Nuclear reactor core fuel assembly interference identification method and device and electronic equipment

Abstract

The application belongs to the technical field of nuclear power, and particularly relates to a nuclear reactor core fuel assembly interference identification method and device, a computer readable storage medium and an electronic device. The method comprises the following steps: determining a center bottom distance of a first component of a first fuel assembly of a nuclear reactor core and a center bottom distance of a second component of a second fuel assembly; wherein the first fuel assembly is a fuel assembly being loaded into or unloaded from the nuclear reactor core, the second fuel assembly is a fuel assembly adjacent to the first fuel assembly, and the center bottom distance is a distance from the center of the component to the bottom of the fuel assembly; determining a lifting height of the first fuel assembly; determining a center distance of the first component and the second component in a vertical direction according to the center bottom distance of the first component, the center bottom distance of the second component and the lifting height of the first fuel assembly; and determining an interference identification result between the first component and the second component according to the center distance of the first component and the second component in the vertical direction.

Description

Technical Field

[0001] This application belongs to the field of nuclear power technology, and in particular relates to a method, apparatus, computer-readable storage medium and electronic equipment for identifying interference of fuel assemblies in a nuclear reactor core. Background Technology

[0002] During each refueling overhaul of a pressurized water reactor nuclear power plant, all fuel assemblies (FAs) must be removed from the reactor. After replacing some spent fuel assemblies with new ones, all fuel assemblies are rearranged and sequentially loaded into the reactor core. Because the fuel assemblies are closely packed and in contact with each other within the reactor, interference and friction occur between them and adjacent assemblies during the removal and loading process. This interference often occurs between components such as fuel assembly positioning grids and upper and lower mounting brackets, frequently leading to difficulties in loading and unloading fuel assemblies and, in severe cases, damage. Summary of the Invention

[0003] In view of this, embodiments of this application provide a method, apparatus, computer-readable storage medium, and electronic device for identifying interference in nuclear reactor core fuel assemblies, in order to identify the height at which interference may occur in advance and improve the safety of the nuclear reactor loading and unloading process.

[0004] A first aspect of this application provides a method for identifying interference in fuel assemblies in a nuclear reactor core, which may include:

[0005] The center-to-bottom distance of a first component of a first fuel assembly in a nuclear reactor core and the center-to-bottom distance of a second component of a second fuel assembly are determined; wherein, the first fuel assembly is a fuel assembly being loaded into or unloaded from the nuclear reactor core, the second fuel assembly is a fuel assembly in the nuclear reactor core adjacent to the first fuel assembly, and the center-to-bottom distance is the distance from the center of the component to the bottom of the fuel assembly;

[0006] Determine the lifting height of the first fuel assembly; wherein, the lifting height is the distance from the bottom of the fuel assembly to the lower grid plate of the reactor core;

[0007] The center-to-bottom distance of the first component, the center-to-bottom distance of the second component, and the lifting height of the first fuel assembly are used to determine the center-to-center distance of the first component and the second component in the vertical direction.

[0008] The interference identification result between the first component and the second component is determined based on the center distance between the first component and the second component in the vertical direction.

[0009] In one specific implementation of the first aspect, determining the center-to-bottom distance of a first component of a first fuel assembly and the center-to-bottom distance of a second component of a second fuel assembly in the nuclear reactor core may include:

[0010] Determine the original center-to-bottom distance of the first component and the original center-to-bottom distance of the second component; wherein, the original center-to-bottom distance is the center-to-bottom distance without considering irradiation growth;

[0011] Determine the irradiation growth rate of the first fuel assembly and the irradiation growth rate of the second fuel assembly;

[0012] The center-to-bottom distance of the first component is determined based on the original center-to-bottom distance of the first component and the irradiation growth rate of the first fuel assembly;

[0013] The center-to-bottom distance of the second component is determined based on the original center-to-bottom distance of the second component and the irradiation growth rate of the second fuel assembly.

[0014] In one specific implementation of the first aspect, determining the irradiation growth rate of the first fuel assembly and the irradiation growth rate of the second fuel assembly may include:

[0015] Determine the irradiation growth amount of the first fuel assembly and the irradiation growth amount of the second fuel assembly;

[0016] The irradiation growth rate of the first fuel assembly is determined based on the irradiation growth amount of the first fuel assembly and the height of the unirradiated fuel assembly; wherein, the height of the unirradiated fuel assembly is the height of the fuel assembly without considering irradiation growth and does not include the height of the upper tube seat leaf spring.

[0017] The irradiation growth rate of the second fuel assembly is determined based on the irradiation growth amount of the second fuel assembly and the height of the unirradiated fuel assembly.

[0018] In one specific implementation of the first aspect, determining the interference recognition result between the first component and the second component based on the center distance between the first component and the second component in the vertical direction may include:

[0019] The irradiation height of the first component is determined based on the height of the first component and the irradiation growth rate of the first fuel assembly.

[0020] The irradiation height of the second component is determined based on the height of the second component and the irradiation growth rate of the second fuel assembly;

[0021] The interference threshold between the first component and the second component is determined based on the irradiation height of the first component and the irradiation height of the second component.

[0022] The interference identification result between the first component and the second component is determined based on the center distance between the first component and the second component in the vertical direction and the interference threshold.

[0023] In one specific implementation of the first aspect, determining the interference recognition result between the first component and the second component based on the center distance between the first component and the second component in the vertical direction and the interference threshold may include:

[0024] If the absolute value of the center distance between the first component and the second component in the vertical direction is less than or equal to the interference threshold, it is determined that interference occurs between the first component and the second component.

