Spent fuel transportation equipment for nuclear power station and spent fuel treatment system
By designing spent fuel transportation equipment in nuclear power plants, using the combination of hanging basket assembly, shell assembly and cover assembly, the spent fuel transportation problem in downhole loading operations is solved, and the safe and stable transportation and drying of spent fuel are achieved, meeting the safety requirements of nuclear power plants.
Patent Information
- Application Number
- CN202510347499.1
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-03-24
- Publication Date
- 2025-07-11
AI Technical Summary
The lack of spent fuel transport containers that can be used for downhole loading operations makes it difficult to ensure the safe and stable operation of nuclear power and achieve the goal of spent fuel off-load storage.
A spent fuel transportation equipment for nuclear power plants is designed, including a hanging basket assembly, a shell assembly and a cover body assembly. The hanging basket assembly is installed in the shell assembly, and material openings are provided at both ends of the shell assembly. The cover assembly is sealed and installed and equipped with an inflatable port. Water injection and exhaust gas are inflated and inflatable through the material opening, and the inflatable port is inflated to realize the underground loading and dry transportation of spent fuel.
It realizes underground loading and drying transportation of spent fuel, ensures the safe and stable operation of nuclear power plants, and meets functional requirements such as sealing and inclusion, radiation shielding and waste heat export.
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Figure CN120299767A_ABST
Abstract
Description
Technical Field
[0001] The present application relates to the technical field of spent fuel processing, and particularly to a spent fuel transportation device for a nuclear power plant and a spent fuel processing system. Background Art
[0002] Spent fuel, also known as irradiated nuclear fuel, is nuclear fuel that has been irradiated and used, usually produced by the nuclear reactor of a nuclear power plant. The nuclear fuel undergoes a nuclear reaction when bombarded by neutrons in the reactor and is unloaded from the reactor after a certain period of time. The uranium content of this fuel decreases and it can no longer sustain a nuclear reaction, so it is called spent fuel. Spent nuclear fuel contains a large amount of radioactive elements and thus has radioactivity. If not properly processed, it will seriously affect the environment and the health of people who come into contact with it.
[0003] The spent fuel transportation container is an indispensable safety transportation guarantee device in the fuel reprocessing process. The spent fuel transportation container needs to meet functions such as sealed containment, radiation shielding, critical safety, and waste heat removal. For high burn-up fuel assemblies with a certain burn-up depth, higher technical requirements are imposed on the realization of safety functions. Currently, there is a lack of a spent fuel transportation container that can be used for downhole loading operations, making it difficult to ensure the safe and stable operation of nuclear power and achieve the goal of off-reactor storage of spent fuel. Summary of the Invention
[0004] Based on this, in view of the problem of the lack of a spent fuel transportation container that can be used for downhole loading operations, it is necessary to provide a spent fuel transportation device for a nuclear power plant and a spent fuel processing system.
[0005] To achieve the above object, the technical solution adopted in the present application is as follows:
[0006] In a first aspect, an embodiment of the present application provides a spent fuel transportation device for a nuclear power plant, which is used for downhole spent fuel loading operations. The spent fuel transportation device for a nuclear power plant includes:
[0007] A hanging basket assembly, which is internally provided with a plurality of storage cavities for storing the spent fuel;
[0008] An outer shell assembly, which is internally provided with a receiving cavity with an open end. The hanging basket assembly is installed in the receiving cavity. A first material port is provided on the circumferential side of the outer shell assembly at the end with the open end, and a plurality of second material ports are provided on the circumferential side of the end far from the open end;
[0009] A cover body assembly, which is hermetically installed at the open end and is provided with an inflation port. The inflation port is communicated with the first material port and each of the second material ports through the receiving cavity.
[0010] In one embodiment of the first aspect, the spent nuclear fuel transportation equipment of the nuclear power plant further includes two shock absorption components, and one of the shock absorption components is installed on the cover body component, and the other shock absorption component is installed at one end of the outer shell component away from the cover body component.
[0011] In one embodiment of the first aspect, each of the shock absorption components includes a buffer member and a rigid member. The rigid member is coated on the outside of the buffer member, and the rigid members of the two shock absorption components respectively fix the corresponding buffer members to one end of the cover body component and the outer shell component away from the open end.
[0012] In one embodiment of the first aspect, the cover body component includes an outer cover, a pressing cover, and an inner cover. The outer cover, the pressing cover, and the inner cover are all sequentially sealed at the open end of the outer shell component, and the inner cover is provided with an inflation port, and the pressing cover is correspondingly provided with a through hole so that the inflation port can be exposed to the through hole.
[0013] In one embodiment of the first aspect, the inner cover includes a third cover body, and a lifting boss is provided in the middle of the third cover body;
[0014] The inflation port is opened on the third cover body, a quick connector is provided in the inflation port, and the outer cover further includes a hole cover, and the hole cover is hermetically covered on the inflation port.
[0015] In one embodiment of the first aspect, the hanging basket component includes a plurality of sleeves, and a square storage cavity is defined in each of the sleeves.
