Radioactive refueling pool simulation device

Abstract

The invention relates to the technical field of nuclear radiation protection, in particular to a radioactive refueling pool simulation device which comprises a pool simulation body and a storage rack mechanism, and the storage rack mechanism is arranged in the pool simulation body and used for bearing radioactive materials; the internal water circulation mechanism is arranged in the pool simulation body and is used for enabling fluid in the pool simulation body to circularly flow; the radioactive refueling pool simulation device provided by the invention can be used for researching the decontamination mode of the radioactive refueling pool.

Description

Technical Field

[0001] The invention relates to the technical field of nuclear radiation protection, and in particular to a radioactive refueling pool simulation device. Background Art

[0002] At present, the decontamination methods of nuclear power plant refueling pools are relatively simple, mainly manual cleaning, which can easily lead to contamination of personnel and increase the collective radiation exposure dose of operators;

[0003] Therefore, in order to explore new decontamination technologies for refueling pools, reduce the radiation exposure of maintenance personnel, and achieve green, clean, and effective decontamination and cleaning of refueling pools, it is necessary to develop a set of experimental equipment to facilitate the study of the decontamination process of refueling pools. Summary of the invention

[0004] In view of the above shortcomings of the prior art, an object of the present invention is to provide a radioactive refueling pool simulation device for studying the decontamination method of the radioactive refueling pool.

[0005] To achieve the above-mentioned purpose and other related purposes, the present invention provides a radioactive material exchange pool simulation device, including a pool simulation body, a rack mechanism and an internal water circulation mechanism; the rack mechanism is arranged in the pool simulation body to carry radioactive materials; the internal water circulation mechanism is arranged in the pool simulation body to circulate the fluid in the pool simulation body.

[0006] In one embodiment of the present invention, the rack mechanism comprises:

[0007] A conveying component is arranged in the water pool simulation body;

[0008] A first storage rack, disposed on the conveying assembly;

[0009] The water pool simulation body comprises a material delivery hole, the material delivery hole is located in the delivery direction of the delivery component, and the first storage rack is extended toward the direction of the material delivery hole.

[0010] In one embodiment of the present invention, the rack mechanism further includes:

[0011] A second rack is disposed above the first rack, and one end of the second rack away from the feeding hole is hingedly connected to the first rack or the conveying assembly;

[0012] A cover plate, arranged on the upper part of the second storage rack;

[0013] The second driving assembly is used to drive the second storage rack to rotate around the hinge to adjust the angle.

[0014] In one embodiment of the present invention, the internal water circulation mechanism includes a first pipeline and a filtering and purifying device and a first circulating water pump arranged in the first pipeline;

[0015] The first pipeline includes a liquid extraction end and a liquid discharge end which are arranged far apart from each other, and at least the liquid extraction end is located in the water pool simulation body.

[0016] In one embodiment of the present invention, the radioactive refueling pool simulation device further comprises a pipeline simulation mechanism, and the pipeline simulation mechanism is at least partially disposed in the pool simulation body to simulate the pipeline arrangement in the pool simulation body.

[0017] In one embodiment of the present invention, the radioactive refueling pool simulation device further comprises a ladder simulation mechanism disposed in the pool simulation body to simulate the ladder structure in the pool simulation body.

[0018] In one embodiment of the present invention, the radioactive refueling pool simulation device further comprises at least one group of hole slot simulation components disposed in the pool simulation body;

[0019] The hole and groove simulation components are arranged horizontally, vertically and / or obliquely in the water pool simulation body.

[0020] In one embodiment of the present invention, at least one group of the hole and slot simulation components is provided with a second pipeline for supplying liquid, and a liquid discharge port is provided at the bottom of the group of hole and slot simulation components.

[0021] In one embodiment of the present invention, the radioactive refueling pool simulator further comprises a monitoring component for monitoring the operation of the radioactive refueling pool simulator itself, wherein the monitoring component comprises a monitoring camera and a display device connected to the monitoring camera.

[0022] In one embodiment of the present invention, the radioactive refueling pool simulation device further comprises a control module, and the control module is configured to control the operation of the storage rack mechanism and / or the internal water circulation mechanism.

[0023] In summary, the radioactive refueling pool simulation device of the present invention is intended to simulate different application scenarios to study the decontamination process or technology of the radioactive refueling pool. By conducting experimental tests in the simulation body, the device can demonstrate the feasibility and safety of the decontamination process or equipment, and ensure that the decontamination process will not damage the performance of the components inside the radioactive refueling pool. In addition, the device can quickly and effectively remove the hot spots of pollutants in the radioactive refueling pool and improve the cleaning efficiency. By simulating the structure and movement state of the internal functional components of the radioactive refueling pool, it is relatively easy to identify the locations where radioactive hot spots are easily formed, so as to facilitate the formulation of a special decontamination and cleaning implementation plan, which helps to improve the efficiency and effect of on-site decontamination, while reducing interference with the internal functional components of the radioactive refueling pool. Testing in the radioactive refueling pool simulation device can avoid affecting the progress of the operation or reducing the decontamination effect due to equipment interference during actual on-site decontamination; in addition, this can also shorten the on-site decontamination time and reduce the radiation dose of the operators, thereby protecting their health. BRIEF DESCRIPTION OF THE DRAWINGS

[0024] In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings required for use in the embodiments or the description of the prior art will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the present invention. For ordinary technicians in this field, other drawings can be obtained based on these drawings without paying creative work.

