A complex core co-design system suitable for research reactors

Abstract

The application provides a complex reactor core collaborative design system suitable for research reactors, relates to the technical field of reactor core design systems, and aims to improve the reliability of reactor core design, and comprises a model library module, a reactor core scheme design module, a reactor core scheme evaluation module and an interactive interface module. The model library module comprises a reactor model library and an irradiation device model library, and is established based on different research reactors and various types of irradiation test pieces in the reactors. The reactor core scheme design module is used for independently initializing and designing the reactor core, solving the problems of missing fuel assemblies and target piece positions caused by channel opening operation, and solving the regional demand of newly added beryllium aluminum assemblies caused by channel closing operation. The reactor core scheme evaluation module is used for evaluating the reactor core. The application has the advantages of intelligent design, easy operation and reliable design quality.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of reactor core design systems, in particular to a complex reactor core collaborative design system suitable for research reactors. BACKGROUND

[0002] With the continuous progress of reactor physics thermal analysis methods, computer technology, intelligent algorithms, and the like, reactor core design gradually changes from complete reliance on manual operation and experience to collaborative processing and intelligent design.

[0003] To make up for the deficiencies of the existing reactor core design in data management, multi-specialty collaboration, intelligent optimization, and the like, and to achieve efficient data management, comprehensive demonstration of multi-dimensional parameters, coupling and integration of multi-specialty software, and intelligent support of the design process in the reactor core design of research reactors, a complex reactor core collaborative design system is developed based on the HFETR reactor core design. In the existing scheme design, the fuel assembly numbers of the cells where the components need to be transposed are manually filled in the cell positions where the components finally need to be placed, and then the cell numbers of the cells that are transposed are filled in the cell positions where the components need to be transposed, which is prone to errors.

[0004] Therefore, it is necessary to optimize the reactor core design method and improve the reliability of the reactor core design. SUMMARY

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

[0006] The present application is implemented by the following technical solutions:

[0007] A complex reactor core collaborative design system suitable for research reactors comprises:

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

[0009] An interactive interface module for realizing interactive operation;

[0010] A reactor core scheme design module for autonomously initializing the design of the reactor core and solving the problems of missing fuel assembly and target piece positions caused by channel opening operation and the regional requirements of newly added beryllium aluminum components caused by channel closing operation;

[0011] A reactor core scheme evaluation module for evaluating the reactor core.

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

[0013] The characteristic units are established by structural parameters, cross-sectional parameters and thermal physical parameters;

[0014] The non-characteristic units are established according to actual irradiation task targets and actual engineering needs based on irradiation test objects, boundary conditions, key physical and thermal parameters and data processing methods.

[0015] Preferably, the interactive interface module comprises:

[0016] A scheme information area for selecting a reactor type, determining a reactor operation power and a fuel number and providing a path of a core design file;

[0017] A core initialization area for determining a new fuel number, a target number and core irradiation channel switching information and realizing core design initialization;

[0018] An intelligent optimization area for realizing core optimization design by an intelligent method;

[0019] A thermal model area for determining irradiation objects, boundary conditions and irradiation task targets corresponding to each irradiation channel in the core and realizing thermal calculation, analysis and evaluation of each irradiation object;

[0020] A design operation area for determining a lattice assembly position by a drag operation and realizing functions of core layout scheme operation, pre-operation viewing, core thermal calculation and Monte Carlo simulation modeling and fine calculation.

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

[0022] A design process area for viewing displacement sequence information of each lattice assembly in the entire design process;

[0023] A visualization area for viewing a core design diagram and a neutron fluence rate distribution diagram;

[0024] A scheme comparison area for comparing different core design information.

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

[0026] Performing fuel rearrangement optimization;

[0027] Performing target rearrangement optimization.

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

[0029] The fuel burnup calculation value at the end of the life of the previous furnace section is obtained, the fuel burnup values at different positions in the previous furnace are sorted in order from deep to shallow, the total number of fuel in the next furnace section and the number of new fuel are obtained, the fuel with a fuel burnup value greater than a preset threshold in the previous furnace is replaced by the new fuel, and a new fuel scheme is obtained.