[0016] In one embodiment of the first aspect, boron-aluminum plates and stainless steel claddings are provided on the circumferential side of the sleeve, and the stainless steel cladding is coated on the side of the boron-aluminum plate away from the sleeve.
[0017] In one embodiment of the first aspect, the hanging basket component further includes a top plate, a plurality of support plates, a plurality of heat transfer plates, a mounting plate member, a bottom plate, and a threaded rod. The threaded rod sequentially connects in series the top plate, each of the support plates, each of the heat transfer plates, the mounting plate member, and the bottom plate, and the support plates and the heat transfer plates are arranged at intervals.
[0018] 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 installed on the threaded rod.
[0019] In one embodiment of the first aspect, the housing assembly includes a cylinder body, a support ring, and lifting trunnions. A second material port is provided at one end of the cylinder body away from the open end. The support ring is sleeved on the open - end of the cylinder body and is provided with the first material port. The lifting trunnions are installed on the circumferential side of the support ring.
[0020] 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 sleeved on the outer side of the cylinder body and defines a cavity between it and the cylinder body. Each heat sink is circumferentially arranged in the cavity and divides the cavity into a plurality of filling cavities. The shielding layer is poured into the filling cavities.
[0021] In one embodiment of the first aspect, a safety valve is provided at one end of the cylinder body away from the open end, and the safety valve is communicated with the cavity.
[0022] In one embodiment of the first aspect, a turning block is provided on one side of the cylinder body, and the turning block is provided with a groove for turning force.
[0023] In one embodiment of the first aspect, a plurality of steps are provided at the open - end of the cylinder body. The inner cover and the pressing cover are respectively installed on different steps and are completely embedded in the cylinder body, and the outer cover is fastened to the end face of the cylinder body.
[0024] In a second aspect, an embodiment of the present application further provides a spent fuel treatment system, including the nuclear power plant spent fuel transportation equipment in any of the above - mentioned embodiments.
[0025] Compared with the related art, the beneficial effects of the present application are as follows: The present application provides a nuclear power plant spent fuel transportation equipment and a spent fuel treatment system for underground spent fuel loading operations. The nuclear power plant spent fuel transportation equipment includes a hanging basket assembly, a housing assembly, and a cover assembly. Among them, the hanging basket assembly is installed in the housing assembly and is provided with a plurality of storage cavities for storing spent fuel. The circumferential sides of both ends of the housing assembly are respectively provided with a first material port and a plurality of second material ports. The cover assembly is sealed and installed at the open end of the housing assembly and is provided with an inflation port. In this way, when performing underground loading, first, water is injected into the nuclear power plant spent fuel transportation equipment through the first material port and the second material port to discharge the internal gas of the container, eliminate the internal negative pressure state, and facilitate the opening of the cover assembly. Then, the cover assembly is opened, and spent fuel is loaded from the open side. After the loading is completed, the cover assembly is sealed, and gas is inflated into the container through the inflation port to discharge the liquid from the second material port, facilitating subsequent water - free transportation operations and realizing underground spent fuel loading operations. BRIEF DESCRIPTION OF THE DRAWINGS
[0026] To more clearly illustrate the technical solutions in the embodiments of the present application or the prior art, the following will briefly introduce the drawings required for the description of the embodiments or the prior art. Obviously, the drawings in the following description are only some embodiments of the present application. For those of ordinary skill in the art, without creative efforts, other drawings can also be obtained based on these drawings.
[0027] Figure 1 Structural schematic diagram of spent fuel transportation equipment in some embodiments of the present application;
[0028] Figure 2 Structural schematic of the hanging basket assembly in some embodiments of the present application Figure 1 ;
[0029] Figure 3 Structural schematic diagram of the outer shell assembly in some embodiments of the present application;
[0030] Figure 4 External appearance structural schematic diagram of the inner cover in some embodiments of the present application;
[0031] Figure 5 Cross-sectional structural schematic diagram of the inner cover in some embodiments of the present application;
[0032] Figure 6 Structural schematic diagram of the sleeve in some embodiments of the present application;
[0033] Figure 7 For Figure 6 Enlarged structural schematic diagram of part A in
[0034] Figure 8 Structural schematic of the hanging basket assembly in some embodiments of the present application Figure 2 ;
[0035] Figure 9 For Figure 8 Enlarged structural schematic diagram of part B in
[0036] Figure 10 Structural schematic of the shielding layer in some embodiments of the present application Figure 1 ;
[0037] Figure 11 Structural schematic diagram of the bottom of the cylinder in some embodiments of the present application;
[0038] Figure 12 For Figure 11 Enlarged structural schematic diagram of part C in
[0039] Figure 13 Structural schematic of the shielding layer in some embodiments of the present application Figure 2 ;
[0040] Figure 14 Structural schematic diagram of a heat dissipation pipe in some embodiments of the present application;
[0041] Figure 15 Structural schematic diagram of a shock absorption component in some embodiments of the present application;