[0025] If the absolute value of the center distance between the first component and the second component in the vertical direction is greater than the interference threshold, it is determined that no interference has occurred between the first component and the second component.

[0026] In one specific implementation of the first aspect, the nuclear reactor core fuel assembly interference identification method may further include:

[0027] In the event of interference between the first component and the second component, the amount of overlap between the first component and the second component in the vertical direction is determined based on the center distance between the first component and the second component in the vertical direction, the irradiation height of the first component, and the irradiation height of the second component.

[0028] In one specific implementation of the first aspect, determining the lifting height of the first fuel assembly may include:

[0029] The height threshold of the first fuel assembly is determined based on the coordinate value of the main lifting height of the refueling machine when the first fuel assembly is released from the core load, the unloading stroke of the refueling machine gripper, the compensation stroke of the refueling machine lifting mechanism, and the irradiation growth of the first fuel assembly.

[0030] The lifting height of the first fuel assembly is determined based on the main lifting height coordinates of the refueling machine and the height threshold.

[0031] A second aspect of this application provides a nuclear reactor core fuel assembly interference identification device, which may include:

[0032] The center-to-bottom distance determination module is used to determine the center-to-bottom distance of a first component of a first fuel assembly in a nuclear reactor core, and the center-to-bottom distance of a second component of a second fuel assembly; wherein, the first fuel assembly is a fuel assembly being loaded into or unloaded from the nuclear reactor core, the second fuel assembly is a fuel assembly in the nuclear reactor core adjacent to the first fuel assembly, and the center-to-bottom distance is the distance from the center of the component to the bottom of the fuel assembly;

[0033] The component lifting height determination module is used to determine the lifting height of the first fuel assembly; wherein, the lifting height is the distance from the bottom of the fuel assembly to the lower grid plate of the core;

[0034] The component center distance determination module is used to determine the center distance between the first component and the second component in the vertical direction based on the center-to-bottom distance of the first component, the center-to-bottom distance of the second component, and the lifting height of the first fuel assembly.

[0035] The interference identification result determination module is used to determine the interference identification result between the first component and the second component based on the center distance between the first component and the second component in the vertical direction.

[0036] In one specific implementation of the second aspect, the center-bottom distance determination module may include:

[0037] The original center-bottom distance determination unit is used to determine the original center-bottom distance of the first component and the original center-bottom distance of the second component; wherein, the original center-bottom distance is the center-bottom distance without considering irradiation growth;

[0038] An irradiation growth rate determination unit is used to determine the irradiation growth rate of the first fuel assembly and the irradiation growth rate of the second fuel assembly.

[0039] The center-bottom distance determination unit is used to determine the center-bottom distance of the first component based on the original center-bottom distance of the first component and the irradiation growth rate of the first fuel assembly; and to determine the center-bottom distance of the second component based on the original center-bottom distance of the second component and the irradiation growth rate of the second fuel assembly.

[0040] In one specific implementation of the second aspect, the irradiation growth rate determining unit may be specifically used to: determine the irradiation growth amount of the first fuel assembly and the irradiation growth amount of the second fuel assembly; determine the irradiation growth rate of the first fuel assembly based on the irradiation growth amount of the first fuel assembly and the height of the unirradiated fuel assembly; wherein, the height of the unirradiated fuel assembly is the height of the fuel assembly without considering irradiation growth and does not include the height of the upper tube seat leaf spring; and determine the irradiation growth rate of the second fuel assembly based on the irradiation growth amount of the second fuel assembly and the height of the unirradiated fuel assembly.

[0041] In one specific implementation of the second aspect, the interference recognition result determination module may include:

[0042] An irradiation height determination unit is used to determine the irradiation height of the first component based on the height of the first component and the irradiation growth rate of the first fuel assembly; and to determine the irradiation height of the second component based on the height of the second component and the irradiation growth rate of the second fuel assembly.

[0043] An interference threshold determination unit is used to determine an interference threshold between the first component and the second component based on the irradiation height of the first component and the irradiation height of the second component.

[0044] An interference identification result determination unit is used to determine the interference identification result between the first component and the second component based on the center distance between the first component and the second component in the vertical direction and the interference threshold.

[0045] In one specific implementation of the second aspect, the interference identification result determination unit may be specifically used to: determine that interference occurs between the first component and the second component when the absolute value of the center distance between the first component and the second component in the vertical direction is less than or equal to the interference threshold; and determine that no interference occurs between the first component and the second component when the absolute value of the center distance between the first component and the second component in the vertical direction is greater than the interference threshold.

[0046] In one specific implementation of the second aspect, the nuclear reactor core fuel assembly interference identification device may further include:

[0047] The overlap determination module is used to determine the overlap amount of the first component and the second component in the vertical direction based on the center distance between the first component and the second component in the vertical direction, the irradiation height of the first component, and the irradiation height of the second component when interference occurs between the first component and the second component.

[0048] In one specific implementation of the second aspect, the component lifting height determination module can be specifically used to: determine the height threshold of the first fuel assembly based on the main lifting height coordinate value of the refueling machine when the first fuel assembly is released from the core load, the unlocking stroke of the refueling machine gripper, the compensation stroke of the refueling machine lifting mechanism, and the irradiation growth amount of the first fuel assembly; and determine the lifting height of the first fuel assembly based on the main lifting height coordinate value of the refueling machine and the height threshold.

[0049] A third aspect of this application provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the steps of any of the above-described nuclear reactor core fuel assembly interference identification methods.

