Method for determining reduction ratio of simulated core of simulated reactor with respect to actual core of actual reactor, simulated reactor, design verification and safety check method for reactor, and computer storage medium

Abstract

The embodiment of the invention relates to the technical field of reactor testing, in particular to a method for determining the reduction proportion of a simulated reactor core of a simulated reactor relative to an actual reactor core of an actual reactor, the simulated reactor, a design verification and safety checking method of the reactor and a computer storage medium. According to the method for determining the reduction ratio of the simulated reactor core of the simulated reactor relative to the actual reactor core of the actual reactor, the resistance characteristic of the simulated reactor core of the simulated reactor is similar to that of the actual reactor core of the actual reactor; the rod bundle heat exchange characteristic and the flow distribution characteristic of the fuel assembly simulation piece of the simulation reactor core are similar to those of an actual reactor core of an actual reactor, so that the simulation reactor can meet the similar requirements of a natural circulation experiment; moreover, by determining the proportion of the number of the fuel assemblies of the actual reactor reduced to the number of the fuel assemblies of the simulated reactor, the number of the fuel assembly simulators of the simulated reactor can be greatly reduced under the condition of ensuring the simulation precision, and the experiment cost of the natural circulation experiment is reduced.

Description

Technical Field

[0001] The embodiments of this application relate to the technical field of reactor testing, specifically to a method for determining the scale-down ratio of a simulated reactor core relative to the actual reactor core, a simulated reactor, a reactor design verification and safety check method, and a computer storage medium. 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] The reactor natural circulation experiment is carried out on a simulated reactor that is scaled down to a certain proportion of the actual reactor. To ensure the accuracy of the experiment, the simulated reactor core needs to meet the design requirements of accurately simulating the drag characteristics of the actual reactor core, as well as the heat transfer characteristics and flow distribution characteristics of the fuel assembly rod bundles. Therefore, it is necessary to determine the scaled-down ratio of the simulated reactor core relative to the actual reactor core so that the simulated reactor core can be manufactured accordingly.

[0004] Currently, there are still many problems in determining the scaling ratio of the simulated reactor core to the actual reactor core, making it difficult for the simulated reactor core to meet the similarity requirements of natural circulation experiments. 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 the scaling-down ratio of a simulated reactor core relative to the actual reactor core of a real reactor. The method includes the following steps: S10: determining the structural parameters of the actual reactor; S20: determining the length scaling-down ratio of the simulated reactor core relative to the actual reactor core; S30: determining the number of rods in the simulated fuel assembly components of the simulated reactor core and the number of rods in the actual reactor core's fuel assemblies, and determining the ratio of the number of fuel assemblies in the actual reactor core to the number of fuel assemblies in the simulated reactor core; S40: determining the hydraulic diameter ratio of the rod bundle segments of the simulated fuel assembly components of the simulated reactor core, and determining the preliminary cladding outer diameter of the simulated fuel assembly components of the simulated reactor core; S50: determining the simulated reactor core based on the number of rods determined in S30, the ratio of the number of fuel assemblies in the actual reactor core to the number of fuel assemblies in the simulated reactor core determined in step S30, and the preliminary cladding outer diameter determined in S40. The flow area ratio of the fuel assembly simulator and the inner side length and inner side-to-side distance of the outer sleeve of the fuel assembly simulator; S60: Based on the flow area ratio determined in S50, determine the total power ratio of the simulated core, and based on the total power ratio of the simulated core, determine the power density of the electric heating rods of the simulated core; S70: Determine the availability of the number of rods, preliminary cladding outer diameter, inner side length of the outer sleeve, inner side-to-side distance of the outer sleeve, and power density of the electric heating rods of the simulated core determined in the previous steps; S80: Based on the results determined in S70, modify the preliminary cladding outer diameter in step S40; S90: Repeat S50-S80 to determine the final cladding outer diameter; S100: Based on the final cladding outer diameter, determine the flow area ratio of the fuel assembly simulator of the simulated core and the inner side length and inner side-to-side distance of the outer sleeve of the fuel assembly simulator.

[0007] The method provided in this application for determining the scaling-down ratio of the simulated reactor core relative to the actual reactor core of a real reactor, by determining the hydraulic diameter ratio of the rod bundle section of the simulated fuel assembly in the simulated reactor core, and based on this, determining the flow area ratio of the simulated fuel assembly, as well as the inner side length and the inner side-to-side distance of the outer sleeve of the simulated fuel assembly, in order to ensure the simulation reactor meets the similarity requirements of natural circulation experiments by considering that the drag characteristics of the simulated reactor core are similar to those of the actual reactor core, and that the rod bundle heat transfer characteristics and flow distribution characteristics of the simulated fuel assembly are similar to those of the actual reactor core fuel assemblies. This ensures the effectiveness of the experiment. Furthermore, by determining the ratio of the number of actual reactor fuel assemblies to the number of simulated reactor fuel assemblies, and accordingly determining the flow area ratio of the simulated fuel assembly, as well as the inner side length and the inner side-to-side distance of the outer sleeve of the simulated fuel assembly, the method can significantly reduce the number of simulated fuel assembly components in the simulated reactor while ensuring simulation accuracy, thereby reducing the experimental cost of natural circulation experiments and ensuring the validity and accuracy of experimental data.