[0042] Figure 16 Structural schematic diagram of an outer cover in some embodiments of the present application;
[0043] Figure 17 Structural schematic diagram of a pressing cover in some embodiments of the present application;
[0044] Figure 18 is Figure 16 Enlarged structural schematic diagram of part D in
[0045] Explanation of reference numerals:
[0046] 100, Nuclear power plant spent fuel transportation equipment; 110, Basket assembly; 111, Storage cavity; 112, Sleeve; 113, Top plate; 114, Support plate; 115, Mounting plate member; 1151, Sleeve 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 body; 1211, Accommodation cavity; 1212, Open end; 1213, First material port; 1214, Second material port; 122, Support ring; 123, Lifting trunnion; 124, Protective shell; 125, Heat dissipation pipe; 126, Heat dissipation fin; 127, Shielding layer; 128, Safety valve; 129, Flipping block; 130, Cover body assembly; 131, Outer cover; 1311, First cover body; 1312, Outer cover sealing ring; 1313, Detection hole; 132, Pressing cover; 1321, Second cover body; 1322, Pressing cover sealing ring; 1323, Through hole; 133, Inner cover; 1331, Third cover body; 1332, Lifting boss; 1333, Inflation port; 1334, Hole cover; 1335, Quick connector; 140, Shock absorption component; 141, Rigid member; 142, Buffer member. Detailed implementation manners
[0047] To make the above objects, features, and advantages of the present application more apparent and understandable, the following will describe the detailed implementation manners of the present application in conjunction with the accompanying drawings. Many specific details are set forth in the following description in order to fully understand the present application. However, the present application can be implemented in many other ways different from those described herein, and those skilled in the art can make similar improvements without departing from the connotation of the present application. Therefore, the present application is not limited by the specific embodiments disclosed below.
[0048] In the description of the present application, it should be understood that if terms such as "center", "longitudinal", "transverse", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential", etc. appear, the orientation or positional relationship indicated by these terms is based on the orientation or positional relationship shown in the drawings. It is only for the convenience of describing the present application and simplifying the description, rather than indicating or implying that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and thus should not be construed as a limitation to the present application.
[0049] In addition, if the term "and / or" appears, "and / or" is merely an associative relationship describing associated objects, indicating that three relationships can exist. For example, A and / or B can represent three situations: A exists alone, A and B exist simultaneously, and B exists alone. Additionally, the character " / " in this text generally indicates that the associated objects before and after are in an "or" relationship. If terms such as "first" and "second" appear, these terms are only for descriptive purposes and cannot be construed as indicating or implying relative importance or implicitly specifying the quantity of the indicated technical features. Thus, features defined with "first" and "second" can explicitly or implicitly include at least one such feature. In the description of the present application, if the term "plurality" appears, the meaning of "plurality" is at least two, such as two, three, etc., unless otherwise specifically and clearly defined.
[0050] In the present application, unless otherwise clearly specified and limited, if terms such as "install", "connect", "couple", "fix", etc. appear, these terms should be understood in a broad sense. For example, it can be a fixed connection, a detachable connection, or integrated; it can be a mechanical connection or an electrical connection; it can be directly connected or indirectly connected through an intermediate medium, and it can be the communication inside two elements or the interaction relationship between two elements, unless otherwise clearly limited. For those of ordinary skill in the art, the specific meanings of the above terms in the present application can be understood according to specific circumstances.
[0051] In the present application, unless otherwise clearly specified and limited, if a description such as the first feature being "on" or "under" the second feature appears, its meaning can be that the first and second features are in direct contact, or the first and second features are in indirect contact through an intermediate medium. Moreover, the first feature being "above", "over", and "on top of" the second feature can mean that the first feature is directly above or obliquely above the second feature, or merely indicates that the first feature has a higher horizontal height than the second feature. The first feature being "under", "beneath", and "underneath" the second feature can be that the first feature is directly below or obliquely below the second feature, or merely indicates that the first feature has a lower horizontal height than the second feature.
[0052] It should be noted that if an element is referred to as "fixed to" or "disposed on" another element, it can be directly on the other element or there may also be an intermediate 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 intermediate element at the same time. If present, the terms "vertical", "horizontal", "upper", "lower", "left", "right" and similar expressions used in this application are only for illustrative purposes and do not represent the only implementation.
[0053] Referring to Figure 1 As shown, an embodiment of the present application provides a nuclear power plant spent fuel transportation device 100 for underground spent fuel loading operations. Specifically, the nuclear power plant spent fuel transportation device 100 includes a hanging basket assembly 110, a housing assembly 120 and a cover assembly 130. The hanging basket assembly 110 is used to load the spent fuel assembly and is installed inside the housing assembly 120. The cover assembly 130 can be hermetically sealed with the housing assembly 120 to facilitate the sealed transportation of the spent fuel.