[0050] A fourth aspect of this application provides an electronic device including a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the processor executes the computer program to implement the steps of any of the above-described nuclear reactor core fuel assembly interference identification methods.

[0051] The fifth aspect of this application provides a computer program product that, when run on an electronic device, causes the electronic device to perform the steps of any of the above-described nuclear reactor core fuel assembly interference identification methods.

[0052] The beneficial effects of this application embodiment compared with the prior art are as follows: This application embodiment determines the center-to-bottom distance of a first component of a first fuel assembly in a nuclear reactor core, and the center-to-bottom distance of a second component of a second fuel assembly; wherein, the first fuel assembly is a fuel assembly being loaded into or unloaded from the nuclear reactor core, and the second fuel assembly is a fuel assembly adjacent to the first fuel assembly in the nuclear reactor core, and the center-to-bottom distance is the distance from the center of the component to the bottom of the fuel assembly; determines the lifting height of the first fuel assembly; wherein, the lifting height is the distance from the bottom of the fuel assembly to the lower grid plate of the core; determines the center-to-center distance between the first component and the second component in the vertical direction based on the center-to-bottom distance of the first component, the center-to-bottom distance of the second component, and the lifting height of the first fuel assembly; and determines the interference identification result between the first component and the second component based on the center-to-center distance in the vertical direction. Through this application embodiment, the height at which interference may occur can be identified in advance, thereby enabling corresponding avoidance operations based on the interference identification result, thus improving the safety of the nuclear reactor loading and unloading process. Attached Figure Description

[0053] To more clearly illustrate the technical solutions in the embodiments of this application, the drawings used in the description of the embodiments or the prior art will be briefly introduced below. Obviously, the drawings described below are only some embodiments of this application. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0054] Figure 1 This is a flowchart of one embodiment of a nuclear reactor core fuel assembly interference identification method in this application.

[0055] Figure 2 A schematic flowchart for determining the center-to-bottom distance of the first component and the center-to-bottom distance of the second component;

[0056] Figure 3 A schematic diagram of a dynamic simulation of the interference identification results of fuel assemblies in a nuclear reactor core;

[0057] Figure 4 This is a structural diagram of one embodiment of an interference identification device for nuclear reactor core fuel assemblies in this application.

[0058] Figure 5 This is a schematic block diagram of an electronic device according to an embodiment of this application. Detailed Implementation

[0059] To make the inventive objectives, features, and advantages of this application more apparent and understandable, the technical solutions in the embodiments of this application will be clearly and completely described below with reference to the accompanying drawings. Obviously, the embodiments described below are only some embodiments of this application, and not all embodiments. Based on the embodiments in this application, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of this application.

[0060] It should be understood that, when used in this specification and the appended claims, the term "comprising" indicates the presence of the described features, integrals, steps, operations, elements and / or components, but does not exclude the presence or addition of one or more other features, integrals, steps, operations, elements, components and / or collections thereof.

[0061] It should also be understood that the terminology used in this specification is for the purpose of describing particular embodiments only and is not intended to limit the scope of the application. As used in this specification and the appended claims, the singular forms “a,” “an,” and “the” are intended to include the plural forms unless the context clearly indicates otherwise.

[0062] It should also be further understood that the term “and / or” as used in this application specification and the appended claims means any combination of one or more of the associated listed items and all possible combinations, and includes such combinations.

[0063] As used in this specification and the appended claims, the term "if" may be interpreted, depending on the context, as "when," "once," "in response to determination," or "in response to detection." Similarly, the phrase "if determined" or "if [the described condition or event] is detected" may be interpreted, depending on the context, as "once determined," "in response to determination," "once [the described condition or event] is detected," or "in response to detection of [the described condition or event]."

[0064] Furthermore, in the description of this application, the terms "first," "second," "third," etc., are used only to distinguish descriptions and should not be construed as indicating or implying relative importance.

[0065] During each refueling overhaul of a pressurized water reactor nuclear power plant, all fuel assemblies must be removed from the reactor, some spent fuel assemblies replaced with new ones, and then all fuel assemblies are rearranged and sequentially loaded into the reactor core. Because the fuel assemblies are closely packed within the reactor and in contact with each other, interference and friction occur between the fuel assemblies and adjacent components during the removal and loading process. This interference often occurs between components such as fuel assembly positioning grids and upper and lower mounting brackets, frequently leading to difficulties in loading and unloading fuel assemblies and, in severe cases, damage to the fuel assemblies.

[0066] In view of this, embodiments of this application provide a method, apparatus, computer-readable storage medium, and electronic device for identifying interference in nuclear reactor core fuel assemblies, in order to identify the height at which interference may occur in advance and improve the safety of the nuclear reactor loading and unloading process.

[0067] Please see Figure 1 One embodiment of the interference identification method for nuclear reactor core fuel assemblies in this application may include:

[0068] Step S101: Determine the center-to-bottom distance of the first component of the first fuel assembly and the center-to-bottom distance of the second component of the second fuel assembly in the nuclear reactor core.

[0069] The first fuel assembly is the fuel assembly being loaded into or unloaded from the nuclear reactor core, and the second fuel assembly is the fuel assembly in the nuclear reactor core that is adjacent to the first fuel assembly.

[0070] Fuel assemblies may include components prone to interference, such as lower tube sockets, upper tube sockets, positioning grids, and inter-compounding grids. For ease of description, the AFA3G fuel assembly is used as an example here. Subscript 1 can represent the lower tube socket, subscript 13 can represent the upper tube socket, and subscripts 2 to 12 can represent the grid layers from bottom to top.