[0008] Secondly, embodiments of this application also provide a reactor design verification method, which uses the method of any embodiment of the first aspect of this application to simulate the designed reactor, and in step S10, determines the structural parameters according to the reactor design drawings.

[0009] The reactor design verification method provided in the embodiments of this application uses the method of any embodiment of the first aspect of this application to simulate the designed reactor, and in step S10, determines the structural parameters according to the reactor design drawing so as to obtain a simulated reactor that is highly similar to the designed reactor. Thus, by conducting experiments on the simulated reactor, it is easy to verify whether the designed reactor meets the predetermined design requirements and standards.

[0010] Thirdly, embodiments of this application also provide a simulated reactor, which is scaled down using the method of any embodiment of the first aspect of this application.

[0011] The simulated reactor provided in the embodiments of this application is scaled down using the method of any embodiment of the first aspect of this application. The simulated reactor assembled therefrom can meet the similar requirements of natural circulation experiments for core drag characteristics, rod bundle heat transfer characteristics and flow distribution characteristics, ensuring the experimental accuracy of natural circulation experiments. At the same time, it significantly reduces the number of fuel assembly simulation components in the simulated reactor, which helps to reduce the experimental cost of natural circulation experiments.

[0012] Fourthly, embodiments of this application also provide a method for verifying the safety of a reactor, which involves running a simulated reactor according to any embodiment of the third aspect of this application, obtaining the operating parameters of the simulated reactor, and verifying the safety of the reactor based on the operating parameters.

[0013] The reactor safety verification method provided in the embodiments of this application obtains the operating parameters of the simulated reactor by running a simulated reactor according to any embodiment of the third aspect of this application. By utilizing the similarity between the simulated reactor and the simulated actual reactor, the safety of the reactor is verified based on the operating parameters of the simulated reactor. Compared with performing safety tests on the actual reactor, this method can effectively reduce testing costs, improve testing accuracy, and help ensure the operational safety of the actual reactor.

[0014] Fifthly, embodiments of this application also provide a computer storage medium having a computer program stored thereon, the computer program being executed by a processor to implement the method as described in any embodiment of the first aspect of this application. Attached Figure Description

[0015] Other objects and advantages of this application will become apparent from the following description of embodiments of this application with reference to the accompanying drawings, and will help to provide a comprehensive understanding of this application.

[0016] Figure 1 This is a flowchart of a method for determining the scale-down ratio of the simulated core of a simulated reactor relative to the actual core of a real reactor, according to an embodiment of this application. Figure 2 This is a schematic cross-sectional view of the rod bundle section of a simulated reactor according to an embodiment of this application; Figure 3 This is a schematic diagram of the drag characteristics of a simulated core of a simulated reactor according to an embodiment of this application; Figure 4 This is a schematic diagram comparing the flow share and outlet temperature of each flow zone of the simulated reactor core and the actual reactor core according to an embodiment of this application.

[0017] Explanation of reference numerals in the attached figures: 10. Fuel rod simulator; 20. Stainless steel rod; 30. Component box simulator; 40. Inner winding wire.

[0018] 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. 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] The inventors of this application have discovered that in the prior art, the design of the simulated reactor core for a simulated reactor generally uses the "black box assumption" method to lump together the drag characteristics of the core and the heat transfer characteristics of the fuel assembly rod bundles. This method can only obtain the boundary requirements for the entire simulated reactor core. The drag characteristics, heat transfer characteristics of the fuel assembly rod bundles, and flow distribution characteristics of the simulated reactor core fabricated based on this method are significantly distorted, thus affecting the experimental accuracy of natural circulation experiments.

[0022] Based on this, embodiments of this application provide a method for determining the scaled-down ratio of the simulated core of a simulated reactor relative to the actual core of a real reactor, such as... Figure 1 As shown, Figure 1 A flowchart illustrating an embodiment of this application shows a method for determining the scale-down ratio of a simulated reactor core relative to the actual reactor core of a real reactor. The method includes the following steps: S10: Determine the structural parameters of the actual heap.

[0023] S20: Determine the ratio of the simulated stack length to the actual stack length.

