Transportation device for spent fuel of nuclear power plant, and spent fuel processing system

Abstract

A transportation device (100) for spent fuel of a nuclear power plant and a spent fuel processing system, relating to the technical field of spent fuel processing, and capable of realizing underground loading operations for spent fuel in spent fuel pits. The transportation device (100) for spent fuel of a nuclear power plant comprises a basket assembly (110), a housing assembly (120) and a lid assembly (130), wherein a plurality of storage cavities (111) are formed inside the basket assembly (110), and the storage cavities (111) are used for storing spent fuel; an accommodating cavity (1211) having one end provided with an opening (1212) is formed inside the housing assembly (120); the basket assembly (110) is mounted inside the accommodating cavity (1211); a first fuel port (1213) is formed in the peripheral side of the end of the housing assembly (120) provided with the opening (1212), and a plurality of second fuel ports (1214) are formed in the peripheral side of the end away from the opening (1212); and the lid assembly (130) is sealingly mounted on the opening (1212) and is provided with an inflation inlet (1333), and the inflation inlet (1333) is communicated with the first fuel port (1213) and the second fuel ports (1214) by means of the accommodating cavity (1211).

Description

Nuclear power plant spent fuel transport equipment and spent fuel processing system

[0001] Related applications

[0002] This application claims priority to Chinese patent application filed on March 24, 2025, with application number 2025103474991 and entitled “Nuclear Power Plant Spent Fuel Transport Equipment and Spent Fuel Processing System”, the entire contents of which are incorporated herein by reference. Technical Field

[0003] This application relates to the field of spent fuel processing technology, and in particular to a spent fuel transportation device and a spent fuel processing system for nuclear power plants. Background Technology

[0004] Spent fuel, also known as irradiated nuclear fuel, is nuclear fuel that has been exposed to radiation and has been used. It is usually produced by the nuclear reactors of nuclear power plants. The fuel undergoes a nuclear reaction inside the reactor after being bombarded with neutrons, and is then removed from the reactor after a certain period. This fuel has a reduced uranium content and can no longer sustain a nuclear reaction, hence the name spent fuel. Spent nuclear fuel contains a large amount of radioactive elements and is therefore radioactive. If not properly handled, it can seriously affect the environment and the health of those exposed to it.

[0005] Spent fuel transport containers are indispensable safety transport equipment in the fuel reprocessing process. These containers must meet functions such as airtight containment, radiation shielding, critical safety, and residual heat removal. For high-burnup fuel assemblies with a certain burnup depth, the technical requirements for achieving these safety functions are even higher. Currently, there is a lack of spent fuel transport containers suitable for downhole loading operations, making it difficult to ensure the safe and stable operation of nuclear power plants and achieve the goal of off-site spent fuel storage. Summary of the Invention

[0006] Therefore, it is necessary to provide a nuclear power plant spent fuel transportation equipment and spent fuel handling system to address the lack of spent fuel transportation containers that can be used for downhole loading operations.

[0007] To achieve the above objectives, the technical solution adopted in this application is as follows:

[0008] In a first aspect, embodiments of this application provide a spent fuel transportation device for nuclear power plants, used for underground spent fuel loading operations. The spent fuel transportation device for nuclear power plants includes:

[0009] The basket assembly has multiple storage chambers inside, which are used to store spent fuel;

[0010] The outer shell assembly has an internal receiving cavity with an open end. The basket assembly is installed in the receiving cavity. The outer shell assembly has a first material port on the periphery of the open end and multiple second material ports on the periphery of the end away from the open end.

[0011] The cover assembly is sealed and installed at the opening and is provided with an air inlet. The air inlet is connected to the first material inlet and each of the second material inlets through a receiving cavity.

[0012] In one embodiment of the first aspect, the spent fuel transport equipment for the nuclear power plant further includes two damping components, one damping component being mounted on the cover assembly and the other damping component being mounted on the outer shell assembly at the end away from the cover assembly.

[0013] In one embodiment of the first aspect, each damping component includes a buffer and a rigid member, the rigid member covering the outside of the buffer, and the rigid members of the two damping components respectively fix the corresponding buffers to the end of the cover assembly and the outer shell assembly away from the opening.

[0014] In one embodiment of the first aspect, the cover assembly includes an outer cover, a clamping cover, and an inner cover, all of which are sequentially sealed to the opening of the outer shell assembly. The inner cover has an inflation port, and the clamping cover has a corresponding through hole so that the inflation port can be exposed to the through hole.

[0015] In one embodiment of the first aspect, the inner cover includes a third cover body, the third cover body having a lifting boss at its center;

[0016] The inflation port is located in the third cover, and a quick connector is provided inside the inflation port. The outer cover also includes a hole cover, which seals and covers the inflation port.

[0017] In one embodiment of the first aspect, the basket assembly includes a plurality of sleeves, each sleeve defining a storage cavity forming a square.