[0071] The first component is any component in the first fuel assembly, and the second component is any component in the second fuel assembly. The center-to-bottom distance is the distance from the center of the component to the bottom of the fuel assembly.

[0072] like Figure 2 As shown, step S101 may include the following process:

[0073] Step S1011: Determine the original center-bottom distance of the first component and the original center-bottom distance of the second component.

[0074] Wherein, the original center-to-bottom distance is the center-to-bottom distance without considering irradiation growth.

[0075] Step S1012: Determine the irradiation growth rate of the first fuel assembly and the irradiation growth rate of the second fuel assembly.

[0076] In this embodiment, the irradiation growth amount of the first fuel assembly and the irradiation growth amount of the second fuel assembly can be determined. Then, the irradiation growth rate of the first fuel assembly can be determined based on the irradiation growth amount of the first fuel assembly and the height of the unirradiated fuel assembly, and the irradiation growth rate of the second fuel assembly can be determined based on the irradiation growth amount of the second fuel assembly and the height of the unirradiated fuel assembly. As shown in the following formula:

[0077] R a =1+Δ a / L f R b =1+Δ b / L f

[0078] Where, Δ a Δ represents the irradiation growth amount of the first fuel assembly. b L represents the irradiation growth amount of the second fuel assembly. f R represents the height of the unirradiated fuel assembly, i.e., the height of the fuel assembly without considering irradiation growth, and excluding the height of the upper tube seat leaf spring. a R represents the irradiation growth rate of the first fuel assembly. b The irradiation growth rate of the second fuel assembly.

[0079] Step S1013: Determine the center-bottom distance of the first component based on the original center-bottom distance of the first component and the irradiation growth rate of the first fuel assembly; determine the center-bottom distance of the second component based on the original center-bottom distance of the second component and the irradiation growth rate of the second fuel assembly.

[0080] In this embodiment, the product of the original center-to-bottom distance of the first component and the irradiation growth rate of the first fuel assembly can be used to determine the center-to-bottom distance of the first component; and the product of the original center-to-bottom distance of the second component and the irradiation growth rate of the second fuel assembly can be used to determine the center-to-bottom distance of the second component. As shown in the following formula:

[0081] L Ai =L i R a L Bj =L j R b

[0082] Among them, L i L is the original center-to-bottom distance of the first component (excluding irradiation growth). Ai L is the distance from the center bottom of the first component (considering irradiation growth). j L is the original center-to-bottom distance of the second component (excluding irradiation growth). Bj The distance from the center bottom of the second component (considering irradiation growth).

[0083] Step S102: Determine the lifting height of the first fuel assembly.

[0084] Wherein, the lifting height is the distance from the bottom of the fuel assembly to the lower grid plate of the reactor core. In the embodiments of this application, the height threshold of the first fuel assembly can be determined based on the coordinate value of the main lifting height of the refueling machine when the first fuel assembly is released from the core load, the unlocking stroke of the refueling machine grippers, the compensation stroke of the refueling machine lifting mechanism, and the irradiation growth amount of the first fuel assembly. The lifting height of the first fuel assembly can then be determined based on the coordinate value of the main lifting height of the refueling machine and the height threshold, as shown in the following formula:

[0085]

[0086] Where Z represents the main lifting height coordinate value of the material changer, Z LR C represents the coordinate value of the main lifting height of the refueling machine when the first fuel assembly is released from the core load. gripper Z represents the unlocking stroke of the material changer's gripper, and Offset represents the compensation stroke of the material changer's lifting mechanism. For the same type of material changer, Z... LR C gripper The values ​​of offset, etc., are fixed; only Z changes as the first fuel assembly is loaded or unloaded from the core.LR -C gripper -Offset-Δ a Let H be the height threshold of the first fuel assembly, and H be the lifting height of the first fuel assembly. When the main lifting height coordinate value of the refueling machine is less than or equal to this height threshold, the lifting height of the first fuel assembly is this height threshold; when the main lifting height coordinate value of the refueling machine is greater than this height threshold, the lifting height of the first fuel assembly is 0.

[0087] Step S103: Determine the center-to-bottom distance of the first component and the second component in the vertical direction based on the center-to-bottom distance of the first component, the center-to-bottom distance of the second component, and the lifting height of the first fuel assembly.

[0088] In this embodiment, the sum of the center-to-bottom distance of the first component and the lifting height of the first fuel assembly, minus the center-to-bottom distance of the second component, yields the center-to-center distance between the first and second components in the vertical direction. This is illustrated in the following formula:

[0089] L i,j =L Ai +HL Bj

[0090] Among them, L i,j The center distance between the first component and the second component in the vertical direction.

[0091] Step S104: Determine the interference identification result between the first component and the second component based on the center distance between the first component and the second component in the vertical direction.

[0092] In this embodiment, the irradiation height of the first component can be determined based on the height of the first component and the irradiation growth rate of the first fuel assembly; the irradiation height of the second component can be determined based on the height of the second component and the irradiation growth rate of the second fuel assembly; the interference threshold between the first component and the second component can be determined based on the irradiation height of the first component and the irradiation height of the second component; and the interference identification result between the first component and the second component can be determined based on the center distance between the first component and the second component in the vertical direction and the interference threshold.

