Method for determining detector counting space correction factor and system for determining detector counting space correction factor
By determining the detector counting space correction factor, the problem of inaccurate neutron flux caused by control rod space effects was solved, achieving efficient calculation and accurate neutron flux at the nuclear power plant site.
Patent Information
- Application Number
- CN202511030780.9
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-07-25
- Publication Date
- 2025-10-31
AI Technical Summary
In large pool-type sodium-cooled fast reactors, the space effect of the control rods causes the neutron flux measured by the detector to not accurately represent the total flux of the entire reactor, resulting in distortion when calculating reactivity using existing techniques.
The method for determining the detector counting space correction factor includes changing the position of the control rods, determining the three-dimensional spatial response function of the detector and the three-dimensional fission rate distribution of the core, and calculating the relationship between the detector counting space correction factor and the position and location of the control rods.
It enables efficient calculation of detector counting space correction factors at nuclear power plant sites, ensuring the accuracy of the whole-reactor neutron flux after neutron flux correction, and reducing the computational scale and data processing volume.
Smart Images
Figure CN120871223A_ABST
Abstract
Description
Technical Field
[0001] The embodiments of this application relate to the field of nuclear reactor monitoring technology, specifically to a method and system for determining a detector count space correction factor. Background Technology
[0002] The statements herein are provided merely as background information in connection with this application and do not necessarily constitute prior art.
[0003] When the spatial distribution and variations of neutron flux are not considered—that is, when the reactor volume is small or the coupling is relatively tight—the reactor can be lumped together as a "point," and the reactor reactivity can be calculated using the inverse dynamic equations of a point reactor. However, if the reactor volume is large or the coupling is relatively loose, approximating it as a "point reactor" is highly inaccurate. For large pool-type sodium-cooled fast reactors, the control rods exhibit significant spatial effects.
[0004] The space effect of control rods refers to the change in the ratio between the neutron flux measured by the detector and the total neutron flux of the entire reactor due to changes in the position of the control rods. Before and after the control rods are dropped, the neutron flux distribution changes significantly, and the detector efficiency also changes markedly. This causes the neutron flux measured by the detector to fail to represent the total flux of the entire reactor, resulting in distortion of the reactivity calculated using the inverse dynamic equations of the point reactor. Summary of the Invention
[0005] A brief overview of this application is provided below to offer a basic understanding of certain aspects thereof. It should be understood that this overview is not an exhaustive summary of the application. It is not intended to identify key or essential parts of the application, nor is it intended to limit its scope. Its purpose is merely to present certain concepts in a simplified form as a prelude to the more detailed description that follows.
[0006] In a first aspect, embodiments of this application provide a method for determining a detector counting space correction factor. The detector is suitable for determining the spatial effect of control rods at different positions within a reactor under different rod positions. The method includes the following steps: S10: changing the position and rod position of the control rod to determine the three-dimensional spatial response function of the detector during the control rod movement process; S20: determining the three-dimensional fission rate distribution of the reactor core during the control rod movement process; S30: determining the relationship between the detector counting space correction factor and the position and rod position of the control rod based on the three-dimensional spatial response function of the detector determined in step S10 and the three-dimensional fission rate distribution of the reactor core determined in step S20.
[0007] S40: Based on the current position and position of the control rod, and the relationship between the detector counting space correction factor determined in step S30 and the position and position of the control rod, determine the detector counting space correction factor caused by the control rod.
[0008] The method provided in the embodiments of this application determines the detector count space correction factor and the relationship between the position and position of the control rod. This method can determine the detector count space correction factor even when the position of the control rod at any position in the reactor is known. It has a small computational scale and high computational efficiency, and can achieve the purpose of determining the detector count space correction factor on-site in nuclear power plants. This ensures the accuracy of the total reactor neutron flux obtained after correcting the neutron flux based on the detector count space correction factor.