[0018] In one embodiment of the first aspect, the sleeve is provided with a boron-aluminum plate and a stainless steel cladding on its periphery, the stainless steel cladding covering the side of the boron-aluminum plate opposite to the sleeve.

[0019] In one embodiment of the first aspect, the suspended platform assembly further includes a top plate, a plurality of support plates, a plurality of heat transfer plates, mounting plates, a bottom plate, and threaded rods, wherein the threaded rods are connected in series with the top plate, each support plate, each heat transfer plate, mounting plates, and the bottom plate, and the support plates and heat transfer plates are arranged at intervals.

[0020] In one embodiment of the first aspect, a positioning block is provided between a set of adjacent support plates and heat transfer plates, and the positioning block is mounted on a threaded rod.

[0021] In one embodiment of the first aspect, the housing assembly includes a cylindrical body, a support ring, and a lifting trunnion. The end of the cylindrical body away from the opening is provided with a second feed port. The support ring is fitted onto the end of the cylindrical body with the opening and has a first feed port. The lifting trunnion is installed on the periphery of the support ring.

[0022] In one embodiment of the first aspect, the housing assembly further includes a shielding layer, a plurality of heat sinks, and a protective shell. The protective shell is fitted onto the outside of the cylinder and defines a cavity between the cylinder and the cylinder. Each heat sink is circumferentially disposed within the cavity and divides the cavity into a plurality of filling cavities. The shielding layer is cast into the filling cavity.

[0023] In one embodiment of the first aspect, a safety valve is provided at the end of the cylinder away from the opening, and the safety valve is in communication with the cavity.

[0024] In one embodiment of the first aspect, a flipping block is provided on one side of the cylinder, and the flipping block has a groove for flipping and receiving force.

[0025] In one embodiment of the first aspect, the cylinder has multiple steps at one open end, the inner cover and the clamping cover are respectively installed on different steps and are completely embedded in the cylinder, and the outer cover is fastened to the end face of the cylinder.

[0026] Secondly, embodiments of this application also provide a spent fuel handling system, including the spent fuel transport equipment of a nuclear power plant described in any of the above embodiments.

[0027] Compared to related technologies, the advantages of this application are as follows: This application provides a spent fuel transportation device and a spent fuel processing system for nuclear power plants, used for downhole spent fuel loading operations. The spent fuel transportation device includes a basket assembly, an outer shell assembly, and a cover assembly. The basket assembly is installed inside the outer shell assembly and has multiple storage chambers for storing spent fuel. The outer shell assembly has a first feed port and multiple second feed ports on its two ends. The cover assembly is sealed to the open end of the outer shell assembly and has an inflation port. In this way, during downhole loading, water is first injected into the spent fuel transportation device through the first and second feed ports to expel internal gases and eliminate the internal negative pressure, facilitating the opening of the cover assembly. Then, the cover assembly is opened, and spent fuel is loaded from the open side. After loading is completed, the cover assembly is sealed closed, and air is injected into the container through the inflation port, causing liquid to drain from the second feed ports, facilitating subsequent waterless transportation operations and realizing the downhole loading operation of spent fuel. Attached Figure Description

[0028] To more clearly illustrate the technical solutions in the embodiments of this application or the conventional technology, the drawings used in the description of the embodiments or the conventional technology will be briefly introduced below. Obviously, the drawings described below are only embodiments of this application. For those skilled in the art, other drawings can be obtained based on the disclosed drawings without creative effort.

[0029] Figure 1 is a schematic diagram of the structure of a nuclear power plant spent fuel transport device in some embodiments of this application.

[0030] Figure 2 is a schematic diagram of the structure of the suspended basket assembly in some embodiments of this application.

[0031] Figure 3 is a schematic diagram of the structure of the housing assembly in some embodiments of this application.

[0032] Figure 4 is a schematic diagram of the appearance structure of the inner cover in some embodiments of this application.

[0033] Figure 5 is a cross-sectional structural diagram of the inner cover in some embodiments of this application.

[0034] Figure 6 is a schematic diagram of the sleeve structure in some embodiments of this application.

[0035] Figure 7 is an enlarged structural diagram of part A in Figure 6.

[0036] Figure 8 is a schematic diagram of the structure of the suspended basket assembly in some embodiments of this application.

[0037] Figure 9 is a magnified schematic diagram of part B in Figure 8.

[0038] Figure 10 is a schematic diagram of the shielding layer structure in some embodiments of this application.

[0039] Figure 11 is a schematic diagram of the bottom structure of the cylinder in some embodiments of this application.

[0040] Figure 12 is a schematic diagram of the enlarged structure of part C in Figure 11.

[0041] Figure 13 is a schematic diagram of the shielding layer structure in some embodiments of this application.

[0042] Figure 14 is a schematic diagram of the structure of the heat pipe in some embodiments of this application.

[0043] Figure 15 is a structural schematic diagram of the shock absorption component in some embodiments of this application.