[0093] Specifically, this can be achieved when the absolute value of the center distance between the first component and the second component in the vertical direction is less than or equal to the interference threshold, i.e., |L i,j |≤(G i R a +G j R b ) / 2, determining that interference occurs between the first and second components. This can occur when the absolute value of the center distance between the first and second components in the vertical direction is greater than the interference threshold, i.e., |L i,j |>(G i Ra +G j R b ) / 2, confirming that no interference occurred between the first and second components. Wherein, G i G is the height of the first component. i R a G is the irradiation height of the first component. j G is the height of the second component. j R b The irradiation height of the second component, (G) i R a +G j R b ) / 2 is the interference threshold between the first component and the second component.

[0094] In the event of interference between the first and second components, the amount of overlap in the vertical direction between the first and second components can be determined based on the center-to-center distance in the vertical direction, the irradiation height of the first component, and the irradiation height of the second component. This is illustrated in the following formula:

[0095]

[0096] Where Min() is the minimum value, and I is the amount of overlap between the first and second components in the vertical direction.

[0097] It should be noted that the above process is illustrated using any component in the first fuel assembly and any component in the second fuel assembly as an example. By iterating through all the pairings of components in the first and second fuel assemblies in the manner described above, a complete interference identification result between the first and second fuel assemblies can be obtained.

[0098] In one specific implementation of the embodiments of this application, such as Figure 3 As shown, computer software can be used to calculate the interference between fuel assemblies and adjacent assemblies in the reactor at any height during reactor loading and unloading, and display a dynamic simulation.

[0099] The fuel assembly interference simulation screen can display a full view and relative position of the fuel assembly being loaded or unloaded, as well as its adjacent fuel assemblies, on a scale. The height coordinates of the fuel assembly can be displayed next to the lower tube seat. The size and relative position of components on the fuel assembly that may cause interference, such as the compression springs (i.e., leaf springs), upper and lower tube seats, positioning grids, and inter-compound mixing grids, can all be displayed at scale to the actual size. The positioning grids and inter-compound mixing grids can all display grid numbers. When contact occurs between interfering components, it can be highlighted with different colors. The size of all screens can automatically scale with the window size.

[0100] The interference situation can be displayed as a list of all interfering components, along with the amount of overlap between them. Clicking on an item in the list will display a magnified view of the interfering component and its relative position. The shape, size, and relative position of the interfering components can all be scaled proportionally to their actual size.

[0101] Fuel assembly interference is related to factors such as the refueling machine model, core load release height, fuel assembly model, fuel assembly irradiation growth rate, and the height coordinates of the fuel assembly being loaded or unloaded from the core on the refueling machine. Therefore, the software provides the following functions: It allows selection of different refueling machine models and automatically updates the core load release height of new assemblies. It allows adjustment of the core load release height of new assemblies based on actual conditions. It allows switching fuel assembly models. It allows adjustment of the irradiation growth rate of the fuel assembly being loaded or unloaded from the core and adjacent fuel assemblies. It allows direct input of the refueling machine height coordinates of the fuel assembly being loaded or unloaded from the core, and also allows rapid increase or decrease of the height coordinates. It allows quick switching to commonly used heights during loading and unloading via several preset status buttons on the right side of the height bar. The interference list and simulation diagram are automatically updated whenever any of the above data changes.

[0102] The fuel assembly object in the software is used to display a complete image of the fuel assembly in the window interface. To achieve dynamic color-changing display of fuel assembly components, each component, such as the upper and lower tube seats, grid, leaf springs, fuel rods, and control rod guide tubes, can be created as an independent object, which is then combined to form the fuel assembly object. The size and position of each component within the fuel assembly object can be defined based on the dimensions of the fuel assembly. When scaling the fuel assembly object, the size and position of each component can be scaled proportionally. The fuel assembly object can include custom attributes such as fuel assembly type, scale bar, default grid color, and default text color. By setting these attributes of the fuel assembly object, as well as the attributes of its sub-components such as the grid, the appearance of the fuel assembly object can be changed.

[0103] The interference component simulation object in the software is used to display magnified images of the contacting components between fuel assemblies in the window interface. This object consists of two sub-objects, A and B. By setting several custom attributes (e.g., the index of component A, the index of component B, and the center distance of the components in the vertical direction), the two sub-objects can be displayed as components with different appearances, and the relative distance between the components can be changed proportionally.

[0104] In summary, this application embodiment determines the center-to-bottom distance of the first component of the first fuel assembly and the center-to-bottom distance of the second component of the second fuel assembly in the nuclear reactor core; wherein, the first fuel assembly is the fuel assembly being loaded into or unloaded from the nuclear reactor core, and the second fuel assembly is the fuel assembly adjacent to the first fuel assembly in the nuclear reactor core, and the center-to-bottom distance is the distance from the center of the component to the bottom of the fuel assembly; determines the lifting height of the first fuel assembly; wherein, the lifting height is the distance from the bottom of the fuel assembly to the lower grid plate of the core; determines the center-to-center distance of the first and second components in the vertical direction based on the center-to-bottom distance of the first component, the center-to-bottom distance of the second component, and the lifting height of the first fuel assembly; and determines the interference identification result between the first and second components based on the center-to-center distance of the first and second components in the vertical direction. Through this application embodiment, the height at which interference may occur can be identified in advance, thereby enabling corresponding avoidance operations based on the interference identification result to improve the safety of the nuclear reactor loading and unloading process.

[0105] It should be understood that the sequence number of each step in the above embodiments does not imply the order of execution. The execution order of each process should be determined by its function and internal logic, and should not constitute any limitation on the implementation process of the embodiments of this application.

[0106] Corresponding to the nuclear reactor core fuel assembly interference identification method described in the above embodiments, Figure 4 This illustration shows a structural diagram of one embodiment of a nuclear reactor core fuel assembly interference identification device provided in this application.