[0025] Figure 1 It is a schematic diagram of the three-dimensional structure of a radioactive refueling pool simulation device in one embodiment of the present invention;

[0026] Figure 2 It is a structural schematic diagram of one side of a radioactive refueling pool simulation device in one embodiment of the present invention;

[0027] Figure 3 It is an enlarged view of the local structure on the other side of the radioactive refueling pool simulation device in one embodiment of the present invention;

[0028] Figure 4 This is a schematic diagram of the bottom structure of a radioactive refueling pool simulation device in one embodiment of the present invention;

[0029] Figure 5 It is a schematic diagram of the partial structural arrangement of a radioactive refueling pool simulation device in one embodiment of the present invention;

[0030] Figure 6 Schematic diagram of the structure of a storage rack mechanism in one embodiment of the present invention;

[0031] Figure 7 is a schematic diagram of the bottom structure of a storage rack mechanism in one embodiment of the present invention;

[0032] Figure 8 It is a schematic structural diagram of one end of a conveying track in one embodiment of the present invention;

[0033] Fig. 9 It is a structural schematic diagram of a first storage rack in one embodiment of the present invention being movably installed on a conveying assembly;

[0034] Component number description: pool simulation body 1, material feeding hole 11, drain port 12, bottom support structure 13, inner support 14, rack mechanism 2, conveying assembly 21, conveying track 211, first drive assembly 212, first drive motor 2121, transmission assembly 2122, first rack 22, roller 221, second rack 23, cover plate 24, second drive assembly 25, discharge drive motor 251, rope roller 252, rope 253, internal water circulation mechanism 3, first pipeline 31, filtering and purification device 32, first circulating water pump 33, pipeline simulation mechanism 4, ladder simulation mechanism 5, hole slot simulation assembly 6, vertical hole simulation unit 61, horizontal hole simulation unit 62, second circulating water pump 63, second pipeline 7, discharge port 71, monitoring assembly 8, monitoring camera 81, display device 82, control module 9. DETAILED DESCRIPTION

[0035] The following is an explanation of the embodiments of the present invention by specific examples, and those skilled in the art can easily understand other advantages and effects of the present invention from the contents disclosed in this specification. The present invention can also be implemented or applied through other different specific embodiments, and the details in this specification can also be modified or changed in various ways based on different viewpoints and applications without departing from the spirit of the present invention. It should be noted that the features in the following embodiments and the embodiments can be combined with each other without conflict. It should also be understood that the terms used in the embodiments of the present invention are intended to describe specific embodiments, rather than to limit the scope of protection of the present invention. The test methods for which specific conditions are not specified in the following examples are usually carried out under conventional conditions or according to the conditions recommended by the manufacturers.

[0036] See also Figures 1 to 9. It should be noted that the structures, proportions, sizes, etc. illustrated in the drawings of this specification are only used to match the contents disclosed in the specification for people familiar with this technology to understand and read, and are not used to limit the limiting conditions for the implementation of the present invention, so they have no substantial technical significance. Any modification of the structure, change in the proportional relationship, or adjustment of the size, without affecting the effects and purposes that can be achieved by the present invention, should still fall within the scope of the technical content disclosed by the present invention. At the same time, the terms such as "upper", "lower", "left", "right", "middle" and "one" quoted in this specification are only for the convenience of description, and are not used to limit the scope of the implementation of the present invention. Changes or adjustments in their relative relationships should also be regarded as the scope of the implementation of the present invention without substantially changing the technical content.

[0037] When numerical ranges are given in the embodiments, it should be understood that, unless otherwise specified in the present invention, both endpoints of each numerical range and any value between the two endpoints can be selected. Unless otherwise defined, all technical and scientific terms used in the present invention are familiar to those skilled in the art and the description of the present invention, and any methods, equipment and materials of the prior art similar or equivalent to the methods, equipment and materials described in the embodiments of the present invention can also be used to implement the present invention.

[0038] It should be noted that the radioactive refueling pool simulation device in this case can at least be used for decontamination simulation work, and can also be used to study the various use steps of the radioactive refueling pool in the daily use process, the structural optimization of the radioactive refueling pool, and the parameter adjustment optimization of each device in the radioactive refueling pool. In other words, all problems related to the use of the radioactive refueling pool can be studied using the radioactive refueling pool simulation device in this case to find problems. The overall radioactive refueling pool simulation device in this case is generally designed in proportion to the real radioactive refueling pool. It should be understood that the radioactive refueling pool simulation device in this case does not have to replicate all the facilities or components of the real radioactive refueling pool, and allows some structures to be different or adaptively adjusted, as long as it can achieve a certain research significance. The decontamination simulation body involved in the following text of this case also refers to the radioactive refueling pool simulation device in this case.

[0039] The radioactive refueling pool of a nuclear power plant is filled with water by the cooling and treatment systems of the radioactive refueling pool and the spent fuel radioactive refueling pool during the shutdown and refueling of the nuclear power unit. It is used to shield the internal fuel assemblies and related components placed in the radioactive refueling pool and reduce the impact of the radioactive components on the surrounding environment. During the long-term operation and maintenance of the radioactive refueling pool, during the transportation and storage of radioactive components, a large amount of radioactive contaminants will adhere to the surface of the internal components of the radioactive refueling pool, the bottom of the radioactive refueling pool, and the inside of the gaps of the equipment components. If they are not cleaned for a long time, they will form firm contaminants and eventually form radioactive hotspots. Therefore, it is necessary to regularly decontaminate the radioactive contaminants in the radioactive refueling pool to avoid the deposition of radioactive contaminants to form radioactive hotspots, or to remove the radioactive hotspots that have already formed. However, as a nuclear facility component of an important nuclear power plant, a radioactive refueling pool requires a safe and reliable decontamination and cleaning method, which is the key to ensuring its stable operation. Therefore, this case designs a device for simulating the operation of a radioactive refueling pool in a nuclear power plant, so as to achieve the purpose of simulating the decontamination of a radioactive refueling pool; for example, it is used to study the decontamination and cleaning process of a radioactive refueling pool and develop a special decontamination and cleaning device to remove radioactive pollutants in the radioactive refueling pool, safely and reliably solve the hotspot deposition problem in the radioactive refueling pool, reduce the environmental dose rate level on site, and reduce the collective dose of the staff. By using a decontamination process or a decontamination device in a radioactive refueling pool simulation device to conduct pollutant removal tests, a safe and reliable decontamination working method is explored to ensure that the decontamination operation will not affect the stable operation of the radioactive refueling pool. At the same time, it can reduce the operation time at the decontamination site and improve the decontamination efficiency.