[0009] Secondly, embodiments of this application also provide a system for determining a detector counting spatial correction factor. The detector is suitable for determining the spatial effect of control rods at different positions within a reactor under different rod positions. The system includes: a three-dimensional spatial response function determination module for the detector, configured to change the position and rod position of the control rod to determine the three-dimensional spatial response function of the detector during the control rod movement; a core three-dimensional fission rate distribution determination module, configured to determine the core three-dimensional fission rate distribution during the control rod movement; a module for determining the relationship between the detector counting spatial correction factor and the position and rod position of the control rod, configured to determine the relationship between the detector counting spatial correction factor and the position and rod position of the control rod based on the three-dimensional spatial response function determined by the detector counting spatial response function determination module and the core three-dimensional fission rate distribution determined by the core three-dimensional fission rate distribution determination module; and a module for determining the detector counting spatial correction factor, configured to determine the detector counting spatial correction factor caused by the control rod based on the current rod position of the control rod and the relationship between the detector counting spatial correction factor and the position and rod position of the control rod determined by the module for determining the relationship between the detector counting spatial correction factor and the position and rod position of the control rod.
[0010] These and other advantages of this application will become more apparent from the following detailed description of preferred embodiments in conjunction with the accompanying drawings. Attached Figure Description
[0011] To further illustrate the above and other advantages and features of this application, the specific embodiments of this application will be described in more detail below with reference to the accompanying drawings. The drawings, together with the following detailed description, are included in and form a part of this specification. Elements having the same function and structure are indicated by the same reference numerals. It should be understood that these drawings only depict typical examples of this application and should not be considered as limiting the scope of this application.
[0012] Figure 1This is a schematic diagram of the arrangement of reactors and detectors in related technologies;
[0013] Figure 2 This is a flowchart illustrating a method for determining a detector counting space correction factor according to an embodiment of this application.
[0014] Figure 3 This is a schematic cross-sectional view of a reactor according to an embodiment of this application;
[0015] Figure 4 This is a schematic diagram of the control rod movement process according to an embodiment of this application.
[0016] It should be noted that the accompanying drawings are not necessarily drawn to scale, but are shown only in a schematic manner without affecting the reader's understanding.
[0017] Explanation of reference numerals in the attached figures:
[0018] 102. Reactor vessel; 103. Control rod; 104. Core; 200. Detector; 301. Core assembly; 303. Shielding area. Detailed Implementation
[0019] Exemplary embodiments of this application will be described below with reference to the accompanying drawings. For clarity and brevity, not all features of actual implementations are described in the specification. However, it should be understood that many implementation-specific decisions must be made in the development of any such actual embodiment to achieve the developer's specific goals, such as complying with constraints related to the system and business, and these constraints may vary depending on the implementation. Furthermore, it should be understood that while development work can be very complex and time-consuming, such development work is merely a routine task for those skilled in the art who benefit from the content of this application.
[0020] It should also be noted that, in order to avoid obscuring this application with unnecessary details, only the equipment structure and / or processing steps closely related to the solution according to this application are shown in the accompanying drawings, while other details that are not closely related to this application are omitted.
[0021] It should be noted that, unless otherwise defined, the technical or scientific terms used in this application shall have the ordinary meaning as understood by a person with ordinary skills in the field to which this application pertains.
[0022] In the description of the embodiments of this application, "multiple" means at least two, such as two, three, etc., unless otherwise explicitly specified.
[0023] In related technologies, the detector response change is indirectly calculated by calculating the core fission rate using the detector's spatial response function. Figure 1 This is a schematic diagram of the reactor and detector arrangement in related technologies, such as... Figure 1 As shown, the detectors 200 can be respectively set inside and outside the reactor vessel 102. The control rods 103 inside the reactor can move up and down in the active region of the reactor core 104. The reactivity of the reactor core 104 can be controlled by moving one or more control rods 103 to the position of insertion into the active region of the reactor core.