[0024] S30: Determine the number of rods in the simulated fuel assembly of the simulated reactor core and the number of rods in the actual reactor core fuel assembly, and determine the ratio of the number of fuel assemblies in the actual reactor to the number of fuel assemblies in the simulated reactor.

[0025] S40: Determine the hydraulic diameter ratio of the rod bundle section of the fuel assembly simulator in the simulated reactor core, and determine the preliminary cladding outer diameter of the fuel assembly simulator in the simulated reactor core.

[0026] S50: Based on the number of rods determined in S30, the proportion of the actual reactor fuel assembly scaled down to the simulated reactor fuel assembly determined in step S30, and the preliminary cladding outer diameter determined in S40, determine the flow area ratio of the simulated fuel assembly components in the simulated reactor core, as well as the inner side length of the outer sleeve and the inner side-to-side distance of the outer sleeve of the simulated fuel assembly components.

[0027] S60: Based on the flow area ratio determined in S50, determine the total power ratio of the simulated reactor core, and based on the total power ratio of the simulated reactor core, determine the power density of the electric heating rods in the simulated reactor core.

[0028] S70: Determine the availability of the number of rods, preliminary cladding outer diameter, inner side length of the outer tube, inner side-to-side distance of the outer tube, and power density of the electric heating rods for the simulated core, as determined in the preceding steps.

[0029] S80: Based on the results determined in S70, modify the preliminary outer diameter of the casing in step S40.

[0030] S90: Repeat S50-S80 to determine the final outer diameter of the casing.

[0031] S100: Based on the final cladding outer diameter, determine the flow area ratio of the fuel assembly simulator in the simulated reactor core, as well as the inner side length of the outer sleeve and the distance between opposite sides of the outer sleeve.

[0032] The method provided in this application for determining the scaling-down ratio of the simulated reactor core relative to the actual reactor core of a real reactor, by determining the hydraulic diameter ratio of the rod bundle section of the simulated fuel assembly in the simulated reactor core, and based on this, determining the flow area ratio of the simulated fuel assembly, as well as the inner side length and the inner side-to-side distance of the outer sleeve of the simulated fuel assembly, in order to ensure the simulation reactor meets the similarity requirements of natural circulation experiments by considering that the drag characteristics of the simulated reactor core are similar to those of the actual reactor core, and that the rod bundle heat transfer characteristics and flow distribution characteristics of the simulated fuel assembly are similar to those of the actual reactor core fuel assemblies. This ensures the effectiveness of the experiment. Furthermore, by determining the ratio of the number of actual reactor fuel assemblies to the number of simulated reactor fuel assemblies, and accordingly determining the flow area ratio of the simulated fuel assembly, as well as the inner side length and the inner side-to-side distance of the outer sleeve of the simulated fuel assembly, the method can significantly reduce the number of simulated fuel assembly components in the simulated reactor while ensuring simulation accuracy, thereby reducing the experimental cost of natural circulation experiments and ensuring the validity and accuracy of experimental data.

[0033] In some embodiments, in step S30, based on the rod bundle distribution requirements of the fuel assemblies in the reactor core, the number of rods in the simulated fuel assembly of the simulated core and the number of rods in the actual fuel assembly are determined, thereby determining the ratio of the number of fuel assemblies in the actual reactor to the number of fuel assemblies in the simulated reactor. For example, the rod bundle distribution within the fuel assemblies of a sodium-cooled fast reactor core satisfies: ,in, N Indicates the number of rods in the fuel assembly. n Indicates the number of turns in the rod bundle.

[0034] In some embodiments, when determining the hydraulic diameter ratio of the rod bundle segment of the simulated fuel assembly in the simulated reactor core in step S40, the step may further include: S41: Set the length reduction ratio of the simulated stack core relative to the actual stack core to the length reduction ratio determined in step S20.

[0035] S42: Set the characteristic Reynolds number used to determine the drag characteristics of the simulated reactor core.

[0036] S43: Based on the characteristic Reynolds number in step S42 and the length reduction ratio determined in S20, determine the hydraulic diameter ratio of the rod bundle section of the fuel assembly simulator in the simulated reactor core.

[0037] In this embodiment, a characteristic Reynolds number is set to determine the drag characteristics of the simulated reactor core. Based on the characteristic Reynolds number and the length reduction ratio of the simulated reactor to the actual reactor, the hydraulic diameter ratio of the rod bundle section of the fuel assembly in the simulated reactor core is determined. This ensures that the drag characteristics of the simulated reactor core are similar to those of the actual reactor core, which helps the simulated reactor meet the similarity requirements of natural circulation experiments.

[0038] In some embodiments, in step S42, the set characteristic Reynolds number can be determined based on the characteristic Reynolds number of the actual stack, which helps to ensure that the drag characteristics of the simulated core of the simulated stack can meet the similar requirements of the natural circulation experiment.