[0054] Continuing to refer to Figure 2 and Figure 3 As shown, exemplarily, a plurality of storage cavities 111 are provided inside the hanging basket assembly 110, and the storage cavities 111 are used to store the spent fuel. An accommodation cavity 1211 with an open end 1212 is provided inside the housing assembly 120, and the hanging basket assembly 110 is installed inside the accommodation cavity 1211. And a first material port 1213 is provided on the peripheral side of the end of the housing assembly 120 with the open end 1212, and a plurality of second material ports 1214 are provided on the peripheral side of the end far from the open end 1212. Continuing to refer to Figure 4 and Figure 5 As shown, the cover assembly 130 is hermetically installed at the open end 1212 and is provided with an inflation port 1333. The inflation port 1333 is communicated with the first material port 1213 and each of the second material ports 1214 through the accommodation cavity 1211.
[0055] In a specific embodiment of the present application, the assembled spent nuclear fuel transportation device 100 is vertically hoisted into the reactor shaft, and the spent fuel assemblies are loaded underground. Since the cover assembly 130 is hermetically assembled with the outer shell assembly 120, there is inevitably some air inside it, resulting in a negative pressure state inside the container, making it difficult to open the cover assembly 130. Thus, when opening the cover, first open the first material port 1213 and the second material port 1214, and fill water into the container through the first material port 1213 and the second material port 1214 to discharge the gas inside the container, relieve the internal negative pressure state, and facilitate the disassembly of the cover assembly 130. Then, after the cover assembly 130 is removed, the spent fuel assemblies are placed in the storage cavities 111 of the hanging basket assembly 110 through a loading device. After each storage cavity 111 is loaded, the cover assembly 130 is closed and sealed. Finally, open the second material port 1214, and convey gas into the container through the air inlet 1333 to discharge the internal liquid from the second material port 1214 to ensure the dry transportation of the spent nuclear fuel transportation device 100 by the transportation device.
[0056] Continue to refer to Figure 6 As shown, in some embodiments, the hanging basket assembly 110 includes a plurality of sleeves 112, and a square storage cavity 111 is defined inside each sleeve 112.
[0057] Specifically, through the arrangement of the plurality of sleeves 112, each sleeve 112 forms a separate storage cavity 111, which is convenient for the disassembly and assembly of the hanging basket assembly 110, improves the assembly efficiency, and is also convenient for the loading of the spent fuel assemblies. It can be understood that the spent fuel assemblies are in the shape of a square prism, the sleeves 112 are correspondingly square tube structures, and a storage cavity 111 adapted to the size of the spent fuel assemblies is formed inside.
[0058] Continue to refer to Figure 7 As shown, further, boron-aluminum plates 119 and stainless steel claddings 1110 are provided on the peripheral side of the sleeve 112, and the stainless steel cladding 1110 covers the side of the boron-aluminum plate 119 facing away from the sleeve 112.
[0059] Specifically, boron-aluminum plates 119 are provided on all four sides of the sleeve 112 to control the spent fuel assemblies to be in a subcritical state. The stainless steel cladding 1110 covers the outside of the boron-aluminum plate 119 to fix the boron-aluminum plate 119 and maintain the stable operation of the sleeve 112.
[0060] Continue to refer to Figure 8 As shown, in some embodiments, the hanging basket assembly 110 further includes a top plate 113, a plurality of support plates 114, a plurality of heat transfer plates 118, a mounting plate member 115, a bottom plate 116, and a threaded rod 117. The threaded rod 117 sequentially connects in series the top plate 113, each support plate 114, each heat transfer plate 118, the mounting plate member 115, and the bottom plate 116, and the support plates 114 and the heat transfer plates 118 are arranged at intervals.
[0061] Specifically, the top plate 113, the support plate 114, the heat transfer plate 118, the mounting plate member 115, and the bottom plate 116 are all circular plate member structures and are coaxially arranged. The above-mentioned plate members are respectively provided with direction through holes to facilitate the sequential insertion and assembly of the sleeve 112, thereby restricting the axial and radial displacements of the sleeve 112 within the hanging basket assembly 110. Preferably, the end of the sleeve 112 is provided with a flange surface, which abuts against the top plate 113 after assembly and is fixed by bolts to further enhance the installation strength of the sleeve 112.
[0062] Furthermore, the mounting plate member 115 includes a sleeve mounting plate 1151 and a fuel assembly mounting plate 1152. The sleeve mounting plate 1151 is located on the side of the fuel assembly mounting plate 1152 away from the bottom 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 can be understood that the tail end in this embodiment refers to the end of the object closer to the bottom plate 116.
[0063] Continue to refer to Figure 9 As shown, still further, 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.
[0064] Specifically, the support plate 114 can provide support for the sleeve 112 and the threaded rod 117 to form a complete framework after the threaded rod 117 is connected and passed through. The heat transfer plate 118 can dissipate heat from the spent fuel assembly loaded in the sleeve 112 and maintain a distance from the support plate 114 through the support of the positioning block 1111 to avoid the heat-induced deformation of the support plate 114 and ensure the heat dissipation efficiency of the heat transfer plate 118. Exemplarily, the positioning block 1111 has a square stepped structure to facilitate the assembly of the sleeve 112 and maintain the support stability of the support plate 114 and the heat transfer plate 118.
