A core physics multi-group constant library testing method

Abstract

The present invention relates to a method for testing a core physics multi-group constant library, comprising: (1) performing a single nuclide format check and a single nuclide physical check to confirm that the single nuclide data can be read and format converted normally, as well as the physical rationality, self-consistency and availability of each nuclide data; (2) performing a single nuclide data availability test to confirm that each nuclide can be used normally for calculation; (3) performing a burnup chain test to check the applicability of the burnup chain compression and the accuracy of the burnup data; (4) performing a criticality benchmark test and a burnup benchmark test. The present invention performs a series of tests on the core physics multi-group constant library from the "micro" and "macro" levels, and runs the tests throughout the entire development cycle, which not only further ensures the reliability of each nuclide data in the core physics multi-group constant library, but also reduces the difficulty of the core physics multi-group constant library benchmark test analysis to a certain extent, and improves the production efficiency.

Description

Technical Field

[0001] The invention belongs to reactor core simulation technology, and in particular relates to a core physics multi-group constant library testing method. Background Art

[0002] The core physics multi-group constant library is an essential basic input parameter for reactor core simulation calculations. The development of the core physics multi-group constant library includes three stages: design, production and testing. The testing of the core physics multi-group constant library is a key link to ensure the accuracy of the core physics multi-group constant library, and the testing should be carried out throughout the entire development cycle. At present, the commonly used core physics multi-group constant library testing methods mainly include criticality benchmark inspection and burnup benchmark inspection. For example, the WIMS library, CASL library, HELIOS library, etc. are all based on benchmark inspections to test the multi-group constant library. The criticality and burnup benchmark inspections are macro tests that are carried out after the multi-group constant library is completed. Usually, the test of each benchmark example involves the data of multiple nuclides in the multi-group constant library. The test results are also affected by multiple factors such as the calculation program and the "interference" effect between nuclide data. The analysis of the test results requires the use of sensitivity analysis methods, etc., and the location of the problem and the correction of the data is a very complicated process. Therefore, it is necessary to carry out the testing of the multi-group constant library throughout the entire development cycle, and to conduct more basic tests on the multi-group constant library before the benchmark test. First, eliminate possible format problems in the data from a microscopic level, ensure the physical rationality, self-consistency and availability of the single nuclide data, and then conduct a macroscopic benchmark test. On the one hand, it can ensure the accuracy of each nuclide data, and on the other hand, reduce the complexity of the benchmark test analysis. Summary of the invention

[0003] The purpose of the present invention is to provide a core physics multi-group constant library testing method in view of the defects of the prior art, so as to ensure the accuracy of the core physics multi-group constant library and reduce the analysis difficulty of macro-benchmark detection.

[0004] The technical solution of the present invention is as follows: A method for testing a core physics multi-group constant library comprises the following steps:

[0005] (1) Perform single-nuclide format check and single-nuclide physical check to confirm that single-nuclide data can be read and format converted normally, and that each nuclide data is physically reasonable, self-consistent, and usable;

[0006] (2) Perform single-nuclide data availability tests to confirm that each nuclide can be used for calculations normally;

[0007] (3) Carry out fuel chain test to check the suitability of fuel chain compression and the accuracy of fuel consumption data;

[0008] (4) Carry out criticality benchmark inspection and fuel consumption benchmark inspection.

[0009] Furthermore, in the core physics multi-group constant library test method as described above, the method for checking the single nuclide format described in step (1) is to use the base conversion program of the multi-group constant library to convert the single nuclide decimal data into binary, and then convert it back to decimal, and compare the difference between the data before and after the conversion.

[0010] Further, in the core physics multi-group constant library test method described above, the single nuclide physical inspection described in step (1) needs to ensure that the data of each nuclide satisfies the following formula:

[0011] σ t =σ a +σ s (1)

[0012]

[0013] σ f ,σ 0,s ,σ n2n ,σ n3n ,...>0 (3)

[0014] I g >0 (4)

[0015]

[0016]

[0017] Where σ is the cross section, and the subscripts t, a, s, f, n2n, and n3n represent total, absorption, scattering, fission, (n, 2n) reaction, and (n, 3n) reaction, respectively. 0,S represents the 0th-order scattering cross section, represents the fission energy spectrum, I represents the resonance integral, g represents the exit energy group, and g' represents the arrival energy group.