[0039] In some embodiments, step S42 may further include the following steps: S421: Determine the characteristic Reynolds number of each component channel in the actual heap.

[0040] S422: Determine the average density and average velocity of each component channel in the actual heap.

[0041] S423: Determine the characteristic Reynolds number of the actual stack based on the characteristic Reynolds number determined in step S421 and the average density and average velocity determined in step S422.

[0042] In this embodiment, the characteristic Reynolds number of each component channel of the actual stack is determined, as well as the average density and average velocity of each component channel of the actual stack. Based on this, the characteristic Reynolds number of the actual stack is determined. Then, based on the characteristic Reynolds number of the actual stack, the characteristic Reynolds number used to determine the drag characteristics of the simulated stack core is set. This ensures that the simulated stack can reproduce the flow drag characteristics of the actual stack to the greatest extent, thus ensuring the experimental accuracy of the natural circulation experiment.

[0043] In some embodiments, in step S421, during the natural circulation establishment phase of the actual reactor, the characteristic Reynolds number of each component channel is determined. And in step S422, during the natural circulation establishment phase of the actual reactor, the average density and average velocity of each component channel are determined. Determining the characteristic Reynolds number of the actual reactor in this way helps to further improve the similarity between the drag characteristics of the simulated reactor core and the actual reactor, thereby improving the experimental accuracy of the natural circulation experiment.

[0044] In some embodiments, step S43 may further include the following steps: determining the Darcy friction coefficient ratio based on the characteristic Reynolds number determined in step S42 and the length reduction ratio determined in S20; and determining the hydraulic diameter ratio of the rod bundle section of the fuel assembly simulator in the simulated reactor core based on the Darcy friction coefficient ratio.

[0045] In this embodiment, the Darcy friction coefficient ratio is determined based on the characteristic Reynolds number used to simulate the drag characteristics of the reactor core and the length reduction ratio of the simulated reactor relative to the actual reactor core. The hydraulic diameter ratio of the rod bundle section of the fuel assembly in the simulated reactor core is then determined based on this Darcy friction coefficient ratio, so that it can meet the requirements for similar friction drag characteristics in natural circulation tests.

[0046] In some embodiments, the characteristic Reynolds number, the length reduction ratio, and the Darcy friction coefficient ratio satisfy the following relationship: .

[0047] in, This indicates the proportion of Darcy's coefficient of friction. Represents the characteristic Reynolds number, This indicates the ratio of the simulated heap's length to the actual heap's length.

[0048] In this embodiment, by establishing the relationship between the characteristic Reynolds number, the length reduction ratio, and the Darcy friction coefficient ratio, the Darcy friction coefficient ratio can be accurately determined under the condition that the characteristic Reynolds number used to simulate the drag characteristics of the reactor core and the length reduction ratio of the simulated reactor relative to the actual reactor core are known. This helps to ensure that the hydraulic diameter ratio of the rod bundle section determined according to the Darcy friction coefficient ratio can meet the requirement that the friction drag characteristics of the simulated reactor core and the actual reactor core are similar in natural circulation tests.

[0049] In some embodiments, step S40 may further include: determining the cladding outer diameter ratio of the simulated fuel assembly in the simulated reactor core relative to the fuel assembly in the actual reactor core, based on the determined hydraulic diameter ratio of the rod bundle segment and the length reduction ratio determined in step S20; and determining the preliminary cladding outer diameter of the simulated fuel assembly in the simulated reactor core based on the cladding outer diameter ratio and the cladding outer diameter of the fuel assembly in the actual reactor core. This ensures that the determined preliminary cladding outer diameter meets the requirement that the heat transfer characteristics and frictional resistance characteristics of the simulated fuel assembly in the simulated reactor core are similar to those of the fuel assembly in the actual reactor core, thereby improving the experimental accuracy of the natural circulation experiment.

[0050] In some embodiments, the hydraulic diameter ratio of the rod bundle segment, the length reduction ratio, and the ratio of the cladding outer diameter of the simulated fuel assembly in the simulated reactor core to that of the actual fuel assembly in the reactor core satisfy the following relationship: .

[0051] in, This indicates the ratio of the cladding outer diameter of the simulated fuel assembly in the simulated reactor core to that of the actual fuel assembly in the reactor core. This indicates the ratio of the simulated heap's length to the actual heap. This indicates the ratio of the hydraulic diameter of the rod bundle section.

[0052] In some embodiments, in step S50, the number of rods determined in step S30, the ratio of the number of fuel assemblies in the actual reactor to the number of fuel assemblies in the simulated reactor, the preliminary cladding outer diameter determined in step S40, the flow area ratio of the fuel assembly simulator in the simulated reactor core, the inner side length of the outer sleeve of the fuel assembly simulator, and the inner side-to-side distance of the outer sleeve of the fuel assembly simulator satisfy the following relationship: .