[0065] Refer to again Figure 3 As shown, in some embodiments, the outer shell assembly 120 includes a cylinder body 121, a support ring 122, and a lifting trunnion 123. A second material opening 1214 is provided at one end of the cylinder body 121 away from the opening 1212. The support ring 122 is sleeved on the end of the cylinder body 121 provided with the opening 1212 and is provided with a first material opening 1213. The lifting trunnion 123 is mounted on the circumferential side of the support ring 122.
[0066] Specifically, the cylinder body 121 is the installation carrier of the hanging basket assembly 110. It is a stainless-steel cylinder body 121, with one end open and one end closed, for installing the hanging basket assembly 110 and loading the spent fuel assembly from the open end 1212. The support ring 122 is sleeved on the open end 1212 of the cylinder body 121 and fixed to the cylinder body 121 by bolts. Of course, in some other embodiments, the support ring 122 and the cylinder body 121 can also be fixed by welding, and specific limitations are not made here. Through the arrangement of the support ring 122, the force support during the loading process of the container is provided, and it is adapted to the positioning device and the loading device, facilitating the fixation of the nuclear power plant spent fuel transportation equipment 100.
[0067] Exemplarily, threaded holes are provided on the top surface of the support ring 122 to facilitate the installation of the locator and the shock absorber during the downhole loading process. Two square holes are symmetrically provided on the circumferential side of the support ring 122 to match the lifting trunnions 123. The lifting trunnions 123 are fixed to the groove of the cylinder body 121 by bolts and then pass through the square holes of the support ring 122 and protrude. Each lifting trunnion 123 is in the same plane and is arranged at intervals along the circumferential direction of the cylinder body 121 for the lifting operation of the nuclear power plant spent fuel transportation equipment 100. During the downhole loading process, the trunnions are matched with the trunnion positioning device for positioning operation.
[0068] Further, threaded holes are also provided on the end face of the closed end of the cylinder body 121 for installing the shock absorber. A first feed port 1213 is provided on the side surface of the top end of the cylinder body 121, and a second feed port 1214 is provided on the side surface of the bottom end, which is matched with the downhole loading inflatable drainage valve for inflatable drainage or water filling and air exhaust operations.
[0069] It should be noted that to ensure the sealed transportation of the spent fuel assembly and avoid leakage. Covers are provided at each hole position and feed port of the cylinder body 121. And it is sealed with lead plugs, rotary plugs, and rubber O-ring seals, and at the same time, a seal detection hole is provided for seal performance detection.
[0070] Still further, a turning block 129 is provided on one side of the cylinder body 121, and the turning block 129 is provided with a groove for turning force.
[0071] Specifically, the turning block 129 is arranged at the bottom of the cylinder body 121 and welded to the cylinder body 121 for the turning operation of the container. The center line of the turning block 129 is parallel to the axis of the cylinder body 121 and is at a certain distance from the center line of the container. The groove of the turning block 129 is adapted to the turning equipment to facilitate the turning force of the nuclear power plant spent fuel transportation equipment 100.
[0072] Continue to refer to Figure 10As shown, further, the outer shell 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 outside the cylinder body 121 and defines a cavity with the cylinder body 121. Each heat sink 126 is circumferentially arranged in the cavity and divides the cavity into a plurality of filling cavities, and the shielding layer 127 is poured into the filling cavities.
[0073] Specifically, the protective shell 124 is coaxially arranged with the cylinder body 121, and encloses a cavity with the cylinder body 121, the top plate 113, and the bottom plate 116. The shielding layer 127 can be made of materials such as beryllium, graphite, and uranium 238. By pouring the above materials into the cavity, the shielding layer 127 is formed. Both sides of the heat sink 126 are connected to the inner wall of the protective shell 124 and the outer wall of the cylinder body 121 respectively, and are evenly distributed along the axis of the cylinder body 121 to evenly partition the shielding layer 127 material in the filling cavities. Through the uniform arrangement of the heat sinks 126, it is convenient for heat dissipation inside the nuclear power plant spent fuel transportation device 100 and improves the heat dissipation rate of the residual heat of the nuclear power plant spent fuel transportation device 100.
[0074] Continue to refer to Figure 11 and Figure 12 As shown, further, one end of the cylinder body 121 away from the opening 1212 is provided with a safety valve 128, and the safety valve 128 is communicated with the cavity. The safety valve 128 is arranged on the closed end face of the cylinder body 121 to regulate the pressure in the cavity through the safety valve 128 and ensure the safety of the nuclear power plant spent fuel transportation device 100.
[0075] Continue to refer to Figure 13 and Figure 14 As shown, in some other embodiments, the heat sink 126 in the above embodiment is replaced by a modular designed heat dissipation pipe 125. The heat dissipation pipe 125 is internally provided with a filling cavity and is circumferentially distributed outside the cylinder body 121. The protective layer simultaneously covers the outside of each heat dissipation pipe 125, and the shielding material is poured into the cavity of the heat dissipation pipe 125.
