Complex reactor core collaborative design system suitable for research reactor

Abstract

The invention provides a complex reactor core collaborative design system suitable for a research reactor, relates to the technical field of reactor core design systems, aims to improve the reliability of reactor core design, and comprises a model library module, a model database module, a model database module and a model database module, the model library comprises a reactor model library and an irradiation device model library; the interactive interface module is used for realizing interactive operation; the reactor core scheme design module is used for carrying out autonomous initialization design on a reactor core, and solving the problem of fuel assembly and target position loss caused by pore channel opening operation and the area demand of a newly added beryllium aluminum assembly caused by pore channel closing operation; and the reactor core scheme evaluation module is used for evaluating the reactor core. The method has the advantages of being intelligent in design, easy to operate and reliable in design quality.

Description

Technical Field

[0001] The present invention relates to the technical field of core design systems, and in particular to a complex core collaborative design system suitable for research reactors. Background Art

[0002] With the continuous progress of reactor physical thermal analysis methods, computer technology, and intelligent algorithms, reactor core design has gradually shifted from relying entirely on manual operation and experience to collaborative processing and intelligent design.

[0003] In order to make up for the deficiencies of the existing core design of research reactors in data management, multi-professional collaboration, and intelligent optimization, efficient data management, comprehensive demonstration of multi-dimensional parameters, coupling integration of multi-professional software, and intelligent support of the design process in the core design of research reactors are realized. Therefore, based on the HFETR core design, a complex core collaborative design system is developed. In the existing scheme design, the switching material table requires manual filling of the gate cell number of the component to be replaced to the gate cell position where the component needs to be placed in the end, and then filling in the displaced gate cell number to the gate cell position where the component needs to be replaced, which is prone to errors. A visual interface has also been developed, but it uses a fill-in display, which requires manual selection and adjustment of the component type in the gate cell. The workload is still very large, and there is still a risk that the component type in the original gate cell does not change after the replacement.

[0004] Therefore, it is necessary to optimize the core design method to improve the reliability of the core design. Summary of the invention

[0005] The object of the present invention is to provide a complex core collaborative design system suitable for research reactors, which can improve the reliability of core design.

[0006] The present invention is achieved through the following technical solutions:

[0007] A complex core collaborative design system for research reactors, including:

[0008] A model library module, including a model library established based on different research reactors and various types of irradiation test pieces in the reactors, wherein the model library includes a reactor model library and an irradiation device model library;

[0009] Interactive interface module, used to implement interactive operations;

[0010] The core scheme design module is used to perform autonomous initialization design of the core and solve the problem of missing fuel assemblies and target positions caused by the hole opening operation and the regional demand for additional beryllium aluminum assemblies caused by the hole closing operation;

[0011] The core scheme evaluation module is used to evaluate the core.

[0012] Preferably, the reactor model library and the irradiation device model library both include characteristic units and non-characteristic units;

[0013] The method for establishing the characteristic unit is to establish it through structural parameters, cross-sectional parameters and thermophysical property parameters;

[0014] The method for establishing the non-characteristic unit is to establish it based on the irradiation test object, boundary conditions, key physical and thermal parameters and data processing methods according to the actual irradiation task objectives and actual engineering needs.

[0015] Preferably, the interactive interface module includes:

[0016] The solution information area is used to select the reactor type, determine the reactor operating power and fuel quantity, and provide the path to the core design file;

[0017] The core initialization area is used to determine the number of new fuels, the number of targets entering and exiting, and the switch information of the irradiation channels in the core, and to realize the initialization of the core design;

[0018] Intelligent optimization area, used to achieve core optimization design through intelligent methods;

[0019] The thermal model area is used to determine the irradiated parts, boundary conditions and irradiation mission objectives corresponding to each irradiation channel in the core, and to realize the thermal calculation, analysis and evaluation of each irradiated part;

[0020] The design operation area is used to determine the position of the grid element components by dragging operations, realize the operation of the core layout plan and the pre-operation review, core thermal calculation and Monte Carlo simulation modeling and detailed calculation functions.

