and the photo nuclear ACE database available for programs is obtained. Figure 7The production process of the photo-nuclear HDF5 database is shown. Similar to the production process of the photo-nuclear ACE database, the production of the multi-nuclear photo-nuclear ACE data file is also performed. The difference lies in that the photo-nuclear ACE data file needs to be converted into the HDF5 format, so as to generate the photo-nuclear HDF5 data file corresponding to the nuclear. Since the HDF5 data format has natural readability and extensibility, an index file is not needed for calling. Finally, only the generated photo-nuclear HDF5 data file needs to be merged, so as to obtain the photo-nuclear HDF5 database for program use.

[0063] S4, respectively, the first and second photo-nuclear database is tested for reactor data, and the corresponding database test results are obtained.

[0064] It can be understood that the ACE and HDF5 format photo-nuclear databases developed by the applicant are mounted on the Monte Carlo calculation program RMC to test and verify different types of reactor benchmark problems.

[0065] Specifically, in the reactor physics calculation, it is very necessary to verify the benchmark of the calculation program and the database. In order to test the newly developed photo-nuclear database, the present application mainly selects the following benchmark problems for testing and verification: 1, ICSBEP series critical benchmark problems; 2, SINBAD series shielding benchmark problems; 3, VENUS-2 core benchmark problems. The above series of benchmark problems basically cover the actual working conditions involved in the reactor physics calculation, which helps to test the calculation accuracy and reliability of the independently developed photo-nuclear database.

[0066] 1, ICSBEP series critical benchmark problems.

[0067] The ICSBEP series benchmark problems are important critical test benchmark problems internationally. The benchmark problems include a variety of different critical test examples, such as Pu metal, high enrichment uranium metal, low enrichment uranium metal, 233 U, MOX fuel, etc. The present application selects UMF( 233 U-Metal-Fast), HMF (Highly Enriched Uranium-Metal-Fast), HST (Highly Enriched Uranyl Nitrate-Solution-Thermal) and PMF (Plutonium-Metal-Fast) series benchmark problems for testing and verification. The particle number of RMC and MCNP6 program for critical calculation is 30000, the non-active generation is 100, and the total generation is 800. The neutron-photon coupled transport critical calculation is performed, and the specific calculation results are shown in Table 2.

[0068] The calculation results show that after the RMC and MCNP6 programs are mounted with the photo-nuclear database developed by the applicant, the overall k effThe values ​​agree well with the experimental values. Except for some HST examples where the deviation exceeds 200 pcm, the deviations of the remaining examples are all within 200 pcm. Furthermore, the k-values ​​between the RMC and MCNP6 programs are... eff The value deviations were all within 20 pcm, and the errors did not exceed 3 standard deviations, indicating that the RMC program and the self-made optical nucleus database have stable and reliable optical nucleus transport calculation capabilities.

[0069] Table 2

[0070]

[0071]

[0072] 2. SINBAD series shielding benchmark questions.

[0073] This invention selects the OKTAVIAN-A1 shielding benchmark from the SINBAD series of shielding benchmark problems for testing. The geometric structure of this example is as follows: Figure 8 As shown. Furthermore, the experimental values ​​in this example take into account the neutron-photon-electron coupling transport calculation conditions, so this example can effectively test the influence of photonuclear reactions under these conditions. In the fixed-source shielding calculations of the MCNP and RMC programs, this invention selected a particle number of 5,000,000 and compared the obtained neutron and photon leakage rates with experimental values.

[0074] Figures 9-12 This paper primarily showcases a comparison between experimental values ​​and the neutron and photon leakage rates obtained using the RMC and MCNP6 programs coupled with a self-made photonuclear database. The calculation results show that, under neutron-photon-electron coupled transport conditions, the relative deviations between the overall calculated results and experimental values ​​for the RMC and MCNP programs are within 50%, except for a few energy ranges where deviations exceed 100%. These deviations are attributed primarily to experimental biases present in the early detector statistical processes. Furthermore, the overall deviations in neutron and photon leakage rates between the RMC and MCNP programs are small, indicating that the self-made Monte Carlo program RMC and photonuclear database possess good computational accuracy and reliability under neutron-photon-electron coupled transport conditions.