[0044] Figure 16 is a schematic diagram of the structure of the outer cover in some embodiments of this application.

[0045] Figure 17 is a schematic diagram of the structure of the compression cap in some embodiments of this application.

[0046] Figure 18 is a schematic diagram of the enlarged structure of part D in Figure 17.

[0047] Explanation of reference numerals in the attached drawings: 100, spent fuel transport equipment for nuclear power plants; 110, basket assembly; 111, storage chamber; 112, casing; 113, top plate; 114, support plate; 115, mounting plate; 1151, casing mounting plate; 1152, fuel assembly mounting plate; 116, bottom plate; 117, threaded rod; 118, heat transfer plate; 119, boron-aluminum plate; 1110, stainless steel cladding; 1111, positioning block; 120, outer shell assembly; 121, cylinder; 1211, receiving chamber; 1212, opening; 1213, first feed port; 1214, second feed port; 122, support ring; 123, lifting trunnion; 12 4. Protective shell; 125. Heat dissipation pipe; 126. Heat sink; 127. Shielding layer; 128. Safety valve; 129. Flip block; 130. Cover assembly; 131. Outer cover; 1311. First cover; 1312. Outer cover sealing ring; 1313. Detection hole; 132. Compression cover; 1321. Second cover; 1322. Compression cover sealing ring; 1323. Through hole; 133. Inner cover; 1331. Third cover; 1332. Lifting boss; 1333. Air inlet; 1334. Hole cover; 1335. Quick connector; 140. Shock absorption assembly; 141. Rigid component; 142. Buffer component. Detailed Implementation

[0048] The technical solutions of the embodiments of this application will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of this application, and not all embodiments. Based on the embodiments of this application, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of this application.

[0049] To make the above-mentioned objectives, features, and advantages of this application more apparent and understandable, the specific embodiments of this application are described in detail below with reference to the accompanying drawings. Many specific details are set forth in the following description to provide a thorough understanding of this application. However, this application can be implemented in many other ways different from those described herein, and those skilled in the art can make similar modifications without departing from the spirit of this application. Therefore, this application is not limited to the specific embodiments disclosed below.

[0050] In the description of this application, it should be understood that if terms such as "center", "longitudinal", "lateral", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential" appear, these terms indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings, and are only for the convenience of describing this application and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation, and therefore should not be construed as a limitation of this application.

[0051] Furthermore, where the term "and / or" appears, "and / or" merely describes the relationship between related objects, indicating that three relationships can exist. For example, A and / or B can represent: A existing alone, A and B existing simultaneously, or B existing alone. Additionally, the character " / " in this document generally indicates that the preceding and following related objects have an "or" relationship. Where the terms "first" and "second" appear, these terms are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of technical features indicated. Therefore, features defined with "first" or "second" can explicitly or implicitly include at least one of those features. In the description of this application, where the term "multiple" appears, "multiple" means at least two, such as two, three, etc., unless otherwise explicitly specified.

[0052] In this application, unless otherwise expressly specified and limited, the terms "installation," "connection," "joining," and "fixing," etc., should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral part; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; they can refer to the internal communication of two components or the interaction between two components, unless otherwise expressly limited. Those skilled in the art can understand the specific meaning of the above terms in this application based on the specific circumstances.

[0053] In this application, unless otherwise expressly specified and limited, the use of descriptions such as "above" or "below" the second feature indicates that the first and second features are in direct contact or indirect contact via an intermediate medium. Furthermore, "above," "on top of," and "over" the second feature can mean that the first feature is directly above or diagonally above the second feature, or simply that the first feature is at a higher horizontal level than the second feature. Similarly, "below," "below," and "under" the second feature can mean that the first feature is directly below or diagonally below the second feature, or simply that the first feature is at a lower horizontal level than the second feature.

[0054] It should be noted that if an element is referred to as being "fixed to" or "set on" another element, it can be directly on the other element or there may be an intervening element. If an element is considered to be "connected to" another element, it can be directly connected to the other element or there may be an intervening element. If so, the terms "vertical," "horizontal," "upper," "lower," "left," "right," and similar expressions used in this application are for illustrative purposes only and do not represent the only possible implementation.

[0055] Referring to Figure 1, an embodiment of this application provides a spent fuel transport device 100 for underground spent fuel loading operations. Specifically, the spent fuel transport device 100 includes a basket assembly 110, an outer shell assembly 120, and a cover assembly 130. The basket assembly 110 is used to load spent fuel assemblies and is installed inside the outer shell assembly 120. The cover assembly 130 can be sealed to the outer shell assembly 120 to facilitate sealed transport of spent fuel.