[0076] Continue to refer to Figure 15 As shown, in some embodiments, the nuclear power plant spent fuel transportation device 100 further includes two shock absorption components 140, and one shock absorption component 140 is installed on the cover body component 130, and the other shock absorption component 140 is installed at one end of the outer shell assembly 120 away from the cover body component 130.
[0077] Specifically, the cover assembly 130 is installed on the open side 1212 of the cylinder 121, one shock absorbing assembly 140 is installed on the cover assembly 130 by bolts, and the other shock absorbing assembly 140 is installed on the closed end of the cylinder 121 by bolts. Through the arrangement of the two shock absorbing assemblies 140, during transportation, the nuclear power plant spent fuel transportation equipment 100 is placed horizontally, the outer diameter of the shock absorbing assembly 140 is larger than the outer diameter of the cylinder 121, and is coaxially arranged with the cylinder 121, so that when placed horizontally, the two symmetrically arranged shock absorbing assemblies 140 are stress points, and the vibration during transportation is reduced, thereby ensuring the stable transportation of spent fuel.
[0078] Furthermore, each shock absorbing assembly 140 includes a buffer member 142 and a rigid member 141, and the rigid member 141 is coated on the outside of the buffer member 142. The rigid members 141 of the two shock absorbing assemblies 140 respectively fix the corresponding buffer members 142 to the cover assembly 130 and the end of the outer shell assembly 120 away from the opening 1212.
[0079] Specifically, the buffer 142 can absorb vibrations during transportation to ensure stable transportation of spent fuel. The rigid member 141 can be composed of a stainless steel plate, which is coated on the outside of the buffer 142 to be connected to the cylinder 121 and fix the buffer 142.
[0080] For example, the buffer 142 can be made of wood, so as to absorb the impact energy generated by the fall of the spent fuel transport equipment 100 of 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 part of fir wood is provided on the side where the shock absorbing assembly 140 is connected to the cylinder 121, so as to further improve the shock absorbing performance of the shock absorbing assembly 140.
[0081] Of course, in other embodiments, the buffer member 142 may also be made of honeycomb aluminum, foam aluminum, polyurethane foam, and other materials, which are not specifically limited here.
[0082] Furthermore, the outer side of the rigid part 141 is symmetrically provided with lifting ears for lifting and hoisting the shock absorber. The lower side is provided with a supporting angle steel for supporting the force when the spent fuel transportation equipment 100 of the nuclear power plant is placed horizontally. The bottom surface of the shock absorbing assembly 140 is provided with a guide pin hole to align with the cylinder 121 during the installation process through the pin shaft to ensure the installation and positioning accuracy of the shock absorbing assembly 140. The two shock absorbing assemblies 140 are fixed at both ends of the cylinder 121 by evenly distributed bolts and nuts, and each bolt is equipped with a tightening nut and a locking nut to improve the installation strength of the shock absorbing assembly 140.
[0083] Continue reading Figure 16 and Figure 18As shown, in some embodiments, the cover assembly 130 includes an outer cover 131, a pressing cover 132, and an inner cover 133. The outer cover 131, the pressing cover 132, and the inner cover 133 are sequentially sealed at the opening 1212 of the housing assembly 120, and the inner cover 133 is provided with an inflation port 1333. The pressing cover 132 is correspondingly provided with a through hole 1323 so that the inflation port 1333 can be exposed to the through hole 1323.
[0084] Specifically, through the sequential covering of multiple layers of covers of the outer cover 131, the pressing cover 132, and the inner cover 133, the connection sealing performance between the cover assembly 130 and the cylinder 121 is improved. At the same time, the pressing cover 132 is provided with a through hole 1323. When performing inflation and drainage operations, the interface of the inflation device can pass through the through hole 1323 and be connected to the inflation port 1333 to perform corresponding drainage operations, improving airtightness and ensuring the stability of the inflation operation.
[0085] Continue to refer to Figure 16 and Figure 17 As shown, in some embodiments, one end of the cylinder 121 provided with the opening 1212 is provided with a plurality of steps. 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.
[0086] Exemplarily, the open end 1212 of the cylinder 121 is provided with three steps and is arranged in a ring shape. The outer step surface is the end face of the opening 1212 of the cylinder 121, and the other two step surfaces gradually approach the axis of the cylinder 121 in sequence. Thus, during the assembly process, first install the inner cover 133 on the innermost step, then install the pressing cover 132 on the middle step and fit it with the inner cover 133, and finally install the outer cover 131 on the end face of the cylinder 121 and fit it with the pressing cover 132. Through the above assembly method, the sealing performance of the cover is stronger, preventing the leakage of spent fuel during transportation.