[0040] The radioactive refueling pool simulation device in this case can simulate different application scenarios of the radioactive refueling pool, and is used for research on the decontamination process of the radioactive refueling pool, to achieve decontamination and cleaning of radioactive pollutants in the radioactive refueling pool, improve the decontamination efficiency of the radioactive refueling pool, and ensure the operating safety of operators and the environment around the radioactive refueling pool.

[0041] In this case, based on the functional characteristics of the radioactive refueling pool and the conventional operation form, a decontamination simulation body similar to the radioactive refueling pool in a nuclear power plant was developed and designed for the research on the decontamination technology and decontamination process of the radioactive refueling pool. By conducting experimental tests in the decontamination simulation body of the radioactive refueling pool, the feasibility and safety of the decontamination technology were demonstrated, ensuring that the decontamination technology and the decontamination process would not cause damage to the performance of the components inside the radioactive refueling pool, and that the hot spots of pollutants in the radioactive refueling pool could be quickly and effectively removed.

[0042] See also Figure 1-3The present invention provides a radioactive refueling pool simulation device, comprising a pool simulation body 1, a rack mechanism 2 and an internal water circulation mechanism 3; the rack mechanism 2 is arranged in the pool simulation body 1, and is used to carry radioactive components; the internal water circulation mechanism 3 is arranged in the pool simulation body 1, and is used to circulate the fluid in the pool simulation body 1.

[0043] It should be noted that the pool simulation body 1 is used to simulate the body of a real radioactive refueling pool. The shape, size ratio and material selection of the pool simulation body 1 and its internal components should be as close as possible to the actual refueling radioactive refueling pool to ensure the accuracy and reliability of the simulation results. The pool simulation body 1 is usually made of high-strength, corrosion-resistant materials to withstand the long-term corrosion and damage that may be caused by the radioactive environment. In addition, the inner wall of the pool simulation body 1 may need to be coated with a special protective coating to prevent radioactive substances from penetrating and reacting with the pool body material; in the pool simulation body 1, multiple sensors and monitoring equipment can be set to monitor the temperature, pressure, radiation level and chemical composition of the fluid in the radioactive refueling pool in real time. These data are crucial for studying the physical and chemical processes in the radioactive refueling pool, and are also helpful in evaluating the performance and effect of the simulation device. In order to simulate the actual working conditions more realistically, the pool simulation body 1 can also be equipped with a heating and cooling system to control the temperature in the radioactive refueling pool to remain within a specific range, because temperature has a significant effect on the decay and chemical reaction rate of radioactive substances. In addition, a drain port 12 is provided on the water pool simulation body 1 to facilitate the discharge of liquid in the water pool simulation body 1 .

[0044] The rack mechanism 2 is arranged in the water pool simulation body 1, and its main function is to carry radioactive components. In a nuclear power plant, the radioactive fuel assemblies taken out of the reactor during refueling usually need to be placed in the refueling radioactive refueling pool for cooling and storage; therefore, the rack mechanism 2 is arranged in the simulation device to accurately simulate this process. The rack mechanism 2 should have sufficient strength and stability to bear the weight of the radioactive components and prevent them from shaking or tilting in the radioactive refueling pool; at the same time, the design of the rack mechanism 2 should take into account the convenience of placing and removing radioactive components, and the layout in the radioactive refueling pool should comply with the operating specifications of the actual refueling radioactive refueling pool. The rack mechanism 2 can also be equipped with positioning and fixing devices to ensure that the position of the radioactive components in the radioactive refueling pool is accurate and will not move due to water flow or other external forces, so as to ensure the repeatability and accuracy of the simulation experiment.

[0045] The internal water circulation mechanism 3 is one of the key components of the radioactive refueling pool simulation device; it is arranged in the water pool simulation body 1, and is used to circulate the fluid in the water pool simulation body 1. By simulating the flow of water, the diffusion and mixing of radioactive substances in the radioactive refueling pool and the impact on the surrounding environment can be better studied. The internal water circulation mechanism 3 is usually composed of a water pump, a pipe and a valve, etc. The water pump provides power to form a circulation flow in the radioactive refueling pool. The pipe connects various parts of the radioactive refueling pool to ensure smooth water circulation. The valve is used to adjust the flow and direction of water to meet different experimental requirements. In order to simulate the actual working conditions more accurately, the internal water circulation mechanism 3 can also be equipped with monitoring equipment such as flow sensors and pressure sensors to monitor the flow rate and pressure changes of water in real time. These data can help researchers understand the fluid dynamics behavior in the radioactive refueling pool and provide a basis for optimizing the design and management of the radioactive refueling pool.

[0046] This case is based on the operation and maintenance scenario of the radioactive refueling pool at the nuclear power site. According to the functional modules in the radioactive refueling pool, a simulated functional body with the same form and proportional reduction is designed in the simulated radioactive refueling pool, which has the ability to restore the operation and maintenance status of the on-site functional components.