[0053] This represents the ratio of the flow area of ​​the simulated fuel assembly in the simulated reactor core to the flow area of ​​the fuel assembly in the actual reactor core. This indicates the inner side length of the outer sleeve of the fuel assembly simulator. This indicates the inner edge-to-edge distance of the outer sleeve of the fuel assembly simulator. Indicates the initial outer diameter of the casing. Indicates the number of rods in the fuel assembly simulator. This indicates the inner side length of the outer sleeve of the fuel assembly in the actual reactor core. This indicates the distance between the inner edges of the outer sleeve of the fuel assembly in the actual reactor core. This indicates the outer diameter of the cladding of the fuel assembly in the actual reactor core. The value represents the number of rods in the fuel assembly of the actual reactor core, and W represents the proportion of the fuel assembly in the actual reactor scaled down to the number of fuel assemblies in the simulated reactor.

[0054] In this embodiment, by establishing the relationships between the number of rods, the ratio of the actual reactor's fuel assemblies to the simulated reactor's fuel assemblies, the initial cladding outer diameter, the flow area ratio of the simulated fuel assembly components in the simulated reactor core, the inner side length of the outer tube of the simulated fuel assembly components, and the inner side-to-side distance of the outer tube of the simulated fuel assembly components, under the condition of knowing the number of rods in the simulated fuel assembly components, the ratio of the actual reactor's fuel assemblies to the simulated reactor's fuel assemblies, and the initial cladding outer diameter of the simulated fuel assembly components, the flow area ratio of the simulated fuel assembly components in the simulated reactor core, as well as the inner side length and inner side-to-side distance of the outer tube of the simulated fuel assembly components, can be accurately determined. Thus, by considering the fuel rods and flow area in fuel assemblies in the same flow zone together, and adopting an integrated design approach for multiple fuel assemblies in the same flow zone, it is beneficial to significantly reduce the number of simulated fuel assembly components in the simulated reactor while ensuring that the flow distribution characteristics and outlet turbulence characteristics of the simulated reactor can meet the similarity requirements of natural circulation experiments, thus ensuring the simulation accuracy of the simulated reactor.

[0055] In some embodiments, step S60 may further include the following steps: determining the system flow area ratio of the simulated reactor based on the flow area ratio determined in step S50; and determining the total power of the simulated reactor core based on the system flow area ratio of the simulated reactor and the length reduction ratio determined in step S20. This facilitates ensuring that the power density of the electric heating rods of the simulated reactor core, determined based on the total power ratio of the simulated reactor core, meets the similarity requirements of the natural circulation experiment, thereby improving the experimental accuracy of the natural circulation experiment.

[0056] In some embodiments, the total power ratio, length reduction ratio, and system flux area ratio of the simulated core satisfy the following relationship: .

[0057] in, This represents the total power ratio of the simulated reactor core. Indicates the length reduction ratio. This indicates the proportion of the system flow area in the simulated stack.

[0058] In this embodiment, by establishing the relationship between the total power ratio of the simulated reactor core, the length reduction ratio, and the system flow area ratio of the simulated reactor, the total power ratio of the simulated reactor core can be accurately determined under the condition that the length reduction ratio and the system flow area ratio of the simulated reactor are known. This facilitates the determination of the power density of the electric heating rod of the simulated reactor core that better meets the similar requirements of the natural circulation experiment, thus ensuring the experimental accuracy of the natural circulation experiment.

[0059] In some embodiments, in step S70: the fuel assembly simulator is assembled according to the inner side length of the outer sleeve and the distance between opposite sides of the inner sleeve of the fuel assembly simulator determined in step S50. If the device cannot be realized, the preliminary outer diameter of the outer casing determined in step S40 is adjusted, and step S50 is executed again according to the adjusted preliminary outer diameter of the outer casing.

[0060] If assembly cannot be achieved, it indicates that the simulated actual reactor cannot achieve a high-fidelity scale that balances drag characteristics and rod bundle heat transfer characteristics. In this embodiment, when assembly cannot be achieved, the preliminary outer diameter of the cladding determined in step S40 is adjusted, and step S50 is executed based on the adjusted preliminary outer diameter of the cladding. This helps to ensure the assembly feasibility of the fuel assembly simulator and maximizes the balance between the requirements for high similarity of drag characteristics and rod bundle heat transfer characteristics in the natural circulation experiment, thereby improving the experimental accuracy of the natural circulation experiment.