[0087] Continue to refer to Figure 18 As shown, 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 through the outer cover screws. The outer cover bolt holes are counterbored holes. 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, facilitating the installation of the subsequent shock absorption assembly 140. Threaded holes are provided on the top surface of the first cover body 1311 so that during the disassembly process, after being locked by an external bolt and the threaded hole, the outer cover 131 can be lifted and disassembled.
[0088] Further, a sealing ring groove is provided on the bottom surface of the first cover body 1311 for assembling the outer cover sealing ring 1312. The outer cover sealing ring 1312 is arranged between the outer cover 131 and the pressing cover 132 to ensure the sealing performance between the outer cover 131 and the pressing cover 132. Preferably, two outer cover sealing rings 1312 are provided, and a detection hole 1313 is arranged between the two outer cover sealing rings 1312. The detection hole 1313 penetrates through the first cover body 1311 for the leakage test of the outer cover sealing ring 1312 to evaluate the sealing performance of the outer cover sealing ring 1312.
[0089] In some embodiments, the pressing cover 132 includes a second cover body 1321, pressing cover screws, and a pressing cover sealing ring 1322. A threaded hole is also provided on the top of the second cover body 1321 for hoisting operation to facilitate the disassembly and assembly of the pressing cover 132. The surface of the pressing cover bolt hole is below the top surface. After the pressing cover screws are installed, the top surface of the screw head is below the top surface of the second cover body 1321 to make the end surface of the pressing cover 132 flat and facilitate the subsequent installation of the outer cover 131. A through hole 1323 matching the inflation port 1333 of the inner cover 133 is provided in the middle of the second cover body 1321, and a sealing ring groove is provided on the bottom surface for assembling the pressing cover sealing ring 1322. The pressing cover sealing ring 1322 is arranged between the pressing cover 132 and the inner cover 133 to ensure the sealing performance between the pressing cover 132 and the inner cover 133. Preferably, two pressing cover sealing rings 1322 are also provided, and a detection hole 1313 is arranged between the two pressing cover sealing rings 1322. The detection hole 1313 penetrates through the second cover body 1321 for the leakage test of the pressing cover sealing ring 1322 to evaluate the sealing performance of the pressing cover sealing ring 1322.
[0090] Refer again to Figure 4 and Figure 5 As shown, in some embodiments, the inner cover 133 includes a third cover body 1331, and a lifting boss 1332 is provided in the middle of the third cover body 1331. The inflation port 1333 is opened on the third cover body 1331, and a quick connector 1335 is arranged in the inflation port 1333. The outer cover 131 further includes a hole cover 1334 which hermetically covers the inflation port 1333.
[0091] Specifically, the lifting boss 1332 is arranged on the top of the third cover body 1331 for matching the underground loading operation. A vacuum drying hole is also provided on the lifting boss 1332 for vacuum drying operation, and a sealing detection hole 1313 is provided to ensure the sealed vacuum transportation of the spent fuel assembly. The third cover body 1331 is fixedly pressed on the cylinder body 121 by the pressing cover 132. Two positioning pins are arranged on the side of the third cover body 1331 to guide the inner cover 133 to be accurately positioned during the container loading and unloading operations. A threaded hole is provided on the top surface of the inner cover 133 for connecting the inner cover 133 lifting tooling to facilitate the lifting during the disassembly and assembly of the inner cover 133.
[0092] There are two inflation ports 1333 provided on the third cover body 1331, and a hole cover 1334 is provided above the inflation port 1333 for sealing the inflation port 1333. A quick connector 1335 is provided below the hole cover 1334, which can be used for inflation and drainage operations. The hole cover 1334 of the inflation port 1333 is fixed to the third cover body 1331 by screws of the hole cover 1334. Preferably, a sealing ring is also provided below the part where the hole cover 1334 contacts the third cover body 1331, and a sealing detection hole 1313 is provided to detect the sealing performance of the hole cover 1334.
[0093] Furthermore, a sealing ring groove is also opened on the bottom surface of the third cover body 1331 for assembling the inner cover sealing ring. The inner cover sealing ring is arranged between the inner cover 133 and the cylinder body 121 to ensure the sealing performance between the inner cover 133 and the cylinder body 121. Preferably, there are also two inner cover sealing rings, and a detection hole 1313 is arranged between the two inner cover sealing rings. The detection hole 1313 penetrates through the third cover body 1331 for the leakage test of the inner cover sealing ring to evaluate the sealing performance of the inner cover sealing ring.
[0094] The embodiment of the present application also provides a spent fuel treatment system, including the nuclear power plant spent fuel transportation device 100 in any one of the above embodiments.
[0095] In this embodiment, there is the nuclear power plant spent fuel transportation device 100 in any one of the above embodiments. Therefore, it has all the beneficial effects of the nuclear power plant spent fuel transportation device 100 in any one of the above embodiments, which will not be elaborated here one by one.
[0096] The technical features of the above embodiments can be combined arbitrarily. For the sake of concise description, 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, it should be considered as the scope recorded in this specification.