[0018] Furthermore, in the core physics multi-group constant library testing method described above, in step (1), it is also checked whether there are any illegal characters that cannot be used in the single nuclide data.

[0019] Furthermore, in the core physics multi-group constant library test method as described above, the single nuclide data availability test described in step (2) is to calculate the infinite multiplication coefficient of the mixture formed by U-235, H-1 and the nuclide to be tested, and compare it with the Monte Carlo calculation results based on homologous data.

[0020] Furthermore, in step (2), the Monte Carlo calculation results are used as a benchmark to compare the single nuclide data availability test calculation results of the core physics multi-group constant library, and a detection threshold is set. If the ratio of the Monte Carlo calculation results exceeds the detection threshold, it is recorded as excessive deviation; the reasons for the large deviation are analyzed, and the single nuclide data are corrected accordingly based on the analysis results.

[0021] Further, in the core physics multi-group constant library test method as described above, the method of the burnup chain test in step (3) is to use the burnup program to calculate the same burnup problem based on the compression chain and the fine chain respectively, solve the accumulation of all nuclides on the compression chain and compare it with the calculation result of the complete burnup chain, and determine the rationality of the compression of the compression chain and the accuracy of the burnup data according to the deviation of the comparison. For example, by comparing the accumulation of all burnup nuclides, if the deviation of the accumulation of burnup nuclides calculated by the compression chain and the complete burnup chain is less than 2%, it is considered that the compression of the compression chain is reasonable and the burnup data is accurate.

[0022] Furthermore, in the core physics multi-group constant library testing method as described above, the critical benchmark test described in step (4) is to select fast spectrum, intermediate energy spectrum, and thermal spectrum benchmark experiments from the International Nuclear Criticality Safety Manual ICSBEP2006 and the Cross-Section Evaluation Working Group Benchmark Experiment Manual ENDF-202 to test the core physics multi-group constant library, model and calculate the selected benchmark questions, and compare them with the experimental benchmark values.

[0023] Furthermore, when performing the critical benchmark test in step (4), the infinite multiplication coefficient k of the spherical device inf Monte Carlo infinite uniform medium proliferation factor calculation results k inf.cal and effective proliferation factor k eff.cal With the reference value k eff.exp According to the geometric relationship, the formula is as follows:

[0024]

[0025] Furthermore, in the core physics multi-group constant library test method as described above, the burnup benchmark test described in step (4) is to select a burnup benchmark experiment from the spent fuel isotopic composition database SFCOMPO-2 (Spent Fuel Isotopic Composition Database), perform modeling and calculation, compare the calculation results with the experimental results, and evaluate the accuracy of the burnup calculation.

[0026] The beneficial effects of the present invention are as follows: The core physics multi-group constant library testing method provided by the present invention performs a series of tests on the core physics multi-group constant library from the "micro" and "macro" levels, and the tests are carried out throughout the entire development cycle, which not only further ensures the physical rationality, self-consistency and availability of each nuclide data of the core physics multi-group constant library, ensures the accuracy of the core physics multi-group constant library fuel consumption chain and its corresponding fuel consumption data, but also reduces the difficulty of the core physics multi-group constant library benchmark inspection and analysis to a certain extent, and improves the production efficiency. BRIEF DESCRIPTION OF THE DRAWINGS

[0027] Figure 1 A flow chart of a core physics multi-group constant library testing method provided by the present invention;

[0028] Figure 2 A schematic diagram of a Godiva experimental geometric model in a specific embodiment of the present invention;

[0029] Figure 3 It is a schematic diagram of the calculation model of the SF95 series samples in a specific embodiment of the present invention. DETAILED DESCRIPTION

[0030] In order to make the purpose, technical solution and advantages of the present invention more clearly understood, the present invention is further described in detail below in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present invention and are not used to limit the present invention.

[0031] The present invention divides the test of the core physics multi-group constant library into four levels: syntax check, unit test, subsystem integration test, and system integration test. Figure 1 As shown. First, perform syntax check of single nuclide data files - format check and physical rationality and self-consistency check. Second, perform functional test of single nuclide data files - test the availability of single nuclide data files. Third, perform fuel consumption chain test. Finally, perform benchmark test of multi-group constant library, i.e. critical benchmark test and fuel consumption benchmark test. The specific description of each step is as follows:

[0032] (1) Single nuclide format and physical check (syntax check)

[0033] The purpose of single nuclide format check is to test whether the single nuclide data can be read and format converted normally. The test method is as follows: Use the base conversion program of the multi-group constant library to convert the single nuclide decimal data into binary, then convert it back to decimal, and compare the difference between the data before and after the conversion.