[0061] Specifically, when adjusting the initial cladding outer diameter determined in step S40, the initial cladding outer diameter can be iterated under the determined hydraulic diameter ratio of the rod bundle section to obtain multiple initial cladding outer diameter values; among the multiple cladding outer diameter values, the value that makes the power density of the electric heating rods of the simulated core meet the assembly requirements is selected as the newly determined initial cladding outer diameter.

[0062] The embodiments of this application also provide a method for design verification of a reactor, which uses the method of determining the scale-down ratio of the simulated reactor core of the simulated reactor to the actual reactor core of the actual reactor according to any embodiment of this application to simulate the designed reactor, and in step S10, determines the structural parameters according to the design drawings of the reactor.

[0063] The reactor design verification method provided in the embodiments of this application uses the method of determining the scaling ratio of the simulated reactor core relative to the actual reactor core of the actual reactor in any embodiment of this application to simulate the designed reactor. In step S10, the structural parameters are determined according to the reactor design drawings in order to obtain a simulated reactor that is highly similar to the designed reactor. Thus, by conducting experiments on the simulated reactor, it is easy to verify whether the designed reactor meets the predetermined design requirements and standards.

[0064] Embodiments of this application also provide a simulated reactor, wherein the simulated reactor obtains its scaling ratio using a method described in any embodiment of this application for determining the scaling ratio of the simulated reactor core relative to the actual reactor core.

[0065] The simulated reactor provided in the embodiments of this application obtains a scaling ratio by using the method provided in any embodiment of this application for determining the scaling ratio of the simulated reactor core relative to the actual reactor core. The simulated reactor assembled accordingly can meet the similar requirements of natural circulation experiments for core drag characteristics, rod bundle heat transfer characteristics, and flow distribution characteristics, ensuring the experimental accuracy of natural circulation experiments. At the same time, it significantly reduces the number of fuel assembly simulation components in the simulated reactor, which helps to reduce the experimental cost of natural circulation experiments.

[0066] like Figure 2 As shown, Figure 2 The diagram shows a cross-sectional view of the rod bundle section of a simulated reactor according to an embodiment of this application. In some embodiments, the simulated reactor includes a fuel rod simulator 10, stainless steel rods 20, a component box simulator 30, inner winding wires 40, a pin simulator (not shown in the figure), and a data acquisition system (not shown in the figure). The fuel rod simulator 10 is configured as a simulated heat source, the stainless steel rods 20 are configured as structural components simulating heat storage in peripheral components, the component box simulator 30 is configured as the internal flow heat transfer boundary, and the inner winding wires 40 are configured as rod bundle positioning and constraint components.

[0067] In natural circulation experiments, the simulated reactor serves as the natural circulation heat sink in the main circulation loop system. Its natural circulation driving force, resistance, and heat release capacity have a significant impact on the thermal state of the natural circulation experimental device. If the simulation accuracy of the simulated reactor is insufficient compared to the actual reactor, the natural circulation experiment will be unable to reproduce the transient response and natural circulation characteristics of the actual reactor. In this embodiment, by setting the simulated reactor as described above, it is beneficial to accurately simulate the actual reactor and meet the similarity requirements of the natural circulation experiment for core resistance characteristics, rod bundle heat transfer characteristics, and flow distribution characteristics. Thus, it is ensured that the transient response and natural circulation characteristics of the actual reactor can be reproduced using the simulated reactor in the natural circulation experiment.

[0068] In some embodiments, the pin emulator is configured to compensate for the drag characteristics of the simulated reactor to meet drag calibration under different operating conditions, thereby improving the similarity between the drag characteristics of the simulated reactor and the actual reactor. Specifically, the pin emulator is equipped with a throttling device to compensate for the drag characteristics of the simulated reactor.

[0069] In some embodiments, the data acquisition system may include: a temperature measuring device, a differential pressure measuring device, and a flow measuring device. The temperature measuring device is configured to measure the inlet and outlet temperatures of each component of the simulated reactor to determine the internal temperature distribution of each component. The differential pressure measuring device is configured to measure the drag loss pressure drop at the inlet and outlet of the simulated reactor core. The flow measuring device is configured to measure the flow rate of each component channel of the simulated reactor to obtain the flow state parameters of each component of the simulated reactor.

[0070] The embodiments of this application also provide a method for verifying the safety of a reactor, which involves running a simulated reactor provided in any embodiment of this application to obtain the operating parameters of the simulated reactor, and verifying the safety of the reactor based on the operating parameters.

[0071] The reactor safety verification method provided in the embodiments of this application obtains the operating parameters of the simulated reactor by running the simulated reactor provided in any embodiment of this application. By utilizing the similarity between the simulated reactor and the simulated actual reactor, the safety of the reactor is verified based on the operating parameters of the simulated reactor. Compared with performing safety tests on the actual reactor, this method can effectively reduce testing costs, improve testing accuracy, and help ensure the operational safety of the actual reactor.