[0056] Referring again to Figures 2 and 3, exemplarily, the basket assembly 110 has multiple storage chambers 111 inside, which are used to store spent fuel. The outer shell assembly 120 has a receiving cavity 1211 with an opening 1212 at one end, and the basket assembly 110 is installed within the receiving cavity 1211. A first feed port 1213 is provided on the periphery of the end of the outer shell assembly 120 with the opening 1212, and multiple second feed ports 1214 are provided on the periphery of the end away from the opening 1212. Referring again to Figures 4 and 5, the cover assembly 130 is sealed and installed in the opening 1212 and has an inflation port 1333. The inflation port 1333 communicates with the first feed port 1213 and each of the second feed ports 1214 through the receiving cavity 1211.

[0057] In a specific embodiment of this application, the assembled spent fuel transport equipment 100 is vertically hoisted into the reactor shaft, and spent fuel assemblies are loaded underground. Because the cover assembly 130 is sealed to the outer shell assembly 120, some air inevitably exists inside, creating a negative pressure state inside the container, making it difficult to open the cover assembly 130. Therefore, when opening the cover, the first feed port 1213 and the second feed port 1214 are opened first, and water is injected into the container through the first feed port 1213 and the second feed port 1214 to expel the gas inside the container, relieve the internal negative pressure state, and facilitate the disassembly of the cover assembly 130. After the cover assembly 130 is removed, the spent fuel assemblies are placed into the storage chambers 111 of the basket assembly 110 using the loading equipment. After all storage chambers 111 are loaded, the cover assembly 130 is closed and sealed. Finally, the second feed port 1214 is opened, and gas is supplied into the container through the gas filling port 1333, while the internal liquid is discharged from the second feed port 1214 to ensure the dry transport of spent fuel from the nuclear power plant to the transport equipment 100.

[0058] Referring again to Figure 6, in some embodiments, the suspended basket assembly 110 includes a plurality of sleeves 112, each sleeve 112 defining a square storage cavity 111.

[0059] Specifically, by using multiple sleeves 112, each sleeve 112 forms a separate storage cavity 111, which facilitates the assembly and disassembly of the basket assembly 110, improves assembly efficiency, and also facilitates the loading of spent fuel assemblies. It can be understood that the spent fuel assembly has a square prism structure, and the sleeve 112 has a corresponding square tube structure, with a storage cavity 111 inside that is adapted to the size of the spent fuel assembly.

[0060] Referring again to Figure 7, in some embodiments, the sleeve 112 is provided with a boron-aluminum plate 119 and a stainless steel cladding 1110 on its periphery, with the stainless steel cladding 1110 covering the side of the boron-aluminum plate 119 away from the sleeve 112.

[0061] Specifically, each of the four sides of the bushing 112 is provided with a boron-aluminum plate 119 to control the spent fuel assembly in a subcritical state. A stainless steel cladding 1110 covers the outside of the boron-aluminum plate 119 to fix the boron-aluminum plate 119 and maintain the operational stability of the bushing 112.

[0062] Referring again to Figure 8, in some embodiments, the suspended platform assembly 110 further includes a top plate 113, a plurality of support plates 114, a plurality of heat transfer plates 118, mounting plates 115, a bottom plate 116, and threaded rods 117. The threaded rods 117 are connected in series with the top plate 113, each support plate 114, each heat transfer plate 118, mounting plates 115, and bottom plate 116. The support plates 114 and the heat transfer plates 118 are arranged at intervals.

[0063] Specifically, the top plate 113, support plate 114, heat transfer plate 118, mounting plate 115, and bottom plate 116 are all circular plate structures and coaxially arranged. Each of these plates has corresponding through holes to facilitate the sequential insertion and assembly of the sleeve 112, thereby limiting the axial and radial displacement of the sleeve 112 within the suspended platform assembly 110. Preferably, the end of the sleeve 112 is provided with a flange face, which abuts against the top plate 113 after assembly and is fixed with bolts, further enhancing the installation strength of the sleeve 112.

[0064] In some embodiments, the mounting plate 115 includes a sleeve mounting plate 1151 and a fuel assembly mounting plate 1152, with the sleeve mounting plate 1151 located on the side of the fuel assembly mounting plate 1152 facing away from the base plate 116. The sleeve mounting plate 1151 is used to support and fix the tail end of the sleeve 112, and the fuel assembly mounting plate 1152 is used to support and fix the tail end of the spent fuel assembly. It is understood that in this embodiment, the tail end refers to the end of the object closer to the base plate 116.

[0065] Referring again to Figure 9, in some embodiments, a positioning block 1111 is provided between a set of adjacent support plates 114 and heat transfer plates 118, and the positioning block 1111 is mounted on the threaded rod 117.

[0066] Specifically, the support plate 114 provides support for the sleeve 112 and the threaded rod 117, forming a complete frame after the threaded rod 117 is connected and inserted. The heat transfer plate 118 dissipates heat from the spent fuel assembly loaded inside the sleeve 112 and maintains a distance from the support plate 114 through the support of the positioning block 1111, thereby preventing the support plate 114 from deforming due to heat and ensuring the heat dissipation efficiency of the heat transfer plate 118. For example, the positioning block 1111 has a square stepped structure to facilitate the assembly of the sleeve 112 and to maintain the stability of the support plate 114 and the heat transfer plate 118.