[0047] In this case, a radioactive refueling pool simulation device is designed according to the internal functional modules of the radioactive refueling pool at the nuclear power site. It is used to simulate the functional status of the internal components of the radioactive refueling pool of the nuclear power plant, and develops targeted radioactive hotspot decontamination technology and special devices for different functional components to improve the decontamination efficiency of radioactive hotspots. At the same time, the decontamination technology is verified by conducting preliminary tests in the decontamination simulation body to explore the best decontamination process, avoid the impact on the internal structure and system of the radioactive refueling pool during the decontamination process, and ensure that the radioactive pollutants inside the radioactive refueling pool are cleaned and decontaminated non-destructively while effectively decontaminating.

[0048] This case simulates the internal functional component structure of the radioactive refueling pool, and through simulated operation, finds out the decontamination locations that are prone to form radioactive hotspots, formulates a special decontamination and cleaning implementation plan, and improves the cleaning and decontamination efficiency of on-site decontamination implementation.

[0049] In this case, a special decontamination device is developed by simulating the structure of the internal functional components of the radioactive refueling pool and combining the movement state of the internal functional components of the radioactive refueling pool to avoid interference with the internal functional components of the radioactive refueling pool during the decontamination process. Testing is carried out in a simulated body to avoid equipment interference during on-site decontamination, which may affect the decontamination operation or reduce the decontamination effect. At the same time, it can shorten the on-site decontamination time, reduce the radiation dose of operators, and protect the health of operators.

[0050] In this case, a monitoring and control module 9 system is set up, which can not only monitor the movement state of the functional structural parts inside the entire simulation body, but also monitor the decontamination process when conducting a decontamination simulation test, and is used to adjust the decontamination process parameters and the state of the decontamination device to obtain the optimal decontamination process parameters. When applied to the decontamination site, a higher decontamination efficiency can be obtained.

[0051] In this case, a decontamination simulation body of a radioactive refueling pool is used to design a special decontamination device for the radioactive refueling pool. The device can be used to carry out application tests on the decontamination of the radioactive refueling pool and to evaluate the performance of the internal structural components of the radioactive refueling pool during and after the decontamination process. This ensures that the internal system of the radioactive refueling pool will not be affected during on-site decontamination applications, thereby ensuring the stable operation of the nuclear power unit.

[0052] An internal water circulation mechanism 3 is designed inside the decontamination simulation body of the radioactive refueling pool in this case, which is used for the flow of the medium inside the radioactive refueling pool, so that the water inside the radioactive refueling pool can maintain a flowing state, avoid the long-term placement of the medium inside the radioactive refueling pool, resulting in medium deterioration and pollution of the laboratory environment, and avoid the problem of wastewater being unable to be discharged and disposed of, ensure the cleanliness of the medium inside the radioactive refueling pool, and ensure that the decontamination simulation body of the entire radioactive refueling pool is in a green and clean operation and maintenance state.

[0053] See also Figure 1 , 6 -9, as an optional embodiment of the present case, a bottom supporting structure 13 is provided at the bottom of the water pool simulation body 1, so as to facilitate the support of the bottom of the water pool simulation body 1 and facilitate the movement of the water pool simulation body 1 by a forklift.

[0054] See also Figure 1 , 5 As an optional embodiment of the present invention, an internal support member 14 is provided in the water pool simulation body 1 to facilitate the stability of the overall structure of the water pool simulation body 1.

[0055] See also Figure 1 , 6 -9, as an optional embodiment of the present case, the rack mechanism 2 includes a conveying component 21 and a first rack 22; the conveying component 21 is arranged in the pool simulation body 1; the first rack 22 is arranged on the conveying component 21;

[0056] The water pool simulation body 1 includes a material delivery hole 11 , which is located in the delivery direction of the delivery assembly 21 , and the first storage rack 22 is extended toward the material delivery hole 11 .

[0057] It should be noted that the main function of the conveying assembly 21 is to move the radioactive component from one position to another to simulate the transfer and position change of the fuel assembly during the actual refueling process. The conveying assembly 21 can be in various forms, such as a conveying chain, a conveying track 211, etc. According to actual needs, a suitable conveying method can be selected. In order to ensure the safety and reliability of the conveying process, the conveying assembly 21 can also be equipped with a guide device and a positioning device. The guide device is used to help the conveying assembly 21 run on a predetermined track to prevent it from deviating from the direction; the positioning device can accurately control the position of the radioactive component during the conveying process. The first rack 22 is a part of the rack mechanism 2 for carrying the radioactive component. The first rack 22 is arranged on the conveying assembly 21 and moves with the movement of the conveying assembly 21, so as to realize the conveying and placement of the radioactive component. For example, the bottom of the first rack 22 is provided with a roller 221 matching the conveying track 211, and the movement drive of the first rack 22 is realized by the cooperation of the motor, the gear, and the rack. The design of the first rack 22 should take into account the characteristics of the radioactive components and the requirements of the simulation experiment. The first rack 22 usually has sufficient strength and stability to withstand the weight of the radioactive components and other forces that may be applied. The first rack 22 can also be equipped with a fixing device, such as a clamp, a slot, etc., for firmly fixing the radioactive components on the rack to prevent them from moving or shaking during transportation and simulation. The water pool simulation body 1 includes a feed hole 11, which is located in the conveying direction of the conveying assembly 21, and the first rack 22 extends toward the feed hole 11. The function of the feed hole 11 is to provide a channel for the radioactive components to enter the refueling pool simulation body 1. The size and shape of the feed hole 11 should be designed according to the size of the radioactive components and the requirements of the simulation experiment. The feed hole 11 can be a hole of a circular, square or other shape to accommodate radioactive components of different types and sizes. The edge of the feed hole 11 should be smooth to avoid scratching or damage to the radioactive components. Some guiding devices and positioning devices can be arranged around the feeding hole 11 to help the radioactive component accurately enter the feeding hole 11. The guiding device can be in the form of a slope, a guide rail, etc., so that the radioactive component can slide smoothly into the feeding hole 11, and the positioning device can ensure that the radioactive component is in the correct position and posture after entering the feeding hole 11, so that the subsequent simulation experiment can be carried out accurately.