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

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

[0032] The number of new targets is obtained, the targets in the previous furnace are sorted in order from deep to shallow according to the target burnup, and the targets with a burnup exceeding a preset threshold in the previous furnace are replaced by new targets.

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

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

[0035] When a new channel is executed, the nearest position of the original fuel assembly or the original target at the position of the channel is found, and it is judged 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 position of the channel is moved to the position, and the original assembly at the position is removed from the stack; if not, the position of the beryllium assembly, the aluminum assembly or the stainless steel assembly is found by searching for a more distant position, and the original fuel assembly or the original target at the position of the channel is moved to the position, and the original assembly at the position is removed from the stack.

[0036] When a channel is closed, a historical fuel management program design input file is found, and if the channel has ever been the position of a fuel assembly or a target, a beryllium assembly is filled.

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

[0038] In a cooperative processing manner, a file meeting the access specification of each thermal analysis and evaluation program is generated, and the limit power analysis of the reactor core and the physical and thermal calculation analysis of each irradiated component are performed according to parallel instruction iteration.

[0039] Preferably, according to each thermal procedure output file, the key physical thermal parameters of each irradiation member are collated, analyzed and generated, and the key physical thermal parameters are recorded and displayed through a text format and a visual interface.

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

[0041] The system of the present application has a simple structure, and can efficiently assist designers in carrying out core design work when subsequent research reactors perform irradiation production tasks.

[0042] The core scheme design module of the present application can efficiently realize in-core reconstruction design after refueling and hole opening, and avoid defects caused by hole opening or hole filling, thereby improving the reliability of the design.

[0043] The design of the present application can be automatically realized by directly extracting new data, thereby greatly improving the efficiency of scheme designers in refueling and coarse adjustment.

[0044] The present application can realize visual display and design backtracking, and facilitate more comprehensive display of design results and design processes.

[0045] The present application has a reasonable design, and can realize evaluation of the core design and display of the evaluation results, thereby helping to strengthen the analysis of the core. BRIEF DESCRIPTION OF DRAWINGS

[0046] Figure 1 The structure schematic diagram of the interactive interface module provided for the embodiment 1 of the present application is shown. DETAILED DESCRIPTION

[0047] In order to make the purpose, technical scheme and advantages of the embodiments of the present application more clear, the technical scheme of the embodiments of the present application will be described clearly and completely below in combination with the drawings of the embodiments of the present application. Obviously, the described embodiments are part of the embodiments of the present application, rather than all the embodiments of the present application. The components of the embodiments of the present application described and shown in the drawings herein can be arranged and designed in various different configurations.

[0048] Embodiment 1

[0049] The present embodiment provides a complex core collaborative design system suitable for research reactors, referring to Figure 1 , comprising:

[0050] The model library module comprises a model library established based on different research reactors and various types of irradiation test members in the reactors, and the model library comprises a reactor model library and an irradiation device model library;

[0051] The interactive interface module is used for realizing interactive operation;

[0052] The core scheme design module is used for autonomously initializing design of the core and solving the problems of missing fuel assemblies and target pieces caused by channel opening operation and the regional requirement of newly added beryllium aluminum assemblies caused by channel closing operation.

[0053] The core scheme evaluation module is used for evaluating the core.

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

[0055] The characteristic units are established by structural parameters, cross-section parameters and thermophysical parameters.

[0056] The non-characteristic units are established according to actual irradiation task targets and actual engineering needs based on irradiation test objects, boundary conditions, key physical and thermophysical parameters and data processing methods.

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

[0058] The scheme information area is used for selecting a reactor type, determining a reactor operation power and a fuel number and providing a path of a core design file.

[0059] The core initialization area is used for determining a new fuel number, a target piece number and core irradiation channel switching information and realizing core design initialization.

[0060] The intelligent optimization area is used for realizing core optimization design by intelligent methods such as genetic algorithms, neural networks and the like.