[0097] The above embodiments only express several implementation manners of the present application, and the description is relatively specific and detailed, but it cannot be understood as a limitation on the scope of the patent application. It should be noted that for those of ordinary skill in the art, without departing from the concept of the present application, several deformations and improvements can still be made, and these all belong to the protection scope of the present application. Therefore, the protection scope of the patent of the present application should be subject to the appended claims.
Claims
1. A spent fuel transportation device for a nuclear power plant, characterized in that, Used for underground spent fuel loading operations, the nuclear power plant spent fuel transportation equipment includes: A hanging basket assembly, wherein a plurality of storage cavities are provided inside the hanging basket assembly, and the storage cavities are used to store the spent fuel; The outer shell component has an accommodating cavity with an opening at one end, the hanging basket component is installed in the accommodating cavity, the outer shell component has a first material opening on the peripheral side of the end with the opening, and a plurality of second material openings on the peripheral side of the end away from the opening; A cover assembly is sealed and mounted on the opening and is provided with an inflation port, wherein the inflation port is communicated with the first material port and each of the second material ports through the accommodating cavity.
2. The spent fuel transportation equipment for nuclear power plants according to claim 1, characterized in that The spent fuel transportation equipment for a nuclear power plant further comprises two shock absorbing components, one of which is installed on the cover component, and the other is installed on an end of the outer shell component away from the cover component.
3. The spent fuel transportation equipment for nuclear power plants according to claim 2, characterized in that, Each of the shock absorbing assemblies comprises a buffer and a rigid member, wherein the rigid member is coated on the outside of the buffer, and the rigid members of the two shock absorbing assemblies respectively fix the corresponding buffer to the cover assembly and the end of the outer shell assembly away from the opening.
4. The spent fuel transportation equipment for nuclear power plants according to claim 1, characterized in that The cover body assembly includes an outer cover, a compression cover and an inner cover, wherein the outer cover, the compression cover and the inner cover are sealed in the open portion of the outer shell assembly in sequence, and the inner cover is provided with an inflation port, and the compression cover is correspondingly provided with a through hole so that the inflation port can be exposed to the through hole.
5. The spent fuel transportation equipment for nuclear power plants according to claim 4, characterized in that, The inner cover comprises a third cover body, and a lifting boss is provided in the middle of the third cover body; The inflation port is opened in the third cover body, a quick connector is arranged in the inflation port, and the outer cover further comprises a hole cover, and the hole cover is sealed and covers the inflation port.
6. The spent fuel transportation equipment for nuclear power plants according to claim 1, characterized in that, The hanging basket assembly includes a plurality of sleeves, each of which defines a square storage cavity.
7. The spent fuel transportation equipment for nuclear power plants according to claim 6, characterized in that, A boron aluminum plate and a stainless steel cladding are provided on the peripheral side of the sleeve, and the stainless steel cladding is coated on the side of the boron aluminum plate away from the sleeve.
8. The spent fuel transportation equipment for nuclear power plants according to claim 6, characterized in that, The hanging basket assembly also includes a top plate, a plurality of support plates, a plurality of heat transfer plates, a mounting plate, a bottom plate and a threaded rod, wherein the threaded rod is sequentially connected in series with the top plate, each of the support plates, each of the heat transfer plates, the mounting plate and the bottom plate, and the support plates are spaced apart from the heat transfer plates.
9. The spent fuel transportation equipment for nuclear power plants according to claim 8, characterized in that, A positioning block is provided between a group of adjacent supporting plates and the heat transfer plate, and the positioning block is installed on the threaded rod.
10. The spent fuel transportation equipment for nuclear power plants according to claim 4, wherein, The shell assembly includes a cylinder, a support ring and a lifting ear shaft. The second material port is provided at the end of the cylinder away from the opening. The support ring is sleeved on the end of the cylinder with the opening and is provided with the first material port. The lifting ear shaft is installed on the circumferential side of the support ring.
11. The spent fuel transportation equipment for nuclear power plants according to claim 10, characterized in that, The shell assembly also includes a shielding layer, a plurality of heat sinks and a protective shell. The protective shell is sleeved on the outside of the cylinder and defines a cavity with the cylinder. Each heat sink is circumferentially arranged in the cavity and divides the cavity into a plurality of filling cavities. The shielding layer is cast in the filling cavity.
12. The spent fuel transportation equipment for nuclear power plants according to claim 11, characterized in that, A safety valve is provided at one end of the cylinder away from the opening, and the safety valve is communicated with the cavity.
13. The spent fuel transportation equipment for nuclear power plants according to claim 10, characterized in that, A turning block is provided on one side of the cylinder, and the turning block is provided with a groove for turning and receiving force.
14. The spent fuel transportation equipment for nuclear power plants according to claim 10, characterized in that, The open end of the cylinder body is provided with a plurality of steps, the inner cover and the pressing cover are respectively installed on different steps and are completely embedded in the cylinder body, and the outer cover is fastened to the end face of the cylinder body.
15. A spent fuel treatment system, characterized in that, It includes the nuclear power plant spent fuel transportation equipment according to any one of claims 1 to 14.