[0024] The inventors of this application discovered that the neutron flux level and distribution in the reactor core 104 change when the control rod 103 is located at different positions. However, since the detector 200 indirectly measures the average neutron flux level of the reactor core 104 based on the average neutron flux obtained from its location, even if the position of the control rod 103 changes, the average neutron flux at the location of the detector 200 does not change significantly at the same average neutron flux level. This leads to a significant deviation between the control effect of the control rod determined by the change in the neutron flux level measured by the detector 200 and the actual control effect.
[0025] To address the aforementioned technical problems, embodiments of this application provide a method for determining the space correction factor for detector counting, applicable to determining the space effect of control rods at different positions within a reactor under different rod positions. Figure 2 This is a flowchart illustrating a method for determining the detector counting space correction factor according to an embodiment of this application, as shown below. Figure 2 As shown, the method includes the following steps S10 to S40. S10: Change the position and position of the control rod to determine the three-dimensional spatial response function of the detector during the control rod movement. S20: Determine the three-dimensional fission rate distribution of the reactor core during the control rod movement. S30: Based on the three-dimensional spatial response function of the detector determined in step S10 and the three-dimensional fission rate distribution of the reactor core determined in step S20, determine the relationship between the detector counting space correction factor and the position and position of the control rod. S40: Based on the current position and position of the control rod and the relationship between the detector counting space correction factor determined in step S30 and the position and position of the control rod, determine the detector counting space correction factor caused by the control rod.
[0026] The method provided in the embodiments of this application determines the detector count space correction factor and the relationship between the position and position of the control rod. This method can determine the detector count space correction factor even when the position of the control rod at any position in the reactor is known. It has a small computational scale and high computational efficiency, and can achieve the purpose of determining the detector count space correction factor on-site in nuclear power plants. This ensures the accuracy of the total reactor neutron flux obtained after correcting the neutron flux based on the detector count space correction factor.
[0027] In some embodiments, the reactor may be, for example, a pool-type liquid metal cooled reactor.
[0028] In some embodiments, Figure 3 This is a schematic cross-sectional view of a reactor according to an embodiment of this application, as shown below. Figure 3 As shown, the reactor core assembly 301 is a hexagonal assembly, and the detector 200 is located in the radial shielding layer region 303 outside the core assembly 301.
[0029] In some embodiments, Figure 4 This is a schematic diagram of the control rod movement process according to an embodiment of this application, such as... Figure 4 As shown, the control rod 103 can move downward from the top of the core assembly 301 until it is fully inserted into the core assembly 301. During the movement of the control rod 103, the level and distribution of the core neutron flux are different when the control rod 103 is located at different positions in the core assembly 301.
[0030] In some embodiments, step S10 further includes the following steps: S11: determining the reactor cross-section database; S12: determining the core fuel region fission source distribution of the reactor based on the reactor core layout and the cross-section database; S13: determining the core fuel region conjugate neutron flux distribution based on the reactor detector layout and the cross-section database; S14: determining the reactor detector three-dimensional spatial response function based on the core fuel region fission source distribution and the conjugate neutron flux distribution; S15: changing the position of the control rods at different locations within the reactor, repeating steps S12-S14, and determining the detector three-dimensional spatial response function during the control rod movement process.
[0031] The method provided in the embodiments of this application can determine the distribution of fission sources in the reactor core fuel region and the distribution of conjugate neutron flux rate in the reactor core fuel region by determining the reactor cross-section database. In turn, it can determine the three-dimensional spatial response function of the detector during the movement of the control rods. The calculation scale is small and the calculation efficiency is high, which helps to further reduce the amount of on-site calculation and data processing in nuclear power plants.
[0032] In some embodiments, the cross-sectional databases differ significantly for different reactor types; therefore, it is necessary to determine a suitable cross-sectional database for a specific reactor. The reactors in the embodiments of this application can be understood as target reactors for which the detector count space correction factor needs to be determined.
[0033] In some embodiments, core processing tools can be used to process the core cross-section data of the reactor to obtain a core cross-section database.