[0067] Referring again to Figure 3, in some embodiments, the housing assembly 120 includes a cylindrical body 121, a support ring 122, and a lifting trunnion 123. The end of the cylindrical body 121 away from the opening 1212 is provided with a second feed port 1214. The support ring 122 is fitted onto the end of the cylindrical body 121 with the opening 1212 and has a first feed port 1213. The lifting trunnion 123 is installed on the periphery of the support ring 122.

[0068] Specifically, the cylinder 121 serves as the mounting carrier for the basket assembly 110. It is a stainless steel cylinder 121, open at one end and closed at the other, allowing for the installation of the basket assembly 110 and the loading of spent fuel assemblies from the open end 1212. A support ring 122 is fitted onto the open end 1212 of the cylinder 121 and fixed to the cylinder 121 with bolts. Alternatively, in some embodiments, welding can be used to fix the support ring 122 and the cylinder 121; this is not a specific limitation. The support ring 122 provides structural support for the container during the loading process and is compatible with the positioning and loading devices, facilitating the fixing of the spent fuel transport equipment 100 for nuclear power plants.

[0069] For example, the top surface of the support ring 122 has a threaded hole to facilitate the installation of the positioner and the shock absorber during downhole loading. Two square holes are symmetrically arranged on the circumference of the support ring 122 to mate with the lifting trunnion 123. The lifting trunnion 123 is fixed to a groove in the cylinder 121 by bolts and then protrudes through the square hole of the support ring 122. The lifting trunnions 123 are located on the same plane and spaced circumferentially along the cylinder 121 for lifting operations of the spent fuel transport equipment 100 of the nuclear power plant. During downhole loading, the trunnions are matched with the trunnion positioning device for positioning operations.

[0070] In some embodiments, the end face of the closed end of the cylinder 121 is also provided with a threaded hole for the installation of the shock absorber. The top side of the cylinder 121 is provided with a first feed port 1213 and the bottom side is provided with a second feed port 1214, which are matched with the underground loading air-filling and draining valve for air-filling and draining or water-filling and venting operations.

[0071] It should be noted that, to ensure the sealed transport of spent fuel assemblies and prevent leakage, each opening and inlet of the cylinder 121 is equipped with a cover. These are sealed with lead plugs, rotary screw plugs, and rubber O-rings, and a seal test port is also provided for testing the sealing performance.

[0072] In some embodiments, a flipping block 129 is provided on one side of the cylinder 121, and the flipping block 129 has a groove for flipping and receiving force.

[0073] Specifically, the tilting block 129 is disposed at the bottom of the cylinder 121 and welded to the cylinder 121 for tilting the container. The centerline of the tilting block 129 is parallel to the axis of the cylinder 121 and is a certain distance away from the centerline of the container. The groove of the tilting block 129 is adapted to the tilting device to facilitate the tilting force of the spent fuel transport equipment 100 of the nuclear power plant.

[0074] Referring again to Figure 10, in some embodiments, the outer casing assembly 120 further includes a shielding layer 127, a plurality of heat sinks 126, and a protective shell 124. The protective shell 124 is sleeved on the outside of the cylindrical body 121 and defines a cavity between the cylindrical body 121 and the cylindrical body 121. Each heat sink 126 is circumferentially disposed in the cavity and divides the cavity into a plurality of filling cavities. The shielding layer 127 is cast into the filling cavity.

[0075] Specifically, the protective shell 124 is coaxially arranged with the cylinder 121 and forms a cavity with the cylinder 121, top plate 113, and bottom plate 116. The shielding layer 127 can be made of materials such as beryllium, graphite, and uranium-238. The shielding layer 127 is formed by casting the above materials into the cavity. The heat sink 126 is connected to the inner wall of the protective shell 124 and the outer wall of the cylinder 121 on both sides, and is evenly distributed along the axis of the cylinder 121 to evenly separate the shielding layer 127 material within the filling cavity. The even arrangement of the heat sink 126 facilitates heat dissipation within the spent fuel transport equipment 100 of the nuclear power plant and improves the residual heat removal rate of the spent fuel transport equipment 100 of the nuclear power plant.

[0076] Referring again to Figures 11 and 12, in some embodiments, a safety valve 128 is provided at the end of the cylinder 121 away from the opening 1212, and the safety valve 128 communicates with the cavity. The safety valve 128 is located on the closed end face of the cylinder 121 to regulate the pressure inside the cavity and ensure the safety of the spent fuel transport equipment 100 of the nuclear power plant.

[0077] Referring again to Figures 13 and 14, in some other embodiments, a modularly designed heat sink 125 replaces the heat sink 126 in the above embodiments. The heat sink 125 has a filling cavity inside and is circumferentially distributed on the outside of the cylinder 121. A protective layer is also wrapped around the outside of each heat sink 125, and a shielding material is poured into the cavity of the heat sink 125.