[0061] The thermophysical model area is used for determining irradiation pieces, boundary conditions and irradiation task targets corresponding to each irradiation channel in the core and realizing thermophysical calculation, analysis and evaluation of each irradiation piece.

[0062] The design operation area is used for determining lattice assembly positions by drag operation, realizing core layout scheme operation and functions of pre-operation viewing, core thermophysical calculation and Monte Carlo simulation modeling and fine calculation.

[0063] Further, the interactive interface module further includes:

[0064] The design process area is used for viewing displacement sequence information of each lattice assembly in the entire design process.

[0065] The visualization area is used for viewing core design diagrams and neutron fluence rate distribution diagrams. Specifically, the core design diagrams can show information such as types, yields, burnup, rod positions, maximum non-uniformity coefficients, channel neutron fluence rates and key physical and thermophysical parameters of different irradiation pieces of the lattice assemblies in the core.

[0066] The scheme comparison region is used for comparing different core design information, and in actual operation, comparison and sorting can be performed according to the satisfaction of key physical and thermal parameters.

[0067] As a preferred scheme, the method for autonomously initializing the core design comprises:

[0068] Performing fuel rearrangement optimization;

[0069] Performing target rearrangement optimization.

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

[0071] Obtaining the fuel burnup calculation value at the end of the life of the previous furnace section, sorting the fuel burnup values at different positions in the previous furnace in order from deep to shallow, obtaining the total number of fuel in the next furnace section and the number of new fuel, replacing the fuel with a fuel burnup value greater than a preset threshold in the previous furnace with the new fuel to obtain a new fuel scheme;

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

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

[0074] Obtaining the number of new targets, sorting the targets in the previous furnace in order from deep to shallow according to the target burnup, and replacing the targets with a burnup exceeding a preset threshold in the previous furnace with new targets;

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

[0076] In addition, the method for solving the problem of missing fuel assemblies and targets caused by the opening operation and the regional demand for new beryllium-aluminum assemblies caused by the closing operation can be:

[0077] When a new opening channel is executed, the nearest position of the original fuel assembly or the original target at the position of the channel is found, 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 position of the channel is moved to the position, and the original assembly at the position is removed from the reactor; if not, the position is further searched until the position of the beryllium assembly, the aluminum assembly or the stainless steel assembly is found, and the original fuel assembly or the original target at the position of the channel is moved to the position, and the original assembly at the position is removed from the reactor.

[0078] When the closing channel is executed, the historical fuel management program design input file is searched, and if the channel was ever the location of a fuel assembly or target, both are filled with beryllium assemblies.

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

[0080] In a collaborative processing manner, files meeting the access specifications of various thermal analysis and evaluation programs are generated, and limit power analysis of the reactor core and physical and thermal calculation analysis of each irradiated component are performed according to parallel instruction iteration.

[0081] When the reactor core is evaluated in this embodiment, key physical and thermal parameters of each irradiated component can also be sorted, analyzed, and generated according to the output files of various thermal programs, and the key physical and thermal parameters are recorded and displayed through a text format and a visual interface.

[0082] Embodiment 2

[0083] This embodiment provides a case of a complex reactor core collaborative design system suitable for HFETR based on an interactive interface module for specific operation, and the following are the main steps:

[0084] Step 1: Start the complex reactor core collaborative design system, click into the reactor core design interface, and in the scheme information area, input the file storage path of the fuel management program (the remaining physical and thermal calculation analysis programs are stored in the subdirectory of the complex reactor core design system by default), and give the design reactor section, reactor type, reactor design power, and fuel number. If the basic information of the current design scheme is consistent with that of the previous scheme, the user can conveniently click the “default” button, and the system will automatically fill in all the basic scheme information. After confirming that all the basic scheme data is accurate, click the “update” button to record the basic scheme information into the system.

[0085] Step 2: In the reactor core initialization area, according to the design needs of the scheme, input the number of new fuel, fuel number, number of new target, limit value of target out of the reactor, new channel number, and closed channel number. After confirming that the reactor core initialization information is accurate, the “initialize” button can be used to complete the initialization arrangement of the scheme. It is particularly noted that if the initialization design of the reactor core loading scheme has been completed before, step 2 is not needed, and step 3 is jumped to.