[0034] Single nuclide physical inspection is mainly to ensure that the data of each nuclide meets the following formula:

[0035] σ t =σ a +σs (1)

[0036]

[0037] σ f ,σ 0,s ,σ n2n ,σ n3n ,...>0 (3)

[0038] I g >0 (4)

[0039]

[0040]

[0041] Where σ is the cross section, subscripts t, a, s, f, n2n, n3n represent total, absorption, scattering, fission, (n, 2n), (n, 3n) reaction, respectively, and σ 0，S represents the 0th-order scattering cross section, represents the fission energy spectrum, I represents the resonance integral, g represents the exit energy group, and g' represents the arrival energy group. In addition, check whether there are illegal characters that cannot be used in the single nuclide data.

[0042] (2) Single nuclide data usability test (unit test)

[0043] Single nuclide data availability test refers to the K inf The problem run test is designed to confirm that each nuclide can be used normally for calculations. The test method is to calculate the infinite multiplication coefficient of the mixture formed by U-235, H-1 and the nuclide to be tested, and compare it with the Monte Carlo calculation results based on homologous data. Using the Monte Carlo calculation results as a benchmark, compare the deterministic calculation results of the core physics multi-group constant library, set a detection threshold, and record it as excessive deviation if the ratio with the Monte Carlo calculation results exceeds the detection threshold. Analyze the reasons for the large deviation and make corresponding corrections to the single nuclide data based on the analysis results.

[0044] (3) Fuel chain test (subsystem integration test)

[0045] The burnup chain test is mainly to check the applicability of the burnup chain compression and the accuracy of the burnup data. The test uses the burnup program to calculate the ideal burnup problem based on the compression chain and the fine chain, solve the accumulation of all nuclides on the compression chain and compare it with the calculation results of the complete burnup chain. The purpose of the test is to verify the reliability of the burnup chain compression method and the applicability of the designed burnup chain.

[0046] (4) Criticality benchmark test and fuel consumption benchmark test (integrated test)

[0047] The macro benchmark test of the group constant library should theoretically cover all materials and the entire energy range in the library, but this is impossible in reality. Limited benchmark experiments have limited coverage of nuclides and energy spectra, usually only covering major fission nuclides, structural materials, light nuclides, fission products, etc. The coverage of the energy range is restricted by the sensitivity range of the experimental device to a certain nuclear reaction. Therefore, the benchmark test of the group constant library mainly tests the key nuclides commonly used in nuclear devices, and the selection of experimental devices is also selected according to the application type in order to test the accuracy of the database. The macro test of the core physics multi-group constant library selects two types of experiments: criticality benchmark experiments and burnup benchmark experiments. The criticality benchmark test selects fast spectrum, intermediate energy spectrum, and thermal spectrum benchmark experiments from the International Nuclear Criticality Safety Manual ICSBEP2006 and the Cross-Section Evaluation Working Group Benchmark Experiment Manual ENDF-202 to test the core physics library. It is necessary to use the component program of the reactor core simulation calculation to model and calculate the selected benchmark questions and compare them with the experimental benchmark values. The component program is used in conjunction with the core physics multi-group constant library, which is a well-known technology in the field. The core physics multi-group constant library burnup test, criticality benchmark test and burnup benchmark test all require the use of supporting component programs for related calculations. Considering that the component program is not capable of handling spherical geometry, the spherical device k inf Monte Carlo infinite uniform medium proliferation factor calculation results k inf.cal and effective proliferation factor k eff.cal With the reference value k eff.exp According to the geometric relationship, the formula is as follows:

[0048]

[0049] The burnup benchmark test is to select burnup benchmark experiments from the spent fuel isotopic composition database SFCOMPO-2 (Spent Fuel Isotopic Composition Database), use component programs to build models and calculate, compare the calculated results with the experimental results, and evaluate the accuracy of the burnup calculation.

[0050] Example

[0051] 1. Syntax check of core physics multi-group constant library

[0052] The first is the format check. The base conversion program of the core physics multi-group constant library is used to convert the data of each nuclide contained in the multi-group constant library from decimal to binary and then back to decimal. The base conversion program is a tool that must be used for the development and use of the multi-group constant library. It is a well-known technology in the field. The specific implementation of the base conversion program is not introduced in detail here. The file comparison function of the text editor UltraEdit is used to compare the differences between the data before and after the conversion and record them in a file marked with the nuclide number. If the file size is 0, it means there is no difference and the format is correct. Otherwise, it means that there is a defect in the single nuclide data format. For the case of a large number of nuclides, a batch script can be written to automatically call the program to convert one by one, and summarize the results in a unified file.