[0075] 3. VENUS-2 reactor core benchmark.

[0076] The benchmark selected by the application is a critical shielding benchmark released by OECD / NEA, and the prototype is a zero-power critical reactor in Belgium, and the 1 / 4 core layout is as follows. The 1 / 4 core contains 3 15x15 assemblies, the central assembly is UO2 fuel with an enrichment of 3.3wt.%, and there are 10 boron glass rods in the center, and the center is a water hole. The outer assembly is composed of two parts, the inner 7 columns are loaded with UO2 fuel with an enrichment of 4.0wt.%, and the outer 8 columns are loaded with 235 U MOX fuel with an enrichment of 2.0wt.% and high purity plutonium with an enrichment of 2.7wt.%. In the calculation process, the RMC and MCNP6 programs of the application perform neutron-photon-electron coupling criticality calculation, the particle number is 30000, the non-active generation is 100, and the total generation is 800, and the specific calculation results are shown in Table 3.

[0077] The calculation results show that, after considering the photonuclear reaction, the k eff value results obtained by mounting the self-made photonuclear database of MCNP and RMC are overall larger, which conforms to the actual physical process. On the one hand, due to the consideration of the photonuclear reaction, a part of the photons become neutrons, so that the reactivity is larger; on the other hand, due to the threshold energy of the photonuclear reaction, and the overall energy of the VENUS-2 example is smaller than that of the pressurized water reactor example, so that the reactivity is larger by 7-14pcm.

[0078] Table 3

[0079]

[0080] In summary, the photonuclear database production architecture for improving the photonuclear calculation precision of the reactor of the application is as shown in the figure. Figure 14 Firstly, the NJOY2016 program is optimized to realize automatic generation of multi-nucleus input cards and HDF5 format data conversion, so as to realize development of new evaluation nuclear database, multi-nucleus and HDF5 format photonuclear data file; then, based on the infinite medium example, the photonuclear data are compared, and the corresponding photonuclear database is made; in addition, the developed photonuclear database is tested and verified by shielding, criticality and core examples, so as to analyze the calculation precision and efficiency of different photonuclear databases; finally, through iterative feedback, the continuous energy photonuclear database with high precision and high reliability is obtained

[0081] According to the power transmission line lightning identification and positioning method based on ground electromagnetic signals provided by the embodiment of the application, the calculation precision and efficiency of the neutron-photon coupling transport in the reactor can be significantly improved.

[0082] In order to realize the above-mentioned embodiments, as Figure 15As shown, the embodiment also provides a photodisintegration database production device 10 for improving the accuracy of photodisintegration calculation of a reactor, which comprises a data acquisition module 100, a data comparison module 200, a database acquisition module 300 and a database test module 400.

[0083] The data acquisition module 100 is configured to acquire photodisintegration data of a first plurality of nuclides and perform format conversion to obtain photodisintegration data in a first data format.

[0084] The data comparison module 200 is configured to perform photodisintegration calculation on the photodisintegration data of a second plurality of nuclides in the first plurality of nuclides, and perform comparison of the photodisintegration data of the second plurality of nuclides according to the photodisintegration calculation results.

[0085] The database acquisition module 300 is configured to obtain photodisintegration data in a second data format according to the comparison results of the photodisintegration data and the photodisintegration data in the first data format, obtain a first photodisintegration database according to the photodisintegration data in the first data format and an index file, and obtain a second photodisintegration database according to the photodisintegration data in the second data format.

[0086] The database test module 400 is configured to perform reactor data test on the first and second photodisintegration databases respectively to obtain corresponding database test results.

[0087] Further, the data acquisition module 100 is further configured to:

[0088] convert the decimal data in the evaluation nuclear database into binary data and convert the resonance parameters in the evaluation nuclear database into resonance self-screening cross-section data by using a cross-section processing program.