[0021] Preferably, the interactive interface module further includes:

[0022] The design process area is used to view the shift sequence information of each gate element component in the entire design process;

[0023] Visualization area, used to view the core design diagram and neutron injection rate distribution diagram;

[0024] The scheme comparison area is used to compare information of different core designs.

[0025] Preferably, the method for autonomously initializing the core comprises:

[0026] Carry out fuel rearrangement optimization;

[0027] Target rearrangement optimization is performed.

[0028] Preferably, the method for optimizing fuel rearrangement is:

[0029] Obtain the calculated fuel burnup value at the end of the life of the previous furnace section, sort the fuel burnup values ​​at different positions in the previous furnace in order from deep to shallow, obtain the total amount of fuel in the next furnace section and the amount of newly added fuel, replace the fuel in the previous furnace whose fuel burnup value is greater than a preset threshold with the newly added fuel, and obtain a new fuel plan;

[0030] According to the order of fuel burnup values ​​at the end of the life of the previous furnace from deep to shallow, the n newly-input fuels in the new fuel scheme are placed at the positions of the n groups of fuels with the shallowest burnup in the previous furnace section, and the fuel with the deepest fuel burnup value among the remaining fuels in the new fuel scheme is placed at the position of the fuel with the deepest burnup corresponding to the previous furnace, and the positions of the fuels in the scheme are readjusted in order from deep to shallow.

[0031] Preferably, the method for performing target rearrangement optimization is:

[0032] Obtain the number of newly entered targets, sort the targets in the previous furnace in descending order of target burnup, and replace the targets in the previous furnace whose burnup exceeds a preset threshold with the newly entered targets;

[0033] According to the target arrangement information of the previous furnace, the targets are rearranged in the order of burnup from deep to shallow.

[0034] Preferably, the method for solving the problem of missing fuel assembly and target position caused by the hole opening operation and the regional demand for additional beryllium aluminum assembly caused by the hole closing operation is:

[0035] When a new channel is opened, the nearest position of the original fuel assembly or the original target at the channel position is searched, and it is determined whether the nearest position is a beryllium assembly, an aluminum assembly, or a stainless steel assembly; if so, the original fuel assembly or the original target at the channel position is moved to the position, and the original assembly at the position is removed from the stack; if not, the search continues for a position at a farther distance until the position of the beryllium assembly, the aluminum assembly, or the stainless steel assembly is found, the original fuel assembly or the original target at the channel position is moved to the position, and the original assembly at the position is removed from the stack;

[0036] When the hole closure is executed, the historical fuel management program design input file is searched, and if the hole was once the location of a fuel assembly or target, it is filled with a beryllium assembly.

[0037] Preferably, the method for evaluating the core is:

[0038] A collaborative processing approach is adopted to generate files that meet the access specifications of various thermal analysis and evaluation programs, and the core limit power analysis and physical thermal calculation analysis of each irradiated component are performed according to parallel instruction iterations.

[0039] Preferably, according to the output files of each thermal program, the key physical thermal parameters of each irradiated part are collated, analyzed and generated, and the key physical thermal parameters are recorded and displayed in a text format and a visual interface.

[0040] The technical solution of the present invention has at least the following advantages and beneficial effects:

[0041] The system structure of the present invention is simple, and it is convenient for various subsequent research reactors to efficiently assist designers in carrying out core design work when performing irradiation production tasks;

[0042] The core scheme design module of the present invention can efficiently realize the in-core reconstruction design after material replacement and hole opening, while avoiding defects caused by hole opening or hole filling, thereby improving the reliability of the design;

[0043] The design of the present invention can be realized automatically by directly extracting new data, which greatly speeds up the efficiency of switching materials and roughly adjusting the scheme by scheme designers;

[0044] The present invention can realize visual display and design backtracking, which is convenient for more comprehensive display of design results and design process;