[0034] In some embodiments, the reactor core arrangement may include the reactor core region fuel arrangement.
[0035] In some embodiments, the reactor detector arrangement may include the relative positional arrangement between the detectors and the reactor core.
[0036] In some embodiments, the three-dimensional spatial response function of the detector changes as the position of the control rod in the reactor core changes. That is, the detector corresponds to different three-dimensional spatial response functions for different positions of the control rod in the reactor core. In such embodiments, by changing the position and location of the control rod and repeating steps S12-S14 above, the three-dimensional spatial response function of the detector during the movement of the control rod can be determined.
[0037] In some embodiments, step S14 further includes the following steps: S141: dividing the reactor core fuel region into multiple units; S142: determining the volume of each unit; S143: determining the three-dimensional spatial response function of the detector based on the volume of each unit, the fission source distribution in the core fuel region of each unit, and the conjugate neutron flux rate distribution in the core fuel region of each unit.
[0038] The method provided in the embodiments of this application divides the reactor core into multiple units, and can determine the three-dimensional spatial response function of the detector based on the volume of each unit, the fission source distribution in the core fuel region of each unit, and the conjugate neutron flux distribution in the core fuel region of each unit, which has high reliability.
[0039] In some embodiments, the reactor can be modeled, and then the simulated reactor can be divided into multiple units.
[0040] In some embodiments, three-dimensional neutronics calculations can be used to determine the distribution of fission sources in the fuel region of the reactor core.
[0041] In some embodiments, step S143 further includes the following steps: S1431: determining the number of energy groups in the reactor core; S1432: determining the g-group energy width of the reactor core; S1433: determining the three-dimensional spatial response function of the detector based on the number of energy groups, the g-group energy width, the volume of each cell, the fission source distribution in the core fuel region of each cell, and the conjugate neutron flux distribution in the core fuel region of each cell.
[0042] The method provided in the embodiments of this application is relatively simple to calculate and has high reliability by discretizing the detector spatial response function in dimensions such as energy and space and by implementing error control strategies.
[0043] In some embodiments, in step S1433, the number of energy groups, the energy width of the g-group, the volume of each cell, the fission source distribution in the core fuel region of each cell, the conjugate neutron flux distribution in the core fuel region of each cell, and the three-dimensional spatial response function of the detector conform to the following relationship (1):
[0044]
[0045] Where W(i) represents the three-dimensional spatial response function; i represents the i-th core fuel region element; ΔV i Let represent the volume of the i-th core fuel region cell; G represents the energy group number; g represents energy group g; (ΔE) g Indicates the energy width of the g-group; express Energy E g The conjugate neutron fluence rate; E represents the spatial coordinate position of the i-th core fuel region element; g Represents the energy of the g group; express Energy E g The fission spectrum; N represents the number of core subdivision units; j represents the j-th core fuel region unit; ΔV j This represents the volume of the j-th core fuel region cell; express Energy E g The conjugate neutron fluence rate; This represents the spatial coordinate position of the j-th core fuel region element; express Energy E g The fission spectrum.
[0046] The method provided in the embodiments of this application uses the above-mentioned relationship to determine the three-dimensional spatial response function of the detector, which is relatively simple to calculate and has high reliability.
[0047] In some embodiments, the detector response based on the detector's three-dimensional spatial response function conforms to the following relationship (2):
[0048]
[0049] Where R represents the detector response; N represents the number of core partitioning units; i represents the i-th core fuel region unit; (v∑ f φ i ) represents the fission rate at unit i; v represents the number of fission neutrons; ∑ f Indicates the fission cross section; φ iW(i) represents the neutron flux distribution of the i-th core fuel region cell in the reactor core; W(i) represents the response function of the detector at the i-th core fuel region cell in the reactor core, i.e., the three-dimensional detector spatial response function.