[0089] Further, the data comparison module 200 is further configured to:

[0090] acquire a second plurality of nuclides with a preset mass density from the first plurality of nuclides, and set a fission photon point source in a geometric system of the second plurality of nuclides;

[0091] perform photodisintegration data calculation on the second plurality of nuclides based on the fission photon point source, and acquire multi-group photodisintegration cross-section data of the geometric system according to the photodisintegration calculation results;

[0092] perform photodisintegration cross-section comparison on the second plurality of nuclides based on the multi-group photodisintegration cross-section data to obtain photodisintegration cross-section comparison results.

[0093] Further, the database acquisition module 300 is further configured to:

[0094] process the first plurality of nuclides by using a cross-section processing program to obtain the photodisintegration data in the first data format and the corresponding index file;

[0095] The first data format optical kernel data and the index file are subjected to feature processing to obtain a first optical kernel database; and

[0096] The first data format optical kernel data is converted based on the comparison result of the optical kernel data to obtain second data format optical kernel data, and the second data format optical kernel data is merged to obtain a second optical kernel database.

[0097] The optical kernel database manufacturing device for improving the accuracy of optical kernel calculation of a reactor according to the embodiment of the present application can significantly improve the calculation accuracy and efficiency of neutron-photon coupling transport in a reactor.

[0098] In order to implement the method of the above-mentioned embodiments, the present application further provides a computer device, as shown in the accompanying drawings, the computer device 600 comprises a memory 601, a processor 602; wherein the processor 602 runs the program corresponding to the executable program code stored in the memory 601 by reading the executable program code, so as to implement each step of the optical kernel database manufacturing method for improving the accuracy of optical kernel calculation of a reactor described above. Figure 16

[0099] In order to implement the method of the above-mentioned embodiments, the present application further provides a non-transitory computer readable storage medium, which stores a computer program, the program is executed by a processor to implement the optical kernel database manufacturing method for improving the accuracy of optical kernel calculation of a reactor.

[0100] In addition, the terms "first", "second" are only for descriptive purposes and cannot be understood as indicating or implying relative importance or implicitly indicating the number of the indicated technical features. Therefore, the features defined with "first", "second" can explicitly or implicitly include at least one of the features. In the description of the present application, the meaning of "a plurality of" is at least two, for example, two, three, etc., unless otherwise explicitly specified.

[0101] In the description of the present application, the description of the terms "one embodiment", "some embodiments", "example", "specific example", or "some examples" means that the specific features, structures, materials or characteristics described in conjunction with the embodiment or example are included in at least one embodiment or example of the present application. In the present application, the illustrative description of the above terms is not necessarily for the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described can be combined in any one or more embodiments or examples in a suitable manner. In addition, the skilled in the art can combine and combine the different embodiments or examples described in the present application and the features of different embodiments or examples without contradiction.

[0102] ​Although the embodiments of the present application have been shown and described above, it is understood that the above-described embodiments are exemplary and are not to be construed as limiting the present application, and that variations, modifications, substitutions and changes can be made by those skilled in the art without departing from the scope of the present application.