[0072] Embodiments of this application also provide a computer storage medium having a computer program stored thereon, the computer program being executed by a processor to implement a method for determining the scale-down ratio of a simulated core of a simulated reactor relative to the actual core of a real reactor, as described in any embodiment of this application.

[0073] The computer storage medium provided in the embodiments of this application, because it stores a processor that executes a computer program capable of implementing a method for determining the scaling ratio of the simulated core of a simulated reactor relative to the actual core of an actual reactor, facilitates the automatic and continuous execution and processing of the steps, effectively improving the efficiency and accuracy of determining the scaling ratio.

[0074] To facilitate understanding, the following example of the design of a simulated core of a loop-type sodium-cooled fast reactor will be used to further illustrate the process of determining the scaling ratio of the simulated core of the simulated reactor relative to the actual core of the actual reactor in this application.

[0075] Determine the structural parameters of the actual stack. Determine the scaling factor of the simulated stack relative to the actual stack. =0.25; Set the length reduction ratio of the simulated reactor core relative to the actual reactor core to 0.25. Determine the characteristic Reynolds number, average density, and average velocity of each component channel in the actual reactor. Based on the characteristic Reynolds number, average density, and average velocity, determine the characteristic Reynolds number of the actual reactor. =2383. Based on the characteristic Reynolds number and the length reduction ratio, the hydraulic diameter ratio of the rod bundle section of the fuel assembly simulator in the simulated reactor core was determined. =0.6032. Determine the number of rods in the simulated fuel assembly of the simulated reactor core and the number of rods in the actual reactor core fuel assembly, and determine the ratio of the number of fuel assemblies in the actual reactor to the number of fuel assemblies in the simulated reactor. Based on the determined hydraulic diameter ratio of the rod bundle segments, determine the preliminary cladding outer diameter of the simulated fuel assembly of the simulated reactor core. =4.14mm. Based on the determined number of rods, the ratio of the actual reactor fuel assemblies scaled down to the simulated reactor fuel assemblies, and the initial cladding outer diameter, the flow area ratio of the simulated fuel assembly components, the inner side length of the outer sleeve of the simulated fuel assembly components, and the inner side-to-side distance of the outer sleeve are determined. Based on the flow area ratio, the total power ratio of the simulated reactor core is determined, and based on the total power ratio of the simulated reactor core, the power density of the electric heating rods in the simulated reactor core is determined. The availability of the number of rods, initial cladding outer diameter, inner side length of the outer sleeve, inner side-to-side distance of the outer sleeve, and power density of the electric heating rods in the simulated reactor core determined in the previous steps is determined; based on the determined inner side length and inner side-to-side distance of the outer sleeve of the simulated fuel assembly components, the simulated fuel assembly components are assembled. The assembly result is that assembly cannot be achieved, and the initial cladding outer diameter is adjusted. =6mm, and repeat the aforementioned steps. Based on the final cladding outer diameter, determine the flow area ratio of the fuel assembly simulator in the simulated reactor core. =0.028, the inner side length of the outer sleeve of the fuel assembly simulator. =6mm, inner side distance of outer tube =28.44mm.

[0076] Please see Figure 3 and Figure 4 , Figure 3 This diagram illustrates the drag characteristics of a simulated reactor core in an embodiment of this application. Figure 4 This diagram illustrates a comparison of the flow fraction and outlet temperature of each flow zone in the simulated reactor core of an embodiment of this application with that of an actual reactor core. According to... Figure 3 It can be seen that the drag characteristics of the simulated reactor core under natural circulation conditions are similar to those of the actual reactor core, satisfying the similarity requirements of natural circulation experiments. Figure 4 It can be seen that, except for some flow zones where the thermal safety characteristics are conservatively estimated based on the hottest component, the flow share and outlet temperature of each flow zone are basically consistent, which meets the similar requirements of natural circulation experiments for the heat transfer characteristics and flow distribution characteristics of the rod bundle.

[0077] 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.