[0050] In some embodiments, after determining the detector's response at the current location, a detector count space correction factor can be determined. The detector's response and the detector count space correction factor conform to the following relationship (3):
[0051]
[0052] Where NRCF represents the detector counting space correction factor; R x R0 represents the three-dimensional spatial response of the detector at the position after the control rod has moved; R0 represents the three-dimensional spatial response of the detector at the position before the control rod has moved.
[0053] Embodiments of this application also provide a system for determining a detector counting spatial correction factor. The detector is suitable for determining the spatial effect of control rods at different positions within a reactor under different rod positions. The system includes: a three-dimensional spatial response function determination module for the detector, configured to change the position and rod position of the control rod to determine the three-dimensional spatial response function of the detector during the control rod movement; a core three-dimensional fission rate distribution determination module, configured to determine the core three-dimensional fission rate distribution during the control rod movement; a relationship determination module between the detector counting spatial correction factor and the position and rod position of the control rod, configured to determine the relationship between the detector counting spatial correction factor and the position and rod position of the control rod based on the three-dimensional spatial response function determined by the detector counting spatial response function determination module and the core three-dimensional fission rate distribution determined by the core three-dimensional fission rate distribution determination module; and a detector counting spatial correction factor determination module, configured to determine the detector counting spatial correction factor caused by the control rod based on the current position and rod position of the control rod and the relationship between the detector counting spatial correction factor and the position and rod position of the control rod determined by the relationship determination module.
[0054] The system provided in the embodiments of this application, by determining the relationship between the detector counting space correction factor and the position and position of the control rod, can determine the detector counting space correction factor even when the position of the control rod at any position in the reactor is known. The system has a small computational scale and high computational efficiency, and can achieve the purpose of determining the detector counting space correction factor on-site in nuclear power plants, thereby ensuring the accuracy of the total reactor neutron flux obtained after correcting the neutron flux based on the detector counting space correction factor.
[0055] In some embodiments, the detector's three-dimensional spatial response function determination module further includes: a cross-section database determination submodule, configured to determine the reactor's cross-section database; a core fuel region fission source distribution submodule, configured to determine the core fuel region fission source distribution of the reactor based on the reactor's layout and the cross-section database; a core fuel region conjugate neutron flux rate determination submodule, configured to determine the core fuel region conjugate neutron flux rate distribution based on the reactor's detector layout and the cross-section database; a detector three-dimensional spatial response function determination submodule, configured to determine the reactor's detector three-dimensional spatial response function based on the core fuel region fission source distribution and the conjugate neutron flux rate distribution; and configured to change the position of control rods at different locations within the reactor, and use the detector three-dimensional spatial response function determination submodule to determine the detector's three-dimensional spatial response function during the control rod movement process.
[0056] The system provided in the embodiments of this application can determine the distribution of fission sources and conjugate neutron flux rates in the reactor core fuel region by determining the reactor cross-section database. In turn, it can determine the three-dimensional spatial response function of the detector during the movement of the control rods. The system has a small computational scale and high computational efficiency, which helps to further reduce the amount of on-site calculations and data processing in nuclear power plants.
[0057] In some embodiments, the detector three-dimensional spatial response function determination submodule is further configured to: divide the reactor core fuel region into multiple units and determine the volume of each unit; and determine the detector's three-dimensional spatial response function based on the volume of each unit, the fission source distribution in the core fuel region of each unit, and the conjugate neutron flux distribution in the core fuel region of each unit.
[0058] The system provided in the embodiments of this application divides the reactor core into multiple units, and can determine the three-dimensional spatial response of the detector based on the volume of each unit, the fission source distribution in the core fuel region of each unit, and the conjugate neutron flux distribution in the core fuel region of each unit, resulting in high reliability.
[0059] In some embodiments, the detector three-dimensional spatial response function determination submodule is further configured to: determine the number of energy groups in the reactor core; determine the g-group energy width of the reactor core; and determine the detector's three-dimensional spatial response function based on the number of energy groups, the g-group energy width, the volume of each cell, the fission source distribution in the core fuel region of each cell, and the conjugate neutron flux distribution in the core fuel region of each cell.