[0086] Step 3: In the intelligent optimization area, it is selected according to the actual needs whether to enable advanced optimization algorithm to further optimize the scheme. If it is decided to use the optimization algorithm, the algorithm parameters can also be finely adjusted in the advanced settings based on historical experience or according to the feedback results after optimization, to achieve more accurate design optimization. When it does not involve the complex constraints and optimization objectives brought by the key physical and thermal parameters of the irradiation device, the system will automatically start the core intelligent optimization through the "intelligent optimization" button. If the influence of each irradiation device is involved, it needs to complete step 4 and click the "intelligent optimization" button.

[0087] Step 4: In the thermal model area, the key input information of the core thermal and irradiation device thermal can be filled according to the requirements of the scheme design, including the reactor inlet water temperature, the maximum temperature limit of the fuel cladding, the corresponding physical output file number of each irradiation device, the irradiation target type, the irradiation target parameter range, the calculation bias, the inlet water temperature and the flow rate, etc. If the current thermal model parameters are consistent with the previous scheme, the "default" button can be conveniently clicked, and the system will automatically fill all the thermal model parameters. After confirming that all the thermal model parameters are accurate, the "model access" button can be clicked to enter the thermal model information into the system.

[0088] Step 5: If the intelligent optimization is not used in step 3, the scheme design experience can be used in this step to carry out the design optimization of the core scheme by using the drag-and-drop scheme adjustment method. The "view" button will automatically generate visual information of the current optimization scheme, and the "clear" button will clear all the cell transposition information (the cell transposition information and the operation sequence are displayed in the design process area, and the cell transposition information and the sequence in the design process area can also be directly adjusted). If the "save" button is clicked, the system will save the user's adjusted design scheme and overwrite the original scheme. If the "run" button is clicked, the system will call and run the fuel management program. After the fuel management program is run, the visual information of the new core design scheme will be automatically generated. At this time, if the "thermal calculation" button is clicked, the system will call the reactor-specific thermal-hydraulic analysis program and the thermal-hydraulic analysis program of different irradiation devices, and carry out parallel calculation. If the "material calculation" button is clicked, the system will automatically generate the calculation file of the Monte Carlo model based on the core loading information of the fuel management program, and call the Monte Carlo program for simulation to obtain the accurate local photon parameter information of the irradiation device.

[0089] Step 6: After the core scheme operation is completed, visual information of the new core design scheme is automatically generated and displayed in the visualization area, and the visual information includes the component type of each cell of the core scheme, the fuel assembly net increase of burnup, the burnup at the end of life, the activity information of the target, the key physical and thermal parameters of each irradiation device, the control rod position information, the core uneven factor, the local channel neutron flux information, etc. The user can select the "neutron flux rate diagram" and click the "switch" button to view the fast thermal neutron flux rate field of the full core.

[0090] Step 7: After the scheme is run, different operation schemes can be compared in the scheme comparison area as needed. The scheme to be compared is selected at the "scheme selection" place, the main comparison information is selected at the "cell selection", "channel selection" and "parameter selection", and the "comparison" button is clicked to generate the core design scheme comparison table.

[0091] The above is only the preferred embodiment of the present application and is not used to limit the present application. For those skilled in the art, the present application can have various changes and variations. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present application shall be included in the protection scope of the present application.