[0078] Referring again to Figure 15, in some embodiments, the spent fuel transport equipment 100 of the nuclear power plant further includes two shock-absorbing components 140, one of which is mounted on the cover assembly 130 and the other is mounted on the outer shell assembly 120 at the end away from the cover assembly 130.

[0079] Specifically, the cover assembly 130 is installed on the open side 1212 of the cylinder 121. One shock-absorbing assembly 140 is bolted to the cover assembly 130, and the other shock-absorbing assembly 140 is bolted to the closed end of the cylinder 121. With the two shock-absorbing assemblies 140 installed, the spent fuel transport equipment 100 is placed horizontally during transport. The outer diameter of the shock-absorbing assembly 140 is larger than the outer diameter of the cylinder 121, and it is coaxially arranged with the cylinder 121. Thus, when placed horizontally, the two symmetrically arranged shock-absorbing assemblies 140 act as stress points, reducing vibration during transport and ensuring stable transport of spent fuel.

[0080] In some embodiments, each shock-absorbing component 140 includes a buffer 142 and a rigid component 141. The rigid component 141 covers the outside of the buffer 142. The rigid components 141 of the two shock-absorbing components 140 respectively fix the corresponding buffer 142 to the end of the cover assembly 130 and the outer shell assembly 120 away from the opening 1212.

[0081] Specifically, the buffer 142 can absorb vibrations during transportation to ensure stable transportation of spent fuel. The rigid member 141 may be made of stainless steel plate, which covers the outside of the buffer 142 to connect with the cylinder 121 and fix the buffer 142.

[0082] For example, the buffer 142 can be made of wood to absorb the impact energy generated by the fall of the spent fuel transport equipment 100 from the nuclear power plant by compressing the wood, thereby controlling the impact load experienced by the container body. In this specific embodiment, the main material of the buffer 142 is balsa wood, and a portion of cedar wood is provided on the side where the shock-absorbing component 140 is connected to the cylinder 121 to further improve the shock absorption performance of the shock-absorbing component 140.

[0083] Of course, in other embodiments, the buffer 142 may also be made of materials such as honeycomb aluminum, aluminum foam, or polyurethane foam, and no specific limitation is made here.

[0084] In some embodiments, the outer side of the rigid member 141 is symmetrically equipped with lifting lugs for lifting and hoisting the shock absorber. A supporting angle steel is installed on the lower side for supporting the load when the spent fuel transport equipment 100 of the nuclear power plant is placed horizontally. The bottom surface of the shock absorber assembly 140 is provided with guide pin holes to align with the cylinder 121 during installation via a pin shaft, ensuring the installation positioning accuracy of the shock absorber assembly 140. The two shock absorber assemblies 140 are fixed to both ends of the cylinder 121 by evenly distributed bolts and nuts, and each bolt is equipped with a tightening nut and a lock nut to improve the installation strength of the shock absorber assembly 140.

[0085] Referring again to Figures 16 and 18, in some embodiments, the cover assembly 130 includes an outer cover 131, a clamping cover 132, and an inner cover 133. The outer cover 131, the clamping cover 132, and the inner cover 133 are all sequentially sealed at the opening 1212 of the outer shell assembly 120. The inner cover 133 has an inflation port 1333, and the clamping cover 132 has a corresponding through hole 1323 so that the inflation port 1333 can be exposed through the through hole 1323.

[0086] Specifically, the sealing performance of the cover assembly 130 and the cylinder 121 is improved by sequentially covering the outer cover 131, the pressing cover 132, and the inner cover 133. Meanwhile, the pressing cover 132 has a through hole 1323. During inflation and deflation operations, the interface of the inflation device can be passed through the through hole 1323 and connected to the inflation port 1333 to perform the corresponding deflation operation, improving airtightness while ensuring the stability of the inflation operation.

[0087] Referring to Figures 16 and 17, in some embodiments, the cylinder 121 has multiple steps at one end with an opening 1212, the inner cover 133 and the pressing cover 132 are respectively installed on different steps and are completely embedded in the cylinder 121, and the outer cover 131 is fastened to the end face of the cylinder 121.

[0088] For example, the open end 1212 of the cylinder 121 has three steps, referred to as an annular arrangement. The outer step surface is the open end face 1212 of the cylinder 121, and the other two step surfaces move sequentially towards the axis of the cylinder 121. Thus, during assembly, the inner cover 133 is first installed on the innermost step, then the clamping cover 132 is installed on the middle step and fitted against the inner cover 133, and finally the outer cover 131 is installed on the end face of the cylinder 121 and fitted against the clamping cover 132. Through the above assembly method, the sealing performance of the cover is strengthened, preventing leakage of spent fuel during transportation.