[0058] See also Figure 1 , 6-9, as an optional embodiment of the present case, the conveying assembly 21 includes a conveying track 211 and a first driving assembly 212, the conveying track 211 is arranged in the water pool simulation body 1, the conveying track 211 is fixedly connected or detachably connected to the water pool simulation body 1, the first rack 22 is matched and arranged on the conveying track 211, and the first driving assembly 212 is transmission-connected with the first rack 22 to drive the first rack 22 to move along the conveying track 211. The first driving assembly 212 includes a first driving motor 2121 and a transmission assembly 2122, and the first driving motor 2121 is transmission-connected with the first rack 22 through the transmission assembly 2122. The first rack 22, the conveying track 211 and the first driving assembly 212 are used to simulate the fuel conveying mechanism, simulating the operation and maintenance scenario in which the spent fuel is lifted out of the reactor by the material replacement machine and placed on the rack mechanism 2, and the fuel is transported by the transport vehicle in the rack mechanism 2. By simulating the fuel transportation and operation and maintenance scenario, a customized pool cleaning mechanism is designed without affecting the normal operation and maintenance of the on-site mechanism, and simulating the actual use environment, the pollutant hotspot area can also be obtained, which is convenient for formulating the pool cleaning and decontamination plan.

[0059] See also Figure 1 , 6 -9, as an optional embodiment of the present case, the rack mechanism 2 also includes a second rack 23, a cover plate 24 and a second drive assembly 25; the second rack 23 is arranged above the first rack 22, and the end of the second rack 23 away from the feeding hole 11 is hingedly connected to the first rack 22 or the conveying assembly 21; the cover plate 24 is arranged on the upper part of the second rack 23; the second drive assembly 25 is used to drive the second rack 23 to rotate around the hinge to adjust the angle.

[0060] It should be noted that the second rack 23 is another important part of the rack mechanism 2. It is arranged above the first rack 22. The second rack 23 is designed to provide more placement space to accommodate radioactive components of different types and sizes. At the same time, the second rack 23 can also be adjusted and changed according to actual needs to meet different experimental requirements. The structure of the second rack 23 is similar to that of the first rack 22, and is usually composed of a frame, a support rod, and a connector. The frame can be made of metal material with good strength and stability. The support rod is used to support the frame and bear the weight of the radioactive component. The connector is used to connect the second rack 23 with the first rack 22 or the conveying assembly 21 to ensure the stability and reliability of the entire rack mechanism 2. In order to facilitate the placement and removal of radioactive components, the second rack 23 can also be designed as a multi-layer or multi-column structure; each layer or each column can be placed with a certain number of radioactive components to improve the efficiency and flexibility of the simulation device. In addition, the second rack 23 can also be equipped with a fixing device, such as a clamp, a slot, etc., for firmly fixing the radioactive component on the rack to prevent it from moving or shaking during transportation and simulation. The cover plate 24 is arranged on the upper part of the second rack 23 to cover the top opening of the second rack 23. The function of the cover plate 24 is to prevent the radioactive material from splashing or leaking and protect the surrounding environment and the safety of the operator. The cover plate 24 is usually made of wear-resistant and corrosion-resistant materials, such as metal or plastic. Its size should match the top opening of the second rack 23 to ensure that the opening can be completely covered. The cover plate 24 can be designed to be detachable, so that it can be installed and removed when necessary. For example, a fixing device such as a screw or a buckle can be set on the cover plate 24 so that it can be firmly fixed on the second rack 23. In order to facilitate the observation of the placement of the radioactive components in the second rack 23, the cover 24 can be made of transparent or translucent materials or provided with an observation hole; in this way, the operator can directly observe the position and state of the radioactive components through the cover 24 without opening the cover 24 for viewing. The second drive assembly 25 is used to drive the second rack 23 to rotate around the hinge to adjust the angle. Through the action of the second drive assembly 25, the second rack 23 can be tilted or rotated within a certain range, thereby changing the placement angle and position of the radioactive components. The second drive assembly 25 is generally composed of a motor, a reducer, a transmission shaft, and a control device. The motor provides power, reduces the speed and increases the torque through the reducer, and then transmits the power to the second rack 23 through the transmission shaft. The control device is used to control the operation of the motor to achieve the angle adjustment of the second rack 23. The second drive assembly 25 can be operated manually or automatically. In manual mode, the operator can directly control the operation of the motor through a handle or other operating device to achieve the angle adjustment of the second rack 23.In the automatic mode, the operator can use preset programs or parameters to let the control device automatically control the operation of the motor to adjust the angle of the second rack 23, which can improve the accuracy and efficiency of the simulation experiment and reduce the influence of human factors.

[0061] See also Figure 3 , 6 -9, as an optional embodiment of the present case, the second drive assembly 25 includes a discharge drive motor 251 and a rope roller 252, the discharge drive motor 251 drives the rope roller 252 to rotate to tighten or loosen the rope 253 connected to the second rack 23 or the cover 24, the cover 24 is generally connected to the second rack 23, so as to adjust the angle of the second rack 23, the second rack 23 and the cover 24 are enclosed to form a cavity, when it is necessary to place the radioactive component in the second rack 23, by adjusting the angle of the second rack 23, the radioactive component can be smoothly placed in the second rack 23, so as to prevent the liquid in the pool simulation body 1 from splashing, causing the radioactive material already placed in the pool simulation body 1 to splash and cause contamination.