Claims

1. A method for making a photonuclear database to improve the accuracy of photonuclear calculation of a reactor, characterized in that, The method comprises the following steps: Obtaining photo nuclear data of a first plurality of nuclides and performing format conversion to obtain first data format photo nuclear data; Calculating photo nuclear data of a second plurality of nuclides in the first plurality of nuclides, and comparing photo nuclear data of the second plurality of nuclides according to photo nuclear calculation results; Obtaining second data format photo nuclear data according to the photo nuclear data comparison results and the first data format photo nuclear data, obtaining a first photo nuclear database according to the first data format photo nuclear data and an index file, and obtaining a second photo nuclear database according to the second data format photo nuclear data; Respectively testing the first and second photo nuclear databases for reactor data to obtain corresponding database test results; The calculation of the photo nuclear data of the second plurality of nuclides in the first plurality of nuclides and the comparison of the photo nuclear data of the second plurality of nuclides according to the photo nuclear calculation results comprises: obtaining a second plurality of nuclides with a preset mass density in the first plurality of nuclides, and setting a fission photon point source in a geometric system of the second plurality of nuclides; performing photo nuclear data calculation on the second plurality of nuclides based on the fission photon point source, and obtaining multi-group photo nuclear cross section data of the geometric system according to photo nuclear calculation results; and performing photo nuclear cross section comparison of the second plurality of nuclides based on the multi-group photo nuclear cross section data to obtain photo nuclear cross section comparison results; The obtaining of the second data format photo nuclear data according to the photo nuclear data comparison results and the first data format photo nuclear data, the obtaining of the first photo nuclear database according to the first data format photo nuclear data and the index file, and the obtaining of the second photo nuclear database according to the second data format photo nuclear data comprises: processing the first plurality of nuclides by using a cross section processing program to obtain the first data format photo nuclear data and a corresponding index file; performing feature processing on the first data format photo nuclear data and the index file to obtain the first photo nuclear database; and converting the first data format photo nuclear data based on the photo nuclear data comparison results to obtain the second data format photo nuclear data, and merging the second data format photo nuclear data to obtain the second photo nuclear database.

2. The method of claim 1, wherein, Before the first data format photo nuclear data is obtained, the method further comprises: Converting decimal data in an evaluation nuclear database into binary data and converting resonance parameters in the evaluation nuclear database into resonance self-screening cross section data by using a cross section processing program.

3. A photonuclear database production device that improves the accuracy of photonuclear calculation of a reactor, characterized by The method comprises the following steps: A data acquisition module is configured to obtain photo nuclear data of a first plurality of nuclides and perform format conversion to obtain first data format photo nuclear data; A data comparison module is configured to calculate photo nuclear data of a second plurality of nuclides in the first plurality of nuclides, and compare photo nuclear data of the second plurality of nuclides according to photo nuclear calculation results; A database acquisition module is configured to obtain second data format photo nuclear data according to photo nuclear data comparison results and the first data format photo nuclear data, obtain a first photo nuclear database according to the first data format photo nuclear data and an index file, and obtain a second photo nuclear database according to the second data format photo nuclear data; The database test module is configured to perform reactor data tests on the first and second photonuclear database respectively, and obtain corresponding database test results. The data comparison module is further configured to: obtain a second plurality of nuclides with a preset mass density from the first plurality of nuclides, and set a fission photon point source in a geometric system of the second plurality of nuclides; perform photonuclear data calculation on the second plurality of nuclides based on the fission photon point source, and obtain multi-group photonuclear cross section data of the geometric system according to a photonuclear calculation result; and perform photonuclear cross section comparison on the second plurality of nuclides based on the multi-group photonuclear cross section data to obtain a photonuclear cross section comparison result. The database obtaining module is further configured to: process the first plurality of nuclides by using a cross section processing program to obtain first data format photonuclear data and a corresponding index file; perform feature processing on the first data format photonuclear data and the index file to obtain the first photonuclear database; and convert the first data format photonuclear data based on the photonuclear data comparison result to obtain second data format photonuclear data, and merge the second data format photonuclear data to obtain the second photonuclear database.

4. The apparatus of claim 3, wherein, The data obtaining module is further configured to: The cross section processing program is configured to convert decimal data in the evaluation nuclide database into binary data, and convert resonance parameters in the evaluation nuclide database into resonance self-screening cross section data.

5. A computer device, comprising: The system comprises a processor and a memory; The processor runs a program corresponding to executable program code stored in the memory by reading the executable program code, to implement the photonuclear database production method for improving photonuclear calculation accuracy of a reactor according to any one of claims 1-2.

6. A non-transitory computer-readable storage medium having stored thereon a computer program, characterized in that, The program is executed by the processor to implement the photonuclear database production method for improving photonuclear calculation accuracy of a reactor according to any one of claims 1-2.

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