[0045] The present invention is reasonably designed and can also realize the evaluation of the core design and display the evaluation results, which is helpful to strengthen the analysis of the core. BRIEF DESCRIPTION OF THE DRAWINGS

[0046] Figure 1 This is a schematic diagram of the structure of the interactive interface module provided in Example 1 of the present invention. DETAILED DESCRIPTION

[0047] In order to make the purpose, technical solutions and advantages of the embodiments of the present invention clearer, the technical solutions in the embodiments of the present invention will be clearly and completely described below in conjunction with the drawings in the embodiments of the present invention. Obviously, the described embodiments are part of the embodiments of the present invention, not all of the embodiments. Generally, the components of the embodiments of the present invention described and shown in the drawings here can be arranged and designed in various different configurations.

[0048] Example 1

[0049] This embodiment provides a complex core collaborative design system suitable for research reactors, see Figure 1 ,include:

[0050] A model library module, including a model library established based on different research reactors and various types of irradiation test pieces in the reactors, wherein the model library includes a reactor model library and an irradiation device model library;

[0051] Interactive interface module, used to implement interactive operations;

[0052] The core scheme design module is used to perform autonomous initialization design of the core and solve the problem of missing fuel assemblies and target positions caused by the hole opening operation and the regional demand for additional beryllium aluminum assemblies caused by the hole closing operation;

[0053] The core scheme evaluation module is used to evaluate the core.

[0054] In this embodiment, the reactor model library and the irradiation device model library both include characteristic units and non-characteristic units;

[0055] The method for establishing the characteristic unit is to establish it through structural parameters, cross-sectional parameters and thermophysical property parameters;

[0056] The method for establishing the non-characteristic unit is to establish it based on the irradiation test object, boundary conditions, key physical and thermal parameters and data processing methods according to the actual irradiation task objectives and actual engineering needs.

[0057] On the other hand, see Figure 1 , the interactive interface module includes:

[0058] The solution information area is used to select the reactor type, determine the reactor operating power and fuel quantity, and provide the path to the core design file;

[0059] The core initialization area is used to determine the number of new fuels, the number of targets entering and exiting, and the switch information of the irradiation channels in the core, and to realize the initialization of the core design;

[0060] Intelligent optimization area, used to achieve core optimization design through intelligent methods such as genetic algorithms, neural networks, etc.;

[0061] The thermal model area is used to determine the irradiated parts, boundary conditions and irradiation mission objectives corresponding to each irradiation channel in the core, and to realize the thermal calculation, analysis and evaluation of each irradiated part;

[0062] The design operation area is used to determine the position of the grid element components by dragging operations, realize the operation of the core layout plan and the pre-operation review, core thermal calculation and Monte Carlo simulation modeling and detailed calculation functions.

[0063] Furthermore, the interactive interface module also includes:

[0064] The design process area is used to view the shift sequence information of each gate element component in the entire design process;

[0065] Visualization area, used to view the core design diagram and neutron injection rate distribution diagram. Specifically, the core design diagram can display information such as the type of grid element components in the core, output, burnup, rod position, maximum non-uniformity coefficient, channel neutron injection rate, and key physical and thermal parameters of different irradiated parts;

[0066] The scheme comparison area is used to compare information of different core designs. In actual operation, they can be compared and sorted according to whether key physical and thermal parameters are met.

[0067] As a preferred solution, the method for autonomously initializing the core includes:

[0068] Carry out fuel rearrangement optimization;

[0069] Target rearrangement optimization is performed.

[0070] Preferably, the method for optimizing fuel rearrangement is:

[0071] Obtain the calculated fuel burnup value at the end of the life of the previous furnace section, sort the fuel burnup values ​​at different positions in the previous furnace in order from deep to shallow, obtain the total amount of fuel in the next furnace section and the amount of newly added fuel, replace the fuel in the previous furnace whose fuel burnup value is greater than a preset threshold with the newly added fuel, and obtain a new fuel plan;

[0072] According to the order of fuel burnup values ​​at the end of the life of the previous furnace from deep to shallow, the n newly-input fuels in the new fuel scheme are placed at the positions of the n groups of fuels with the shallowest burnup in the previous furnace section, and the fuel with the deepest fuel burnup value among the remaining fuels in the new fuel scheme is placed at the position of the fuel with the deepest burnup corresponding to the previous furnace, and the positions of the fuels in the scheme are readjusted in order from deep to shallow.