[0060] The system provided in the embodiments of this application helps to reduce data processing time by discretizing the detector spatial response function in dimensions such as energy and space and by employing error control strategies.
[0061] In some embodiments, the number of energy groups, the g-group energy width, the volume of each cell, the fission source distribution in the core fuel region of each cell, the conjugate neutron flux distribution in the core fuel region of each cell, and the three-dimensional spatial response function of the detector conform to the following relationship (1):
[0062]
[0063] The system provided in the embodiments of this application uses the above-mentioned relationship to determine the three-dimensional spatial response function of the detector, which is relatively simple to calculate and has high reliability.
[0064] Regarding the embodiments of this application, it should also be noted that, without conflict, the embodiments of this application and the features in the embodiments can be combined with each other to obtain new embodiments.
[0065] The above description is merely a specific embodiment of this application, but the scope of protection of this application is not limited thereto. The scope of protection of this application shall be determined by the scope of the claims.
Claims
1. A method for determining a detector counting space correction factor, wherein the detector is suitable for determining the spatial effect of control rods at different positions within a reactor under different rod positions, characterized in that, It includes the following steps: S10: Change the position and position of the control rod, and determine the three-dimensional spatial response function of the detector during the movement of the control rod; S20: Determine the three-dimensional fission rate distribution of the core during the movement of the control rod; S30: Based on the three-dimensional spatial response function of the detector determined in step S10 and the three-dimensional fission rate distribution of the core determined in step S20, determine the relationship between the detector counting space correction factor and the position and position of the control rod. S40: Based on the current position and position of the control rod, and the relationship between the detector counting space correction factor determined in step S30 and the position and position of the control rod, determine the detector counting space correction factor caused by the control rod.
2. The method according to claim 1, characterized in that, Step S10 also includes the following steps: S11: Determine the cross-sectional database of the reactor; S12: Determine the distribution of fission sources in the reactor core fuel region based on the reactor core layout and the cross-section database; S13: Determine the conjugate neutron flux distribution in the reactor core fuel region based on the reactor detector arrangement and the cross-section database; S14: Determine the three-dimensional spatial response function of the reactor detector based on the fission source distribution in the core fuel region and the conjugate neutron flux distribution; S15: Change the position of the control rod at different locations within the reactor, repeat steps S12-S14, and determine the detector's three-dimensional spatial response function during the movement of the control rod.
3. The method according to claim 2, characterized in that, Step S14 also includes the following steps: S141: Divide the reactor core fuel region into multiple units; S142: Determine the volume of each unit; S143: Determine the three-dimensional spatial response function of the detector based on the volume of each unit, the fission source distribution in the core fuel region of each unit, and the conjugate neutron flux distribution in the core fuel region of each unit.
4. The method according to claim 3, characterized in that, Step S143 also includes the following steps: S1431: Determine the energy group number of the reactor core; S1432: Determine the g-group energy width of the reactor core; S1433: Determine the three-dimensional spatial response function of the detector based on the number of energy groups, the energy width of the g-group, the volume of each unit, the fission source distribution in the core fuel region of each unit, and the conjugate neutron flux distribution in the core fuel region of each unit.
5. The method according to claim 4, characterized in that, In step S1433, the number of energy groups, the energy width of the g-group, the volume of each cell, the fission source distribution in the core fuel region of each cell, the conjugate neutron flux rate distribution in the core fuel region of each cell, and the three-dimensional spatial response function of the detector conform to the following relationship: Where W(i) represents the three-dimensional spatial response function; i represents the i-th core fuel region element; ΔV i Let represent the volume of the i-th core fuel region cell; G represents the energy group number; g represents energy group g; (ΔE) g Indicates the energy width of the g-group; express Energy E g The conjugate neutron fluence rate; E represents the spatial coordinate position of the i-th core fuel region element; g Represents the energy of the g group; express Energy E g The fission spectrum; N represents the number of core subdivision units; j represents the j-th core fuel region unit; ΔV j This represents the volume of the j-th core fuel region cell; express Energy E g The conjugate neutron fluence rate; This represents the spatial coordinate position of the j-th core fuel region element; express Energy E g The fission spectrum.