Claims

1. A complex core co-design system suitable for research reactors, characterized in that, include: The model library module includes a model library based on different research reactors and various types of irradiation test specimens within the reactors. The model library includes a reactor model library and an irradiation device model library. The interactive interface module is used to implement interactive operations; The core design module is used to perform autonomous initialization design of the core and solve the problems of missing fuel assembly and target positions caused by duct opening operation and the regional requirements for additional beryllium aluminum assemblies caused by duct closing operation. The core evaluation module is used to evaluate the core. The method for autonomous initialization design of the reactor core includes: Optimize fuel rearrangement; Optimize the rearrangement of the target components; The method for optimizing fuel rearrangement is as follows: Obtain the calculated fuel consumption value at the end of the service life of the previous furnace section, sort the fuel consumption values ​​at different locations in the previous furnace in order from dark to light, obtain the total amount of fuel in the next furnace section and the amount of new fuel, replace the fuel with the new fuel in the previous furnace section whose fuel consumption value is greater than a preset threshold, and obtain a new fuel scheme. According to the fuel consumption value at the end of the previous furnace's service life, from deep to shallow, the n new fuels in the new fuel scheme are placed at the n groups of fuels with the shallowest consumption in the previous furnace section. The fuel with the deepest fuel consumption value among the remaining fuels in the new fuel scheme is placed at the corresponding deepest fuel consumption position in the previous furnace. The positions of the fuels in the scheme are readjusted in order from deep to shallow. The method for optimizing the target rearrangement is as follows: Obtain the number of new target components, sort the target components from the previous furnace in order of target component burnup from deep to shallow, and replace the target components from the previous furnace whose burnup exceeds the preset threshold with new target components. Based on the target arrangement information from the previous furnace, the targets are rearranged in order of burnup from deep to shallow. The method for resolving the issues of missing fuel assembly and target positions caused by duct opening operations and the increased area requirements for beryllium aluminum assemblies caused by duct closing operations is as follows: When a new channel is opened, the nearest location of the original fuel assembly or original target is located, and it is determined whether the nearest location is a beryllium assembly, aluminum assembly, or stainless steel assembly. If it is, the original fuel assembly or original target at the channel location is moved to that location, and the original assembly at that location is removed from the stack. If not, the search continues to find a more distant location until the location of the beryllium assembly, aluminum assembly, or stainless steel assembly is found, and the original fuel assembly or original target at the channel location is moved to that location, and the original assembly at that location is removed from the stack. When the duct is closed, the historical fuel management program design input file is searched. If the duct was previously the location of a fuel assembly or target, it is filled with a beryllium assembly.

2. The complex core co-design system for research reactors according to claim 1, characterized in that, Both the reactor model library and the irradiation device model library include characteristic units and non-characteristic units; The method for establishing the feature unit is through structural parameters, cross-sectional parameters, and thermophysical property parameters; The method for establishing the non-featured units is based on the actual irradiation mission objectives and actual engineering needs, and is established according to the irradiation test object, boundary conditions, key physical and thermal parameters, and data processing methods.

3. The complex core co-design system for research reactors according to claim 1, characterized in that, The interactive interface module includes: The scheme 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 documents; The core initialization area is used to determine the number of new fuels, the number of target components entering and exiting, and the irradiation channel switching information within the core, and to achieve core design initialization. The intelligent optimization region is used to achieve core optimization design through intelligent methods. The thermal model region is used to determine the irradiation elements, boundary conditions, and irradiation mission objectives corresponding to each irradiation channel in the reactor core, and to realize the thermal calculation analysis and evaluation of each irradiation element. The design operation area is used to determine the position of the grid element components through drag-and-drop operations, realize the operation of the core layout scheme, and perform functions such as pre-operation viewing, core thermal calculation, Monte Carlo simulation modeling, and fine calculation.

4. A complex core co-design system suitable for research reactors 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 component throughout the entire design process; The visualization area is used to view the core design diagram and neutron flux distribution diagram; The scheme comparison area is used to compare information on different reactor core designs.

5. A complex core co-design system for research reactors according to claim 1, characterized in that, The method for evaluating the reactor core is as follows: A collaborative processing approach is adopted to generate files that meet the access specifications of various thermal analysis and evaluation programs. Limit power analysis of the reactor core and physical and thermal calculation analysis of each irradiated component are performed iteratively according to parallel instructions. Based on the output files of each thermal program, the key physical and thermal parameters of each irradiated element are compiled, analyzed, and generated.

6. A complex core co-design system for research reactors according to claim 1, characterized in that, The key physical and thermal parameters are recorded and displayed using text format and a visual interface.

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