[0073] Specifically, the method for optimizing the target rearrangement is:

[0074] Obtain the number of newly entered targets, sort the targets in the previous furnace in descending order of target burnup, and replace the targets in the previous furnace whose burnup exceeds a preset threshold with the newly entered targets;

[0075] According to the target arrangement information of the previous furnace, the targets are rearranged in the order of burnup from deep to shallow.

[0076] In addition, the method for solving the problem of missing fuel assembly and target position caused by the hole opening operation and the regional demand for additional beryllium aluminum assemblies caused by the hole closing operation can be:

[0077] When a new channel is opened, the nearest position of the original fuel assembly or the original target at the channel position is searched, and it is determined whether the nearest position is a beryllium assembly, an aluminum assembly, or a stainless steel assembly; if so, the original fuel assembly or the original target at the channel position is moved to the position, and the original assembly at the position is removed from the stack; if not, the search continues for a position at a farther distance until the position of the beryllium assembly, the aluminum assembly, or the stainless steel assembly is found, the original fuel assembly or the original target at the channel position is moved to the position, and the original assembly at the position is removed from the stack;

[0078] When the hole closure is executed, the historical fuel management program design input file is searched, and if the hole was once the location of a fuel assembly or target, it is filled with a beryllium assembly.

[0079] Finally, the method for evaluating the core is preferably:

[0080] A collaborative processing approach is adopted to generate files that meet the access specifications of various thermal analysis and evaluation programs, and the core limit power analysis and physical thermal calculation analysis of each irradiated component are performed according to parallel instruction iterations.

[0081] When evaluating the core, this embodiment can also output files according to each thermal program, organize and analyze and generate key physical thermal parameters of each irradiated part, and record and display the key physical thermal parameters in text format and a visual interface.

[0082] Example 2

[0083] This embodiment provides a case of specific operations based on the interactive interface module of the complex core collaborative design system for HFETR applied to other embodiments. The main steps are as follows:

[0084] Step 1: Start the complex core collaborative design system, click to enter the core design interface, in the scheme information area, you can enter the file storage path of the fuel management program (other physical thermal calculation and analysis programs are stored in the complex core design system subdirectory by default), and give the design furnace section, reactor type, reactor design power and fuel quantity. If the basic information of the current design scheme is consistent with the previous scheme, the user can easily click the "Default" button, and the system will automatically fill in all basic scheme information. After confirming that all basic scheme data are correct, click the "Update" button to enter the basic information of the scheme into the system.

[0085] Step 2: In the core initialization area, according to the design requirements, enter the number of new fuels, fuel numbers, number of new targets, target limit, number of new opening channels, number of new closing channels, etc. After confirming that the core initialization information is correct, click the "Initialize" button to complete the initialization layout of the scheme. In particular, if the initialization design of the core loading scheme has been completed before, step 2 is not required and you can jump to step 3.

[0086] Step 3: In the intelligent optimization area, choose whether to enable advanced optimization algorithms to further optimize the solution based on your actual needs. If you decide to use the optimization algorithm, you can also rely on historical experience or feedback results after optimization to fine-tune the algorithm parameters in the advanced settings to achieve more accurate design optimization. When it does not involve the complex constraints and optimization goals brought about by the key physical and thermal parameters of many irradiation devices, you can simply use the "Intelligent Optimization" button to enable the system to automatically start core intelligent optimization. If you want to involve the impact of each irradiation device, you need to complete step 4 and then click the "Intelligent Optimization" button.