6. A system for determining a detector counting space correction factor, the detector being adapted to determine the spatial effect of control rods at different positions within a reactor under different rod positions, characterized in that, It includes: The detector's three-dimensional spatial response function determination module is configured to change the position and position of the control rod to determine the detector's three-dimensional spatial response function during the movement of the control rod. A core three-dimensional fission rate distribution determination module is configured to determine the core three-dimensional fission rate distribution during the movement of the control rods; The module for determining the relationship between the detector counting space correction factor and the position and position of the control rod is configured to determine the relationship between the detector counting space correction factor and the position and position of the control rod based on the three-dimensional spatial response function determined by the detector three-dimensional spatial response function determination module and the three-dimensional fission rate distribution of the core determined by the core three-dimensional fission rate distribution determination module. The detector counting space correction factor determination module is configured to determine the detector counting space correction factor caused by the control rod based on the current position and position of the control rod, and the relationship between the detector counting space correction factor and the position and position of the control rod determined by the module.
7. The system according to claim 6, characterized in that, The detector's three-dimensional spatial response function determination module also includes: A cross-section database determination submodule is configured to determine the cross-section database of the reactor; A core fuel region fission source distribution submodule is configured to determine the core fuel region fission source distribution of the reactor based on the reactor core layout and the cross-section database. A core fuel region conjugate neutron flux distribution determination submodule is configured to determine the core fuel region conjugate neutron flux distribution based on the reactor's detector arrangement and the cross-section database. The detector three-dimensional spatial response function determination submodule is configured to determine the reactor's detector three-dimensional spatial response function based on the fission source distribution in the core fuel region and the conjugate neutron flux distribution. It is also configured to change the position of the control rods at different locations within the reactor and use the detector three-dimensional spatial response function determination submodule to determine the detector's three-dimensional spatial response function during the movement of the control rods.
8. The system according to claim 7, characterized in that, The detector three-dimensional spatial response function determination submodule is further configured to: divide the reactor core fuel region into multiple units and determine the volume of each unit; and determine the detector's three-dimensional spatial response function based on the volume of each unit, the fission source distribution in the core fuel region of each unit, and the conjugate neutron flux distribution in the core fuel region of each unit.
9. The system according to claim 8, characterized in that, The detector three-dimensional spatial response function determination submodule is further configured to: Determine the energy group number of the reactor core; Determine the g-group energy width of the reactor core; The three-dimensional spatial response function of the detector is determined based on the number of energy groups, the energy width of the g-group, the volume of each unit, the fission source distribution in the core fuel region of each unit, and the conjugate neutron flux distribution in the core fuel region of each unit.
10. The system according to claim 9, characterized in that, The number of energy groups, the energy width of the g-group, the volume of each cell, the fission source distribution in the core fuel region of each cell, the conjugate neutron flux rate distribution in the core fuel region of each cell, and the three-dimensional spatial response function of the detector conform to the following relationship: Where W(i) represents the three-dimensional spatial response function; i represents the i-th core fuel region element; ΔV i Let represent the volume of the i-th core fuel region cell; G represents the energy group number; g represents energy group g; (ΔE) g Indicates the energy width of the g-group; express Energy E g The conjugate neutron fluence rate; E represents the spatial coordinate position of the i-th core fuel region element; g Represents the energy of the g group; express Energy E g The fission spectrum; N represents the number of core subdivision units; j represents the j-th core fuel region unit; ΔV j Indicates ΔV j This represents the volume of the j-th core fuel region cell; express Energy E g The conjugate neutron fluence rate; This represents the spatial coordinate position of the j-th core fuel region element; express Energy E g The fission spectrum.