[0062] See also Figure 1-2 5. As an optional embodiment of the present invention, the internal water circulation mechanism 3 includes a first pipeline 31 and a filtering and purifying device 32 and a first circulating water pump 33 arranged in the first pipeline 31;

[0063] The first pipeline 31 includes a liquid extraction end and a liquid discharge end which are disposed apart from each other, and at least the liquid extraction end is located in the pool simulation body 1 .

[0064] It should be noted that the internal water circulation mechanism 3 is used to circulate the fluid in the pool simulation body 1 to improve the mixing and cooling effect of the radioactive material in the pool; the mechanism includes a first pipeline 31 and a filtering and purifying device 32 and a first circulating water pump 33 arranged in the first pipeline 31. The liquid extraction end is an end for extracting liquid from the pool simulation body 1, and the liquid discharge end is an end for discharging liquid into the pool simulation body 1. At least the discharge end is located in the pool simulation body 1, and the liquid discharge end can also be arranged in the pool simulation body 1. The first pipeline 31 connects different parts of the pool simulation body 1 so that the fluid can circulate therein. The first pipeline 31 includes a liquid extraction end and a liquid discharge end that are arranged far apart. The liquid extraction end is located at a specific position in the pool simulation body 1, and is used to extract the fluid in the pool. The liquid discharge end is located at another position of the pool simulation body 1, and is used to discharge the fluid after filtering and purification back into the pool. Through this design, the circulation of fluid in the pool can be achieved, and the mixing and cooling effect of radioactive substances can be improved. In the first pipeline 31, some valves and control devices can also be set to adjust the flow rate and flow direction of the fluid; these valves and control devices can be adjusted according to actual needs to meet different experimental requirements. For example, the flow rate of the fluid can be controlled by adjusting the opening of the valve, or the flow direction of the fluid can be adjusted by changing the setting of the control device. The filtering and purification device 32 is arranged on the first pipeline 31, and is used to filter and purify the extracted fluid. The function of the filtering and purification device 32 is to remove impurities, particulate matter and / or radioactive substances in the fluid to ensure the cleanliness and safety of the fluid. The filtering and purification device 32 usually adopts a variety of filtering technologies and materials, such as filters, filter screens, etc. The filter can effectively remove large particle impurities and suspended matter in the fluid. The filter screen can further filter out smaller particles. The first circulating water pump 33 is the power source of the internal water circulation mechanism 3, and is used to drive the fluid to circulate in the first pipeline 31. The first circulating water pump 33 is usually a centrifugal pump or an axial flow pump, etc., which has a high flow rate and head to meet the requirements of fluid circulation in the pool simulation body 1.

[0065] See also Figure 1 , 5 As an optional embodiment of the present case, the radioactive refueling pool simulation device also includes a pipeline simulation mechanism 4, and the pipeline simulation mechanism 4 is at least partially arranged in the pool simulation body 1 to simulate the pipeline layout in the pool simulation body 1.

[0066] It should be noted that the pipeline simulation mechanism 4 is an application scenario for simulating the pipeline layout in the water pool simulation body 1, and it is at least partially arranged in the water pool simulation body 1. The role of the pipeline simulation mechanism 4 is to simulate the layout and operation of the pipeline system in the actual nuclear power plant, so as to better understand and evaluate the transmission and diffusion laws of radioactive substances in the pipeline. In view of the complex operation and maintenance environment of the pipeline in the water pool, and the areas where radioactive pollutant hotspots are easily formed, a special decontamination implementation plan is formulated to improve the decontamination efficiency under the complex pipeline environment and complete the decontamination under complex pipeline conditions. The pipeline simulation mechanism 4 is usually composed of a plurality of pipelines, which can be straight, curved or branched to simulate different connection methods and layouts in the actual pipeline system. The diameter, length and material of the pipeline can be selected and adjusted according to actual needs to adapt to different experimental requirements. The pipeline simulation mechanism 4 can also include some auxiliary equipment and components, such as pumps, valves, flow meters, etc. These devices can be used to control and adjust the flow velocity, flow rate and pressure of the fluid in the pipeline to more accurately simulate the operation of the actual pipeline system. One end or part of the pipeline simulation mechanism 4 is located inside the water pool simulation body 1 and contacts the water in the water pool. In this way, the pipeline simulation mechanism 4 can better simulate the interaction between the actual pipeline system and the water pool, such as the flow of fluids, heat transfer and mass transfer processes. The pipeline simulation mechanism 4 can also be used to study the leakage detection and repair technology of the pipeline system. By simulating pipeline leakage and observing the diffusion law of radioactive substances in the pipeline and the water pool, the effectiveness of different leakage detection methods and repair technologies can be evaluated, providing a reference for the safety management of actual nuclear power plants.

[0067] See also Figure 1-2 5. As an optional embodiment of the present case, the radioactive refueling pool simulation device also includes a ladder simulation mechanism 5 arranged in the pool simulation body 1 to simulate the ladder structure in the pool simulation body 1.