[0087] Step 4: In the thermal model area, you can complete the key input information of core thermal and irradiation device thermal according to the design requirements, including reactor inlet water temperature, fuel cladding maximum temperature limit, physical output file number corresponding to each irradiation device, irradiation target type, irradiation target parameter range, calculation deviation, inlet water temperature and flow rate, etc. If the current thermal model parameters are consistent with the previous scheme, you can easily click the "Default" button, and the system will automatically fill in all thermal model parameters. After confirming that all thermal model parameters are correct, click the "Model Access" button to enter the thermal model information into the system.

[0088] Step 5: If intelligent optimization is not used in step 3, in this step, you can use the drag-and-drop scheme adjustment method to carry out the design optimization of the core scheme based on your own scheme design experience. Through the "View" button, the system will automatically generate visual information of the current scheme to be optimized. Through the "Clear" button, the system will clear all gate element transposition information (the gate element transposition information and operation sequence are displayed in the design process area, and the gate element transposition information and sequence in the design process area can also be directly adjusted). If you click the "Save" button, the system will save the design scheme adjusted by the user and overwrite the original scheme. If you click the "Run" button, the system will call and run the fuel management program. After the fuel management program is finished running, the visual information of the new core design scheme will be automatically generated. At this time, if you choose to click the "Thermal Calculation" button, the system will call the reactor-specific thermal-hydraulic analysis program and the thermal-hydraulic analysis programs of different irradiation devices, and carry out parallel calculations; if you click the "Material Calculation" button, the system will automatically generate a calculation file of the Monte Carlo model from the core loading information of the fuel management program, and call the Monte Carlo program for simulation to obtain the precise parameter information of the medium-photon local irradiation device.

[0089] Step 6: After the core scheme is run, the visualization information of the new core design scheme will be automatically generated and displayed in the visualization area. The visualization information includes the component type of each grid element of the core scheme, the net increase of fuel assembly burnup, end-of-life burnup, target activity information, key physical and thermal parameters of each irradiation device, control rod position information, core inhomogeneity factor, neutron flux information of local channels, etc. Users can select "Neutron Fluence Rate Diagram" and click the "Switch" button to view the fast thermal neutron flux rate field of the entire core.

[0090] Step 7: After running the scheme, you can compare different operation schemes in the scheme comparison area as needed. Select the scheme to be compared in "Scheme Selection", select the main comparison information in "Gate Element Selection", "Channel Selection" and "Parameter Selection", and click the "Compare" button to generate a core design scheme comparison table.

[0091] The above are only preferred embodiments of the present invention and are not intended to limit the present invention. For those skilled in the art, the present invention may have various modifications and variations. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present invention shall be included in the protection scope of the present invention.

Claims

1. A complex core collaborative design system suitable for research reactors, characterized in that: include: A model library module, including a model library established based on different research reactors and various types of irradiation test pieces in the reactors, wherein the model library includes a reactor model library and an irradiation device model library; Interactive interface module, used to implement interactive operations; The core scheme design module is used to perform autonomous initialization design of the core and solve the problem of missing fuel assemblies and target positions caused by the hole opening operation and the regional demand for additional beryllium aluminum assemblies caused by the hole closing operation; The core scheme evaluation module is used to evaluate the core.

2. A complex core collaborative design system suitable for a research reactor according to claim 1, characterized in that: The reactor model library and the irradiation device model library both include characteristic units and non-characteristic units; The method for establishing the characteristic unit is to establish it through structural parameters, cross-sectional parameters and thermophysical property parameters; The method for establishing the non-characteristic unit is to establish it based on the irradiation test object, boundary conditions, key physical and thermal parameters and data processing methods according to the actual irradiation task objectives and actual engineering needs.