[0089] Referring again to Figure 18, in some embodiments, the outer cover 131 includes a first cover body 1311, outer cover screws, and an outer cover sealing ring 1312. The first cover body 1311 is fastened to the end face of the cylinder 121 by the outer cover screws. The outer cover bolt holes are countersunk holes, and after the outer cover screws are installed, the top surface of the screw head is below the top surface of the first cover body 1311, so that the end face of the outer cover 131 is flat, which facilitates the subsequent installation of the shock absorption assembly 140. A threaded hole is provided on the top surface of the first cover body 1311, so that the outer cover 131 can be lifted and disassembled during disassembly after being locked by the external bolts to the threaded hole.

[0090] In some embodiments, the bottom surface of the first cover 1311 is provided with a sealing ring groove for assembling an outer cover sealing ring 1312. The outer cover sealing ring 1312 is disposed between the outer cover 131 and the clamping cover 132 to ensure the sealing performance between the outer cover 131 and the clamping cover 132. Preferably, two outer cover sealing rings 1312 are provided, and a test hole 1313 is provided between the two outer cover sealing rings 1312. The test hole 1313 penetrates the first cover 1311 for leakage testing of the outer cover sealing ring 1312 to evaluate the sealing performance of the outer cover sealing ring 1312.

[0091] In some embodiments, the clamping cover 132 includes a second cover body 1321, clamping cover screws, and a clamping cover sealing ring 1322. The top of the second cover body 1321 also has a threaded hole for lifting operations, facilitating the assembly and disassembly of the clamping cover 132. The surface of the clamping cover bolt hole is below the top surface, and after the clamping cover screws are installed, the top surface of the screw head is below the top surface of the second cover body 1321, ensuring a flat end face for the clamping cover 132 and facilitating the subsequent installation of the outer cover 131. The second cover body 1321 has a through hole 1323 in its middle that matches the air inlet 1333 of the inner cover 133, and a sealing ring groove on its bottom surface for assembling the clamping cover sealing ring 1322. The clamping cover sealing ring 1322 is disposed between the clamping cover 132 and the inner cover 133 to ensure a tight seal between them. Preferably, two compression cap sealing rings 1322 are provided, and a test hole 1313 is provided between the two compression cap sealing rings 1322. The test hole 1313 penetrates the second cover 1321 for leakage testing of the compression cap sealing ring 1322 to evaluate the sealing performance of the compression cap sealing ring 1322.

[0092] Referring again to Figures 4 and 5, in some embodiments, the inner cover 133 includes a third cover body 1331, with a lifting boss 1332 at the center of the third cover body 1331. An inflation port 1333 is formed in the third cover body 1331, and a quick connector 1335 is provided inside the inflation port 1333. The outer cover 131 also includes a hole cover 1334, which seals and covers the inflation port 1333.

[0093] Specifically, the lifting boss 1332 is located on the top of the third cover 1331 for use in accommodating downhole loading operations. The lifting boss 1332 also has a vacuum drying hole for vacuum drying operations and a seal detection hole 1313 to ensure the sealed vacuum transport of spent fuel assemblies. The third cover 1331 is pressed and fixed to the cylinder 121 by a clamping cover 132. Two locating pins are provided on the side of the third cover 1331 to guide the inner cover 133 into accurate position during container loading and unloading operations. The top surface of the inner cover 133 has threaded holes for connecting the inner cover 133 lifting fixture, facilitating lifting during the assembly and disassembly of the inner cover 133.

[0094] The third cover 1331 has two air inlets 1333, and a cap 1334 is provided above the air inlets 1333 to seal them. A quick connector 1335 is provided below the cap 1334 for inflation and deflation operations. The cap 1334 of the air inlets 1333 is fixed to the third cover 1331 with screws. Preferably, a sealing ring is also provided below the part of the cap 1334 that contacts the third cover 1331, and a sealing test hole 1313 is provided for testing the sealing performance of the cap 1334.

[0095] In some embodiments, the bottom surface of the third cover 1331 also has a sealing ring groove for assembling the inner cover sealing ring. The inner cover sealing ring is disposed between the inner cover 133 and the cylinder 121 to ensure the sealing performance between the inner cover 133 and the cylinder 121. Preferably, two inner cover sealing rings are also provided, and a test hole 1313 is provided between the two inner cover sealing rings. The test hole 1313 penetrates the third cover 1331 for leakage testing of the inner cover sealing ring to evaluate the sealing performance of the inner cover sealing ring.

[0096] Embodiments of this application also provide a spent fuel handling system, including the spent fuel transport equipment 100 of a nuclear power plant in any of the above embodiments.

[0097] This embodiment includes the spent fuel transport equipment 100 of the nuclear power plant in any of the above embodiments. Therefore, it has all the beneficial effects of the spent fuel transport equipment 100 of the nuclear power plant in any of the above embodiments, which will not be described in detail here.