[0068] It should be noted that the ladder simulation mechanism 5 is to simulate the environment inside the pool simulation body 1 more realistically. For the areas around and inside the ladder structure that are prone to form radioactive contaminant hotspots in the pool operating environment, a special decontamination implementation plan is formulated to improve the decontamination efficiency in the complex ladder structure environment and complete the decontamination at the ladder structure. In particular, when it is necessary to simulate the operation of personnel inside the pool in maintenance, overhaul or emergency situations, by setting the ladder simulation mechanism 5 inside the pool simulation body 1, a climbing experience close to reality can be provided for the operator, which helps to evaluate their performance and safety in actual situations. The design of the ladder simulation mechanism 5 should take into account ergonomic principles to ensure comfort and safety during climbing. For example, the height, width and spacing of the ladder should meet standard specifications to prevent accidents such as slipping or falling during climbing. The ladder simulation mechanism 5 can also be used for training and drill purposes. By simulating the actual ladder structure, operators can be trained and drilled to improve their skill level and coping ability. The ladder simulation mechanism 5 is usually used together with other simulation mechanisms to provide a more comprehensive simulation experience.

[0069] See also Figure 1-2 5. As an optional embodiment of the present case, the radioactive refueling pool simulation device also includes at least one group of hole and slot simulation components 6 arranged in the pool simulation body 1; the hole and slot simulation components 6 are arranged horizontally and / or vertically and / or obliquely in the pool simulation body 1.

[0070] It should be noted that the hole slot simulation component 6 is to simulate the structural features inside the pool simulation body 1 more realistically, such as simulating some small and complex hole slot structures such as the feed hole 11 and the structural slot in the pool. During the operation and maintenance of the pool, radioactive pollutants are most likely to accumulate inside it, forming radioactive hot spots. At the same time, due to the narrow hole slot space, the decontamination equipment has the problem of being inaccessible, which is also the difficulty of decontamination. Therefore, by simulating different hole slot environments, exploring different decontamination technologies and special decontamination devices, it is important to clean the hole slot inside the pool. Especially when it is necessary to simulate discontinuous areas such as loopholes, cracks or holes in the pool, these hole slot simulation components 6 can help researchers better understand the distribution and flow of radioactive materials in the pool. The shape and size of the hole slot simulation component 6 can be designed according to actual needs to simulate different types of holes or cracks. For example, the hole slot simulation component 6 can be made into different shapes such as round, square, and elliptical. The hole slot simulation component 6 can be arranged horizontally, vertically and / or obliquely in the pool simulation body 1. This flexible arrangement can better adapt to different experimental requirements, allowing researchers to more accurately simulate the distribution and flow of radioactive materials in different directions. When arranged horizontally, the hole slot simulation component 6 can simulate horizontal cracks or holes in the pool; when arranged vertically, it can simulate cracks or holes in the vertical direction; and when arranged obliquely, it can simulate cracks or holes in the inclined direction. The hole slot simulation component 6 is particularly suitable for experiments that need to study the distribution and flow of radioactive materials in local areas of the pool. For example, in some cases, researchers may only focus on the changes in the concentration of radioactive materials in a specific area. At this time, the hole slot simulation component 6 can be set in the area to achieve accurate measurement and observation of the local area. In addition, the hole slot simulation component 6 can also be used in combination with other simulation mechanisms, such as the pipeline simulation mechanism 4, the ladder simulation mechanism 5, etc., to provide a more comprehensive simulation experience.

[0071] See also Figure 1-2 5. As an optional embodiment of the present case, at least one group of the hole slot simulation components 6 of the radioactive refueling pool simulation device is provided with a second pipeline 7 for liquid supply, and the lower part of the hole slot simulation component 6 of the group is provided with a discharge outlet 71.

[0072] It should be noted that the second pipeline 7 can simulate the liquid supply system in the pool on the one hand. By supplying liquid to the hole slot simulation component 6, the water environment inside the pool can be reproduced more realistically, which helps researchers better understand the distribution and flow of radioactive substances in the pool. On the other hand, the second pipeline 7 supplies liquid to the hole slot simulation component 6, so that after the radioactive refueling pool simulation device completes the simulation, the hole slot simulation component 6 is supplied with liquid to facilitate the cleaning of the hole slot simulation component 6. The diameter and length of the second pipeline 7 should be selected according to actual needs to meet the requirements of the liquid supply amount. The second pipeline 7 can also be equipped with valves, flow meters and other equipment to adjust the liquid supply amount and monitor the flow rate. The discharge port 71 is used to discharge the liquid in the hole slot simulation component 6 for subsequent measurement and analysis. By setting the discharge port 71, it is more convenient to obtain the liquid sample in the hole slot simulation component 6, so as to more accurately measure the concentration and distribution of radioactive substances. The discharge port 71 is usually located at the lower part of the hole slot simulation component 6 to facilitate the natural discharge of the liquid.

[0073] See also Figure 1-2 5. Further, the hole groove simulation component 6 includes a vertical hole simulation unit 61 for simulating vertical holes in the water pool simulation body 1 and / or a horizontal hole simulation unit 62 for simulating horizontal holes in the water pool simulation body 1.

[0074] See also Figure 1-2 5. Further, the second pipeline 7 is arranged at the vertical hole simulation unit 61, a second circulating water pump 63 is arranged on the second pipeline 7, and the discharge port 71 is arranged at the lower part of the vertical hole simulation unit 61.

[0075] See also Figure 1-2 5. As an optional embodiment of the present case, the radioactive refueling pool simulation device also includes a monitoring component 8 for monitoring the operation of the radioactive refueling pool simulation device itself, and the monitoring component 8 includes a monitoring camera 81 and a display device 82 connected to the monitoring camera 81.