[0078] The above are merely specific embodiments 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 the scaling ratio of a simulated reactor core relative to the actual reactor core of a real reactor, characterized in that, It includes the following steps: S10: Determine the structural parameters of the actual heap; S20: Determine the length reduction ratio of the simulated heap relative to the actual heap; S30: Determine the number of rods in the simulated fuel assembly of the simulated reactor core and the number of rods in the actual reactor core fuel assembly, and determine the ratio of the number of fuel assemblies in the actual reactor core reduced to the number of fuel assemblies in the simulated reactor core. S40: Determine the hydraulic diameter ratio of the rod bundle section of the fuel assembly simulator in the simulated reactor core, and determine the preliminary cladding outer diameter of the fuel assembly simulator in the simulated reactor core; S50: Based on the number of rods determined in S30, the proportion of the number of fuel assemblies in the actual reactor reduced to the number of fuel assemblies in the simulated reactor determined in step S30, and the preliminary outer diameter of the cladding determined in S40, determine the flow area ratio of the fuel assembly simulator of the simulated reactor core, as well as the inner side length of the outer sleeve and the inner side-to-side distance of the outer sleeve of the fuel assembly simulator. S60: Based on the flow area ratio determined in S50, determine the total power ratio of the simulated reactor core, and based on the total power ratio of the simulated reactor core, determine the power density of the electric heating rods of the simulated reactor core; S70: Determine the availability of the number of rods, the initial outer diameter of the cladding, the inner side length of the outer tube, the distance between opposite sides of the outer tube, and the power density of the electric heating rods of the simulated core as determined in the preceding steps; S80: Based on the results determined in S70, modify the preliminary outer diameter of the casing in step S40; S90: Repeat S50-S80 to determine the final outer diameter of the casing; S100: Based on the final outer diameter of the cladding, determine the flow area ratio of the fuel assembly simulator of the simulated core, as well as the inner side length of the outer sleeve and the inner side-to-side distance of the outer sleeve of the fuel assembly simulator.

2. The method according to claim 1, characterized in that, In step S50, the number of rods, the ratio of the number of fuel assemblies in the actual reactor to the number of fuel assemblies in the simulated reactor, the initial cladding outer diameter, the flow area ratio of the simulated fuel assembly components in the simulated reactor core, the inner side length of the outer sleeve of the simulated fuel assembly, and the inner side-to-side distance of the outer sleeve of the simulated fuel assembly satisfy the following relationship: ， This represents the ratio of the flow area of ​​the simulated fuel assembly in the simulated reactor core to the flow area of ​​the fuel assembly in the actual reactor core. This indicates the inner side length of the outer sleeve of the fuel assembly simulator. This indicates the distance between the inner edges of the outer sleeve of the fuel assembly simulator. This indicates the initial outer diameter of the casing. This indicates the number of rods in the fuel assembly simulator. This indicates the inner side length of the outer sleeve of the fuel assembly in the actual reactor core. This indicates the distance between the inner edges of the outer sleeve of the fuel assembly in the actual reactor core. This indicates the outer diameter of the cladding of the fuel assembly in the actual reactor core. W represents the number of rods in the fuel assembly of the actual reactor core, and W represents the proportion of the fuel assembly of the actual reactor core scaled down to the number of fuel assemblies in the simulated reactor core.

3. The method according to claim 1, characterized in that, Step S60 also includes the following steps: Based on the flow area ratio determined in S50, the system flow area ratio of the simulated reactor is determined. The total power ratio of the simulated reactor core is determined based on the system flow area ratio of the simulated reactor and the length reduction ratio determined according to step S20.

4. The method according to claim 3, characterized in that, The total power ratio of the simulated core, the length reduction ratio, and the system flux area ratio of the simulated core satisfy the following relationship: ， in, This represents the total power ratio of the simulated reactor core. This indicates the reduction ratio of the length. This indicates the proportion of the system flow area of ​​the simulated stack.

5. The method according to claim 1, characterized in that, In step S70: Based on the inner side length and the distance between opposite sides of the inner side of the outer sleeve of the fuel assembly simulator determined in step S50, the fuel assembly simulator is assembled. If assembly cannot be achieved, adjust the preliminary outer diameter of the casing determined in step S40, and then execute step S50 based on the adjusted preliminary outer diameter of the casing.

6. A reactor design verification method, characterized in that, It uses the method described in any one of claims 1-5 to simulate the designed reactor. In step S10, the structural parameters are determined based on the reactor design drawings.

7. A simulated reactor, characterized in that, The simulated reactor is scaled down using the method described in any one of claims 1-5.

8. The simulated reactor according to claim 7, characterized in that, The simulated reactor includes fuel rod simulators, stainless steel rods, component box simulators, internal wire windings, pin simulators, and a data acquisition system. The fuel rod simulator is used as a simulated heat source, the stainless steel rod is used as a structural component to simulate the heat storage of the peripheral components, the component box simulator is used as the internal flow heat transfer boundary, and the inner winding wire is used as a rod bundle positioning and constraint component.

9. A method for verifying the safety of a reactor, characterized in that, By operating the simulated reactor as described in claim 7 or 8, the operating parameters of the simulated reactor are obtained. The safety of the reactor is verified based on the operating parameters.

10. A computer storage medium, characterized in that, It stores a computer program thereon, which is executed by a processor to implement the method as described in any one of claims 1-5.

Images