[0107] In this embodiment, a nuclear reactor core fuel assembly interference identification device may include:

[0108] The center-to-bottom distance determination module 401 is used to determine the center-to-bottom distance of a first component of a first fuel assembly in a nuclear reactor core, and the center-to-bottom distance of a second component of a second fuel assembly; wherein, the first fuel assembly is a fuel assembly being loaded into or unloaded from the nuclear reactor core, the second fuel assembly is a fuel assembly in the nuclear reactor core adjacent to the first fuel assembly, and the center-to-bottom distance is the distance from the center of the component to the bottom of the fuel assembly;

[0109] The component lifting height determination module 402 is used to determine the lifting height of the first fuel assembly; wherein, the lifting height is the distance from the bottom of the fuel assembly to the lower grid plate of the core;

[0110] The component center distance determination module 403 is used to determine the center distance between the first component and the second component in the vertical direction based on the center-bottom distance of the first component, the center-bottom distance of the second component, and the lifting height of the first fuel assembly.

[0111] The interference identification result determination module 404 is used to determine the interference identification result between the first component and the second component based on the center distance between the first component and the second component in the vertical direction.

[0112] In one specific implementation of this application embodiment, the center-bottom distance determination module may include:

[0113] The original center-bottom distance determination unit is used to determine the original center-bottom distance of the first component and the original center-bottom distance of the second component; wherein, the original center-bottom distance is the center-bottom distance without considering irradiation growth;

[0114] An irradiation growth rate determination unit is used to determine the irradiation growth rate of the first fuel assembly and the irradiation growth rate of the second fuel assembly.

[0115] The center-bottom distance determination unit is used to determine the center-bottom distance of the first component based on the original center-bottom distance of the first component and the irradiation growth rate of the first fuel assembly; and to determine the center-bottom distance of the second component based on the original center-bottom distance of the second component and the irradiation growth rate of the second fuel assembly.

[0116] In one specific implementation of this application embodiment, the irradiation growth rate determination unit may be specifically used to: determine the irradiation growth amount of the first fuel assembly and the irradiation growth amount of the second fuel assembly; determine the irradiation growth rate of the first fuel assembly based on the irradiation growth amount of the first fuel assembly and the height of the unirradiated fuel assembly; wherein, the height of the unirradiated fuel assembly is the height of the fuel assembly without considering irradiation growth and does not include the height of the upper tube seat leaf spring; and determine the irradiation growth rate of the second fuel assembly based on the irradiation growth amount of the second fuel assembly and the height of the unirradiated fuel assembly.

[0117] In one specific implementation of this application embodiment, the interference recognition result determination module may include:

[0118] An irradiation height determination unit is used to determine the irradiation height of the first component based on the height of the first component and the irradiation growth rate of the first fuel assembly; and to determine the irradiation height of the second component based on the height of the second component and the irradiation growth rate of the second fuel assembly.

[0119] An interference threshold determination unit is used to determine an interference threshold between the first component and the second component based on the irradiation height of the first component and the irradiation height of the second component.

[0120] An interference identification result determination unit is used to determine the interference identification result between the first component and the second component based on the center distance between the first component and the second component in the vertical direction and the interference threshold.

[0121] In one specific implementation of this application, the interference identification result determination unit can be specifically used to: determine that interference occurs between the first component and the second component when the absolute value of the center distance between the first component and the second component in the vertical direction is less than or equal to the interference threshold; and determine that no interference occurs between the first component and the second component when the absolute value of the center distance between the first component and the second component in the vertical direction is greater than the interference threshold.

[0122] In one specific implementation of this application embodiment, the nuclear reactor core fuel assembly interference identification device may further include:

[0123] The overlap determination module is used to determine the overlap amount of the first component and the second component in the vertical direction based on the center distance between the first component and the second component in the vertical direction, the irradiation height of the first component, and the irradiation height of the second component when interference occurs between the first component and the second component.

[0124] In one specific implementation of this application, the component lifting height determination module can be specifically used to: determine the height threshold of the first fuel assembly based on the main lifting height coordinate value of the refueling machine when the first fuel assembly is released from the core load, the unlocking stroke of the refueling machine gripper, the compensation stroke of the refueling machine lifting mechanism, and the irradiation growth amount of the first fuel assembly; and determine the lifting height of the first fuel assembly based on the main lifting height coordinate value of the refueling machine and the height threshold.

[0125] Those skilled in the art will clearly understand that, for the sake of convenience and brevity, the specific working processes of the devices, modules, and units described above can be referred to the corresponding processes in the foregoing method embodiments, and will not be repeated here.

[0126] In the above embodiments, the descriptions of each embodiment have different focuses. For parts that are not described in detail or recorded in a certain embodiment, please refer to the relevant descriptions of other embodiments.

[0127] Figure 5 A schematic block diagram of an electronic device provided in an embodiment of this application is shown. For ease of explanation, only the parts related to the embodiment of this application are shown.

[0128] like Figure 5As shown, the electronic device 5 in this embodiment includes: a processor 50, a memory 51, and a computer program 52 stored in the memory 51 and executable on the processor 50. When the processor 50 executes the computer program 52, it implements the steps in the various embodiments of the nuclear reactor core fuel assembly interference identification method described above, for example... Figure 1 Steps S101 to S104 are shown. Alternatively, when the processor 50 executes the computer program 52, it implements the functions of each module / unit in the above-described device embodiments, for example... Figure 4 The functions of modules 401 to 404 are shown.