[0076] It should be noted that the monitoring component 8 is designed to ensure the safe, stable and effective operation of the radioactive refueling pool simulation device. By monitoring the working status of the device in real time, potential faults or abnormal conditions can be discovered and handled in a timely manner to ensure the accuracy and reliability of the experiment. The monitoring camera 81 can capture images inside the device to help operators observe the distribution and flow of radioactive materials and the operating status of the device. The display device 82 is used to display the images and data information captured by the monitoring camera 81, so that the operator can intuitively understand the working status of the device. The display device 82 can be a display screen or a mobile phone or a computer. The monitoring camera 81 usually adopts a high-resolution, waterproof, dustproof and radiation-resistant design to meet the special requirements of the radioactive environment. The number and arrangement of the cameras should be adjusted according to actual needs to ensure effective monitoring of key areas inside the device. The camera can also be equipped with night vision function or infrared function so that images can be clearly captured under low light conditions. The display device 82 can also have a touch screen function or a mouse control function to facilitate the operator to operate and set up. For a multi-camera monitoring system, the display device 82 can also support multi-screen split display or switching display function. By real-time monitoring of the device's working status and the distribution of radioactive materials, operators can promptly adjust experimental parameters or take necessary safety measures to ensure the smooth progress of the experiment and the safety of personnel.

[0077] See also Figure 1-2 5. As an optional embodiment of the present case, the radioactive refueling pool simulation device also includes a control module 9, and the control module 9 is configured to control the operation of the storage rack mechanism 2 and / or the internal water circulation mechanism 3.

[0078] It should be noted that the control module 9 is designed to realize the automatic control of each mechanism in the radioactive refueling pool simulation device. Through the control module 9, the rack mechanism 2 and the internal water circulation mechanism 3 can be easily operated and adjusted to simulate the operating state of the pool under different working conditions. The control module 9 can receive the command signal from the operator or the feedback signal from the sensor, and adjust the operating parameters of the rack mechanism 2 and the internal water circulation mechanism 3 according to these signals to achieve accurate control and monitoring. The control module 9 usually adopts advanced control technologies such as microprocessors or programmable logic controllers (PLCs), and has high reliability and stability. The control module 9 can also be equipped with a human-machine interface (HMI) to facilitate the operator to operate and monitor. Through the human-machine interface, the operator can intuitively understand the working state of the device, set parameters, and view alarm information. The control module 9 can also support remote communication functions, allowing operators to remotely access and control through the network. Through the control module 9, the lifting, rotating and other operations of the storage rack mechanism 2, as well as the starting, stopping and adjusting functions of the internal water circulation mechanism 3 can be realized, which helps to simulate the operating state of the pool under actual working conditions and provide researchers with more accurate experimental data and analysis results.

[0079] In summary, the present invention effectively overcomes some practical problems in the prior art and thus has high utilization value and use significance.

[0080] The above embodiments are merely illustrative of the principles and effects of the present invention, and are not intended to limit the present invention. Anyone familiar with the art may modify or alter the above embodiments without departing from the spirit and scope of the present invention. Therefore, all equivalent modifications or alterations made by a person of ordinary skill in the art without departing from the spirit and technical concept disclosed by the present invention shall still be covered by the claims of the present invention.

Claims

1. A radioactive refueling pool simulation device, characterized in that: include: Pool simulation body; A rack mechanism, disposed in the water pool simulation body, for carrying radioactive materials; The internal water circulation mechanism is arranged in the water pool simulation body and is used for circulating the fluid in the water pool simulation body.

2. The radioactive refueling pool simulation device according to claim 1, characterized in that: The storage rack mechanism comprises: A conveying component is arranged in the water pool simulation body; A first storage rack, disposed on the conveying assembly; The water pool simulation body comprises a material delivery hole, the material delivery hole is located in the delivery direction of the delivery component, and the first storage rack is extended toward the direction of the material delivery hole.

3. The radioactive refueling pool simulation device according to claim 2, characterized in that: The storage rack mechanism also includes: A second rack is disposed above the first rack, and one end of the second rack away from the feeding hole is hingedly connected to the first rack or the conveying assembly; A cover plate, arranged on the upper part of the second storage rack; The second driving assembly is used to drive the second storage rack to rotate around the hinge to adjust the angle.

4. The radioactive refueling pool simulator according to claim 1, characterized in that: The internal water circulation mechanism includes a first pipeline, a filtering and purifying device and a first circulating water pump arranged in the first pipeline; The first pipeline includes a liquid extraction end and a liquid discharge end which are arranged far apart from each other, and at least the liquid extraction end is located in the water pool simulation body.

5. The radioactive refueling pool simulator according to claim 1, characterized in that: It also includes a pipeline simulation mechanism, which is at least partially arranged in the water pool simulation body to simulate the pipeline arrangement in the water pool simulation body.

6. The radioactive refueling pool simulator according to claim 1, characterized in that: It also includes a ladder simulation mechanism arranged in the water pool simulation body to simulate the ladder structure in the water pool simulation body.

7. The radioactive refueling pool simulator according to claim 1, characterized in that: Also included is at least one group of hole and slot simulation components disposed in the pool simulation body; The hole and groove simulation components are arranged horizontally, vertically and / or obliquely in the water pool simulation body.

8. The radioactive refueling pool simulation device according to claim 7, characterized in that: A second pipeline for supplying liquid is disposed at at least one group of the hole and groove simulation components, and a liquid discharge port is disposed at the lower portion of the hole and groove simulation components of the group.

9. The radioactive refueling pool simulator according to claim 1, characterized in that: It also includes a monitoring component for monitoring the operation of the radioactive refueling pool simulation device itself.

10. The radioactive refueling pool simulation device according to claim 1, characterized in that: It also includes a control module, which is configured to control the operation of the storage rack mechanism and / or the internal water circulation mechanism.

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