[0053] After the format check, the data of each nuclide in the multi-group constant library is physically checked. In this part, a program is written according to the above formulas (1) to (6) to check the cross-section self-consistency and physical rationality of the multi-group constant library. The program is written in Fortran language. The main functions and specific writing methods of the program are introduced below. It should be clear to those skilled in the art that the functions of the program can also be implemented by other programming languages.

[0054] (1) Check the physical rationality of the data

[0055] It mainly checks whether there are non-positive values ​​in fission cross section, absorption cross section, scattering cross section, (n,2n) cross section, (n,3n) cross section, resonance integral and fission spectrum. If there are, it will give a prompt message. Taking the (n,2n) cross section check as an example, the check code of the Fortran program is as follows:

[0056]

[0057] Among them, n2 is the number of energy groups of the (n,2n) section. The program traverses all energy groups and counts the number of energy groups with non-positive values, and finally outputs a prompt message. The checking code for other cross-sectional data is similar to the above, and will not be repeated here.

[0058] (2) Check data consistency

[0059] The main purpose is to check the self-consistency of the total cross section, scattering cross section and fission spectrum, that is, whether they satisfy the above-mentioned formulas (1), (2) and (5). Taking the scattering cross section as an example, the checking code implemented in Fortran language is as follows:

[0060]

[0061] Among them, it is the temperature index, ig is the initial energy group index, ig2 is the secondary energy group index, mtr is the array storing the scattering matrix, summtr is the sum of the scattering matrix over the secondary energy group, and err is the deviation between the scattering cross section and the sum of the scattering matrix, through which the self-consistency between the scattering cross section and the scattering matrix can be judged. The self-consistency check of other cross sections is similar to the above, and will not be repeated here.

[0062] (3) Check for illegal characters

[0063] It mainly checks whether the data of each nuclide in the multi-group constant library contains illegal characters such as "NAN" and "INFINITY". If so, a prompt message will be given. The data types checked include energy group structure, fission spectrum, (n,2n) cross section, (n,3n) cross section, smooth resonance cross section, resonance integral, data required for transport, burnup data, high-order scattering cross section and matrix, neutron-to-photon cross section, photon-to-photon interaction cross section, etc. The following takes the check of (n,2n) cross section as an example. The code of the FORTRAN program is as follows:

[0064]

[0065] 2. Core physics multi-group constant library unit test

[0066] First, we design a test problem for the component program of the multi-group constant library, and design a component program that can calculate the k of an infinite homogeneous medium. ∞ Calculate the example problem and call the MCNP program to calculate the k of the test example problem. ∞ , as a reference solution. Secondly, call the component program to calculate the test example and compare it with the corresponding MCNP calculation results. Taking the MCNP calculation results as the benchmark, compare the calculation results of the component program, set the detection threshold to 300pcm, and record it as a large deviation if the ratio with the MCNP calculation results exceeds 0.3%. For example, the definition of the test example is given in the form of an MCNP input card. The test example is a mixture of U-235, H-1 and the nuclide to be tested, and the boundary condition is total reflection. Analyze the specific reasons for the nuclides with large deviations, and modify the corresponding data accordingly.

[0067] 3. Core physics multi-group constant library subsystem integration test

[0068] The matching components of the multi-group constant library are used to calculate the same burnup problem based on the compressed mass chain and the fine mass chain respectively, and the accumulation of all nuclides on the compressed mass chain is solved and compared with the calculation results of the complete burnup chain. The rationality of the compression of the compressed chain and the accuracy of the burnup data are determined according to the deviation of the comparison. For example, by comparing the accumulation of all burnup nuclides, if the deviation of the accumulation of burnup nuclides calculated by the compressed chain and the complete burnup chain is less than 2%, it is considered that the compression of the compressed chain is reasonable and the burnup data is accurate. The burnup problem calculated by the component program can be an ideal problem or a burnup benchmark problem for the application scenario of the multi-group constant library. Here, the HMT011.36 device in the International Nuclear Criticality Safety Manual is taken as an example. The device consists of 22 uranium-aluminum alloy plates of highly enriched uranium. The mass percentage of uranium is 25.56%, of which 235 The mass fraction of U is 93%. The calculated burnup depth is 300GWd / tU, and the full power operation time is 5 years. Since the input format of the burnup problem is related to the component program, the following takes the depletion module of the component program kylin-2 as an example to give a code programming example of using perl language to realize automatic modeling of the HMT011.36 device. It should be clear to those skilled in the art that this part of the data can also be automatically generated for other burnup programs using other programming languages, as shown below:

[0069]

[0070] After modeling is completed, the program can be directly called to calculate the selected fuel consumption problem, and the results can be extracted from the output file and compared.

[0071] 4. Core physics multi-group constant library integration test

[0072] On the one hand, based on the geometric calculation capability of the component program supporting the core physics multi-group constant library and the energy spectrum range commonly used in reactor calculations, fast spectrum, intermediate energy spectrum, and thermal spectrum benchmark experiments were selected from the International Nuclear Criticality Safety Manual ICSBEP2006 and the Cross-Section Evaluation Working Group Benchmark Experiment Manual ENDF-20 to carry out critical benchmark inspections of the core physics multi-group constant library. On the other hand, the burnup benchmark experiment was selected from the spent fuel isotope composition database SFCOMPO-2, and the component program was used for modeling and calculation. The calculation results were compared with the experimental results to evaluate the accuracy of the burnup calculation.

[0073] The criticality benchmark test and the fuel consumption benchmark test involve multiple benchmark problems. Here, the Godiva benchmark problem in ICSBEP is used as a representative to introduce the criticality benchmark test, and the SF95 benchmark problem in SFCOMPO-2 is used as a representative to introduce the fuel consumption benchmark test. The experimental information of the Godiva benchmark problem is shown in Table 1. The modeled geometric model is shown in Figure 2As shown, the radius is 0.5 cm, the grid length is 1 cm, total reflection boundary conditions are defined around it, and the calculation temperature is defined as 300K.

[0074] Table 1 Godiva benchmark test information

[0075]

[0076] The material definition uses the nucleon density (10 24 / cm 3 ) and mass percentage (%), fuel is defined as a combustible material. The material nucleon density of the Godiva benchmark is shown in Table 2.

[0077] Table 2 Nucleon density of Godiva benchmark materials

[0078]

[0079] After completing the modeling based on the above information, call the component program to perform calculations and extract the K eff The data are compared with the benchmark value, and based on the comparison results, it is analyzed whether the data needs to be improved and how to improve it.

[0080] Fuel consumption benchmark question SF95 fuel is UO 2 The fuel cladding is low-tin Zr-4 alloy. The material composition is shown in Table 3. The outer diameter of the fuel rod cladding is 9.5mm, the inner diameter is 8.22mm, and the diameter of the fuel pellet is 8.05mm. The core operating pressure is 16MPa, and the coolant inlet and outlet temperatures are 284℃ and 321℃ respectively.

[0081] Table 3 SF95 sample fuel and cladding material information

[0082]

[0083] A single cell calculation model is used to simulate the real SF95 sample. The outer radius of the cladding is 0.475 cm, the radius of the fuel area is 0.411 cm, the cell side length is 1.26 cm, and the two-dimensional geometric model is as follows: Figure 3 The fuel calculation temperature is defined as 900K and the cladding temperature is 600K.

[0084] Three elements are considered for moderator materials: 1H, 16O, and 10B. In actual core operation, the moderator boron concentration changes with burnup. Therefore, when defining the material, the mass ratio is used to define the moderator boron concentration at each burnup calculation point. The data on the change of boron concentration with burnup can be queried in the SFCOMPO 2.0 database. For data that cannot be directly obtained at the calculation point, linear interpolation is used to obtain the corresponding boron concentration value. The specific boron concentration value settings are shown in Table 4.

[0085] Table 4 Calculation of the mass ratio of moderator nuclei at the burnup point

[0086]

[0087]

[0088] In the calculation, the burnup value used in each step is defined according to the power change time point given by the SFCOMPO-2.0 database. It is worth noting that at different burnup calculation points, not only are the burnup values ​​different, but the moderator material and power also change accordingly.

[0089] Based on the above information, the component program is used to model and calculate the SF95 benchmark problem, the nuclide nuclide density is calculated and compared with the corresponding experimental benchmark value, and the data is analyzed based on the comparison to determine whether there are any problems and how to improve them.