[0129] For example, the computer program 52 may be divided into one or more modules / units, which are stored in the memory 51 and executed by the processor 50 to complete this application. The one or more modules / units may be a series of computer program instruction segments capable of performing a specific function, which describe the execution process of the computer program 52 in the electronic device 5.

[0130] The electronic device 5 may include, but is not limited to, computing devices such as desktop computers, laptops, handheld computers, and servers. Those skilled in the art will understand that... Figure 5 This is merely an example of electronic device 5 and does not constitute a limitation on electronic device 5. It may include more or fewer components than shown, or combine certain components, or different components. For example, electronic device 5 may also include input / output devices, network access devices, buses, etc.

[0131] The processor 50 can be a Central Processing Unit (CPU), or other general-purpose processors, digital signal processors (DSPs), application-specific integrated circuits (ASICs), field-programmable gate arrays (FPGAs), or other programmable logic devices, discrete gate or transistor logic devices, discrete hardware components, etc. The general-purpose processor can be a microprocessor or any conventional processor.

[0132] The memory 51 can be an internal storage unit of the electronic device 5, such as a hard disk or memory. The memory 51 can also be an external storage device of the electronic device 5, such as a plug-in hard disk, Smart Media Card (SMC), Secure Digital (SD) card, or Flash Card. Furthermore, the memory 51 can include both internal and external storage units of the electronic device 5. The memory 51 is used to store the computer program and other programs and data required by the electronic device 5. The memory 51 can also be used to temporarily store data that has been output or will be output.

[0133] Those skilled in the art will clearly understand that, for the sake of convenience and brevity, the above-described division of functional units and modules is merely an example. In practical applications, the above functions can be assigned to different functional units and modules as needed, that is, the internal structure of the device can be divided into different functional units or modules to complete all or part of the functions described above. The functional units and modules in the embodiments can be integrated into one processing unit, or each unit can exist physically separately, or two or more units can be integrated into one unit. The integrated unit can be implemented in hardware or as a software functional unit. Furthermore, the specific names of the functional units and modules are only for easy differentiation and are not intended to limit the scope of protection of this application. The specific working process of the units and modules in the above system can be referred to the corresponding process in the foregoing method embodiments, and will not be repeated here.

[0134] In the above embodiments, the descriptions of each embodiment have different focuses. For parts that are not described in detail or recorded in a certain embodiment, please refer to the relevant descriptions of other embodiments.

[0135] Those skilled in the art will recognize that the units and algorithm steps of the various examples described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, or a combination of computer software and electronic hardware. Whether these functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementation should not be considered beyond the scope of this application.

[0136] In the embodiments provided in this application, it should be understood that the disclosed devices / electronic devices and methods can be implemented in other ways. For example, the device / electronic device embodiments described above are merely illustrative. For instance, the division of modules or units is only a logical functional division, and in actual implementation, there may be other division methods. For example, multiple units or components may be combined or integrated into another system, or some features may be ignored or not executed. Furthermore, the displayed or discussed mutual couplings or direct couplings or communication connections may be through some interfaces; indirect couplings or communication connections between devices or units may be electrical, mechanical, or other forms.

[0137] The units described as separate components may or may not be physically separate. The components shown as units may or may not be physical units; that is, they may be located in one place or distributed across multiple network units. Some or all of the units can be selected to achieve the purpose of this embodiment according to actual needs.

[0138] Furthermore, the functional units in the various embodiments of this application can be integrated into one processing unit, or each unit can exist physically separately, or two or more units can be integrated into one unit. The integrated unit can be implemented in hardware or as a software functional unit.

[0139] If the integrated module / unit is implemented as a software functional unit and sold or used as an independent product, it can be stored in a computer-readable storage medium. Based on this understanding, all or part of the processes in the methods of the above embodiments can also be implemented by a computer program instructing related hardware. The computer program can be stored in a computer-readable storage medium, and when executed by a processor, it can implement the steps of the various method embodiments described above. The computer program includes computer program code, which can be in the form of source code, object code, executable files, or certain intermediate forms. The computer-readable storage medium can include: any entity or device capable of carrying the computer program code, a recording medium, a USB flash drive, a portable hard drive, a magnetic disk, an optical disk, a computer memory, a read-only memory (ROM), a random access memory (RAM), an electrical carrier signal, a telecommunication signal, and a software distribution medium, etc. It should be noted that the content included in the computer-readable storage medium can be appropriately added or removed according to the requirements of legislation and patent practice in the jurisdiction. For example, in some jurisdictions, according to legislation and patent practice, the computer-readable storage medium does not include electrical carrier signals and telecommunication signals.

[0140] The above-described embodiments are only used to illustrate the technical solutions of this application, and are not intended to limit them. Although this application has been described in detail with reference to the foregoing embodiments, those skilled in the art should understand that modifications can still be made to the technical solutions described in the foregoing embodiments, or equivalent substitutions can be made to some of the technical features. Such modifications or substitutions do not cause the essence of the corresponding technical solutions to deviate from the spirit and scope of the technical solutions of the embodiments of this application, and should all be included within the protection scope of this application.