[0098] The technical features of the above embodiments can be combined in any way. For the sake of brevity, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0099] The embodiments described above are merely illustrative of several implementation methods of this application, and while the descriptions are relatively specific and detailed, they should not be construed as limiting the scope of the patent application. It should be noted that those skilled in the art can make various modifications and improvements without departing from the concept of this application, and these all fall within the protection scope of this application. Therefore, the protection scope of this patent application should be determined by the appended claims.

Claims

1. A spent fuel transport device for nuclear power plants, used for underground spent fuel loading operations, the spent fuel transport device comprising: The basket assembly has multiple storage chambers inside, which are used to store the spent fuel; The outer shell assembly has an internal receiving cavity with an open end. The basket assembly is installed in the receiving cavity. The outer shell assembly has a first material inlet on the periphery of the end with the open end and a plurality of second material inlets on the periphery of the end away from the open end. The cover assembly is sealed and installed at the opening and has an air inlet, which is connected to the first feed port and each of the second feed ports through the receiving cavity.

2. The spent fuel transport equipment for nuclear power plants according to claim 1, wherein the spent fuel transport equipment for nuclear power plants further comprises two shock-absorbing components, one of the shock-absorbing components is installed on the cover assembly, and the other shock-absorbing component is installed on the outer shell assembly at the end away from the cover assembly.

3. The spent fuel transportation equipment for nuclear power plants according to claim 2, each of the shock-absorbing components includes a buffer and a rigid component, the rigid component covering the outside of the buffer, and the rigid components of the two shock-absorbing components respectively fix the corresponding buffer to the end of the cover assembly and the outer shell assembly away from the opening.

4. The spent fuel transport equipment for nuclear power plants according to any one of claims 1-3, wherein the cover assembly includes an outer cover, a clamping cover, and an inner cover, wherein the outer cover, the clamping cover, and the inner cover are sequentially sealed at the opening of the outer shell assembly, and the inner cover has an inflation port, and the clamping cover has a corresponding through hole so that the inflation port can be exposed to the through hole.

5. The spent fuel transport equipment for nuclear power plants according to claim 4, wherein the inner cover includes a third cover body, and a lifting boss is provided in the middle of the third cover body; The inflation port is located in the third cover, and a quick connector is provided inside the inflation port. The outer cover also includes a hole cover, which seals and covers the inflation port.

6. The spent fuel transport equipment for a nuclear power plant according to any one of claims 1-5, wherein the basket assembly comprises a plurality of sleeves, each sleeve defining a square storage cavity.

7. The spent fuel transport equipment for nuclear power plants according to claim 6, wherein the casing is provided with a boron-aluminum plate and a stainless steel cladding on its periphery, and the stainless steel cladding covers the side of the boron-aluminum plate opposite to the casing.

8. The spent fuel transport equipment for nuclear power plants according to claim 6 or 7, wherein the basket assembly further comprises a top plate, a plurality of support plates, a plurality of heat transfer plates, mounting plates, a bottom plate and a threaded rod, wherein the threaded rod is connected in series with the top plate, each of the support plates, each of the heat transfer plates, the mounting plates and the bottom plate, and the support plates and the heat transfer plates are arranged at intervals.

9. The spent fuel transport equipment for nuclear power plants according to claim 8, wherein a positioning block is provided between a group of adjacent support plates and the heat transfer plate, and the positioning block is installed on the threaded rod.

10. The spent fuel transport equipment for a nuclear power plant according to claim 4 or 5, wherein the outer shell assembly includes a cylinder, a support ring, and a lifting trunnion, wherein the end of the cylinder away from the opening is provided with a second feed port, the support ring is fitted onto the end of the cylinder with the opening and has the first feed port, and the lifting trunnion is installed on the periphery of the support ring.

11. The spent fuel transport equipment for a nuclear power plant according to claim 10, wherein the outer shell assembly further comprises a shielding layer, a plurality of heat sinks and a protective shell, the protective shell being sleeved on the outside of the cylinder and defining a cavity between the protective shell and the cylinder, each of the heat sinks being circumferentially disposed within the cavity and dividing the cavity into a plurality of filling cavities, and the shielding layer being cast into the filling cavity.

12. The spent fuel transport equipment for nuclear power plants according to claim 11, wherein a safety valve is provided at the end of the cylinder away from the opening, and the safety valve is in communication with the cavity.

13. The spent fuel transport equipment for nuclear power plants according to any one of claims 10-12, wherein a tilting block is provided on one side of the cylinder, and the tilting block has a groove for tilting and bearing force.

14. The spent fuel transport equipment for a nuclear power plant according to any one of claims 10-13, wherein the cylinder has a plurality of steps at one end with the opening, the inner cover and the clamping cover are respectively installed on different steps and are completely embedded in the cylinder, and the outer cover is fastened to the end face of the cylinder.

15. A spent fuel handling system, comprising the spent fuel transport equipment of a nuclear power plant as claimed in any one of claims 1 to 14.

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