[0090] Those skilled in the art will readily conceive of other embodiments of the present invention after considering the specification and practicing the invention disclosed herein. This application is intended to cover any variations, uses or adaptations of the present invention that follow the general principles of the present invention and include common knowledge or customary techniques in the art that are not disclosed by the present invention. Thus, if these variations and use adaptations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is also intended to include these modifications and use adaptations.

[0091] The above embodiments are merely illustrative of the present invention, and the present invention may also be implemented in other specific ways or other specific forms without departing from the gist or essential features of the present invention. Therefore, the described embodiments should be considered illustrative rather than restrictive in any respect. The scope of the present invention should be described by the appended claims, and any changes equivalent to the intent and scope of the claims should also be included within the scope of the present invention.

Claims

1. A core physics multi-group constant library testing method, comprising the following steps: (1) Perform single-nuclide format check and single-nuclide physical check to confirm that the single-nuclide data can be read and format converted normally, as well as the physical rationality, self-consistency and availability of each nuclide data; the single-nuclide physical check shall ensure that the data of each nuclide satisfies the following formula: s t =s a +s s s f ,s 0,s ,s n2n ,s n3n ,...>0 I g ＞0 Where σ is the cross section, and the subscripts t, a, s, f, n2n, and n3n represent total, absorption, scattering, fission, (n, 2n) reaction, and (n, 3n) reaction, respectively. 0,S represents the 0th-order scattering cross section, represents the fission energy spectrum, I represents the resonance integral, g represents the exit energy group, and g' represents the arrival energy group; (2) performing a single nuclide data availability test to confirm that each nuclide can be used normally for calculations; the single nuclide data availability test is to calculate the infinite multiplication coefficient of the mixture formed by U-235, H-1 and the nuclide to be tested, and compare it with the Monte Carlo calculation results based on homologous data; (3) Carry out a burnup chain test to check the applicability of the burnup chain compression and the accuracy of the burnup data; the method of the burnup chain test is to calculate the same burnup problem based on the compression chain and the fine chain respectively, solve the accumulation of all nuclides on the compression chain and compare it with the calculation result of the complete burnup chain, and determine the rationality of the compression of the compression chain and the accuracy of the burnup data according to the deviation of the comparison; (4) Carry out criticality benchmark inspection and fuel consumption benchmark inspection.

2. The core physics multi-group constant library testing method according to claim 1, characterized in that: The method for checking the single nuclide format described in step (1) is to use the base conversion program of the multi-group constant library to convert the single nuclide decimal data into binary, then convert it back to decimal, and compare the difference between the data before and after the conversion.

3. The core physics multi-group constant library testing method according to claim 1, characterized in that: In step (1), it is also checked whether there are any illegal characters that cannot be used in the single nuclide data.

4. The core physics multi-group constant library testing method according to claim 1, characterized in that: In step (2), the Monte Carlo calculation result is used as a benchmark to compare the single nuclide data availability test calculation result of the core physics multi-group constant library, and a detection threshold is set. If the ratio of the Monte Carlo calculation result exceeds the detection threshold, it is recorded as excessive deviation; Analyze the reasons for large deviations and make corresponding corrections to the single nuclide data based on the analysis results.

5. The core physics multi-group constant library testing method according to claim 1, characterized in that: The critical benchmark test described in step (4) is to select fast spectrum, intermediate energy spectrum, and thermal spectrum benchmark experiments from the International Nuclear Criticality Safety Manual ICSBEP2006 and the Cross-Section Evaluation Working Group Benchmark Experiment Manual ENDF-202 to test the core physics multi-group constant library, model and calculate the selected benchmark questions, and compare them with the experimental benchmark values.

6. The core physics multi-group constant library testing method according to claim 5, characterized in that: When performing the critical benchmark test in step (4), the infinite multiplication factor k of the spherical device is inf Monte Carlo infinite uniform medium proliferation factor calculation results k inf.cal and effective proliferation factor k eff.cal With the reference value k eff.exp According to the geometric relationship, the formula is as follows:

7. The core physics multi-group constant library testing method according to claim 1, characterized in that: The burnup benchmark test described in step (4) is to select a burnup benchmark experiment from the spent fuel isotope composition database SFCOMPO-2, perform modeling and calculation, compare the calculated results with the experimental results, and evaluate the accuracy of the burnup calculation.

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