3. A complex core collaborative design system suitable for a research reactor according to claim 1, characterized in that: The interactive interface module includes: The solution information area is used to select the reactor type, determine the reactor operating power and fuel quantity, and provide the path to the core design file; The core initialization area is used to determine the number of new fuels, the number of targets entering and exiting, and the switch information of the irradiation channels in the core, and to realize the initialization of the core design; Intelligent optimization area, used to achieve core optimization design through intelligent methods; The thermal model area is used to determine the irradiated parts, boundary conditions and irradiation mission objectives corresponding to each irradiation channel in the core, and to realize the thermal calculation, analysis and evaluation of each irradiated part; The design operation area is used to determine the position of the grid element components by dragging operations, realize the operation of the core layout plan and the pre-operation review, core thermal calculation and Monte Carlo simulation modeling and detailed calculation functions.

4. A complex core collaborative design system suitable for a research reactor according to claim 3, characterized in that: The interactive interface module also includes: The design process area is used to view the shift sequence information of each gate element component in the entire design process; Visualization area, used to view the core design diagram and neutron injection rate distribution diagram; The scheme comparison area is used to compare information of different core designs.

5. A complex core collaborative design system suitable for a research reactor according to claim 1, characterized in that: The method for autonomously initializing the core comprises: Carry out fuel rearrangement optimization; Target rearrangement optimization is performed.

6. A complex core collaborative design system suitable for a research reactor according to claim 5, characterized in that: The method for optimizing fuel rearrangement is as follows: Obtain the calculated fuel burnup value at the end of the life of the previous furnace section, sort the fuel burnup values ​​at different positions in the previous furnace in order from deep to shallow, obtain the total amount of fuel in the next furnace section and the amount of newly added fuel, replace the fuel in the previous furnace whose fuel burnup value is greater than a preset threshold with the newly added fuel, and obtain a new fuel plan; According to the order of fuel burnup values ​​at the end of the life of the previous furnace from deep to shallow, the n newly-input fuels in the new fuel scheme are placed at the positions of the n groups of fuels with the shallowest burnup in the previous furnace section, and the fuel with the deepest fuel burnup value among the remaining fuels in the new fuel scheme is placed at the position of the fuel with the deepest burnup corresponding to the previous furnace, and the positions of the fuels in the scheme are readjusted in order from deep to shallow.

7. A complex core collaborative design system suitable for a research reactor according to claim 6, characterized in that: The method for performing target rearrangement optimization is: Obtain the number of newly entered targets, sort the targets in the previous furnace in descending order of target burnup, and replace the targets in the previous furnace whose burnup exceeds a preset threshold with the newly entered targets; According to the target arrangement information of the previous furnace, the targets are rearranged in the order of burnup from deep to shallow.

8. A complex core collaborative design system suitable for a research reactor according to claim 7, characterized in that: The method for solving the problem of missing fuel assembly and target position caused by the hole opening operation and the regional demand for additional beryllium aluminum assemblies caused by the hole closing operation is: When a new channel is opened, the nearest position of the original fuel assembly or the original target at the channel position is found, and it is determined whether the nearest position is a beryllium assembly, an aluminum assembly or a stainless steel assembly; If yes, the original fuel assembly or original target at the hole position is moved to the position, and the original assembly at the position is removed from the stack; if no, continue to search for a position farther away until the position of the beryllium assembly, aluminum assembly or stainless steel assembly is found, and the original fuel assembly or original target at the hole position is moved to the position, and the original assembly at the position is removed from the stack; When the hole closure is executed, the historical fuel management program design input file is searched, and if the hole was once the location of a fuel assembly or target, it is filled with a beryllium assembly.

9. A complex core collaborative design system suitable for a research reactor according to claim 1, characterized in that: The method for evaluating the core is: By adopting the collaborative processing method, files that meet the access specifications of various thermal analysis and evaluation programs are generated, and the core limit power analysis and the physical thermal calculation analysis of each irradiated component are performed according to the parallel instruction iteration; According to the output files of each thermal program, the key physical thermal parameters of each irradiated part are sorted, analyzed and generated.

10. A complex core collaborative design system suitable for a research reactor according to claim 1, characterized in that: The key physical and thermal parameters are recorded and displayed through text format and visual interface.

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