Claims

1. A method for interference identification of fuel assemblies in a nuclear reactor core, characterized in that, include: The center-to-bottom distance of a first component of a first fuel assembly in a nuclear reactor core and the center-to-bottom distance of a second component of a second fuel assembly are determined; wherein, the first fuel assembly is a fuel assembly being loaded into or unloaded from the nuclear reactor core, the second fuel assembly is a fuel assembly in the nuclear reactor core adjacent to the first fuel assembly, and the center-to-bottom distance is the distance from the center of the component to the bottom of the fuel assembly; Determine the lifting height of the first fuel assembly; wherein, the lifting height is the distance from the bottom of the fuel assembly to the lower grid plate of the reactor core; The center-to-bottom distance of the first component, the center-to-bottom distance of the second component, and the lifting height of the first fuel assembly are used to determine the center-to-center distance of the first component and the second component in the vertical direction. The interference identification result between the first component and the second component is determined based on the center distance between the first component and the second component in the vertical direction.

2. The nuclear reactor core fuel assembly interference identification method according to claim 1, characterized in that, The determination of the center-to-bottom distance of the first component of the first fuel assembly and the center-to-bottom distance of the second component of the second fuel assembly in the nuclear reactor core includes: Determine the original center-to-bottom distance of the first component and the original center-to-bottom distance of the second component; wherein, the original center-to-bottom distance is the center-to-bottom distance without considering irradiation growth; Determine the irradiation growth rate of the first fuel assembly and the irradiation growth rate of the second fuel assembly; The center-to-bottom distance of the first component is determined based on the original center-to-bottom distance of the first component and the irradiation growth rate of the first fuel assembly; The center-to-bottom distance of the second component is determined based on the original center-to-bottom distance of the second component and the irradiation growth rate of the second fuel assembly.

3. The nuclear reactor core fuel assembly interference identification method according to claim 2, characterized in that, Determining the irradiation growth rate of the first fuel assembly and the irradiation growth rate of the second fuel assembly includes: Determine the irradiation growth amount of the first fuel assembly and the irradiation growth amount of the second fuel assembly; The irradiation growth rate of the first fuel assembly is determined based on the irradiation growth amount of the first fuel assembly and the height of the unirradiated fuel assembly; wherein, the height of the unirradiated fuel assembly is the height of the fuel assembly without considering irradiation growth and does not include the height of the upper tube seat leaf spring. The irradiation growth rate of the second fuel assembly is determined based on the irradiation growth amount of the second fuel assembly and the height of the unirradiated fuel assembly.

4. The nuclear reactor core fuel assembly interference identification method according to claim 1, characterized in that, The step of determining the interference identification result between the first component and the second component based on the center distance in the vertical direction includes: The irradiation height of the first component is determined based on the height of the first component and the irradiation growth rate of the first fuel assembly. The irradiation height of the second component is determined based on the height of the second component and the irradiation growth rate of the second fuel assembly; The interference threshold between the first component and the second component is determined based on the irradiation height of the first component and the irradiation height of the second component. The interference identification result between the first component and the second component is determined based on the center distance between the first component and the second component in the vertical direction and the interference threshold.

5. The nuclear reactor core fuel assembly interference identification method according to claim 4, characterized in that, The step of determining the interference recognition result between the first component and the second component based on the center distance in the vertical direction between the first component and the second component and the interference threshold includes: If the absolute value of the center distance between the first component and the second component in the vertical direction is less than or equal to the interference threshold, it is determined that interference occurs between the first component and the second component. If the absolute value of the center distance between the first component and the second component in the vertical direction is greater than the interference threshold, it is determined that no interference has occurred between the first component and the second component.

6. The nuclear reactor core fuel assembly interference identification method according to claim 4, characterized in that, Also includes: In the event of interference between the first component and the second component, the amount of overlap between the first component and the second component in the vertical direction is determined based on the center distance between the first component and the second component in the vertical direction, the irradiation height of the first component, and the irradiation height of the second component.

7. The method for identifying interference in nuclear reactor core fuel assemblies according to any one of claims 1 to 6, characterized in that, Determining the lifting height of the first fuel assembly includes: The height threshold of the first fuel assembly is determined based on the coordinate value of the main lifting height of the refueling machine when the first fuel assembly is released from the core load, the unloading stroke of the refueling machine gripper, the compensation stroke of the refueling machine lifting mechanism, and the irradiation growth of the first fuel assembly. The lifting height of the first fuel assembly is determined based on the main lifting height coordinates of the refueling machine and the height threshold.

8. A nuclear reactor core fuel assembly interference identification device, characterized in that, include: The center-to-bottom distance determination module is used to determine the center-to-bottom distance of a first component of a first fuel assembly in a nuclear reactor core, and the center-to-bottom distance of a second component of a second fuel assembly; wherein, the first fuel assembly is a fuel assembly being loaded into or unloaded from the nuclear reactor core, the second fuel assembly is a fuel assembly in the nuclear reactor core adjacent to the first fuel assembly, and the center-to-bottom distance is the distance from the center of the component to the bottom of the fuel assembly; The component lifting height determination module is used to determine the lifting height of the first fuel assembly; wherein, the lifting height is the distance from the bottom of the fuel assembly to the lower grid plate of the core; The component center distance determination module is used to determine the center distance between the first component and the second component in the vertical direction based on the center-to-bottom distance of the first component, the center-to-bottom distance of the second component, and the lifting height of the first fuel assembly. The interference identification result determination module is used to determine the interference identification result between the first component and the second component based on the center distance between the first component and the second component in the vertical direction.

9. A computer-readable storage medium storing a computer program, characterized in that, When the computer program is executed by the processor, it implements the steps of the nuclear reactor core fuel assembly interference identification method as described in any one of claims 1 to 7.

10. An electronic device comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, characterized in that, When the processor executes the computer program, it implements the steps of the nuclear reactor core fuel assembly interference identification method as described in any one of claims 1 to 7.

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