A concrete spherical tank for storing nuclear waste water and a method for manufacturing the same

By designing a concrete spherical tank and utilizing a combination of an aluminum hemispherical shell and stirring blades, the efficient solidification and sealing of nuclear wastewater was achieved, solving the problems of cumbersome operation and secondary pollution in existing technologies, and improving the safety and efficiency of nuclear wastewater treatment.

CN122266843APending Publication Date: 2026-06-23HENAN JIAO YUAN ENG TECH CO LTD
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Patent Information

Application Number
CN202610384712.0
Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Filing Date
2026-03-26
Publication Date
2026-06-23

AI Technical Summary

Technical Problem

Existing nuclear wastewater solidification processes involve cumbersome procedures, increase the risk of nuclear wastewater exposure, and pose a potential threat of secondary pollution.

Method used

Design a concrete spherical box, including an aluminum hemispherical shell, a mixing shaft, mixing blades, and a cement layer, to mix nuclear wastewater with cement through centrifugation and stirring, reducing transfer steps and enhancing protection.

Benefits of technology

This reduces the number of times nuclear wastewater needs to be transferred, lowers the probability of secondary contamination, and improves the safety and efficiency of nuclear wastewater treatment.

✦ Generated by Eureka AI based on patent content.

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Abstract

This invention relates to the field of nuclear wastewater treatment technology, and in particular to a concrete spherical container for storing nuclear wastewater and its preparation method. A concrete spherical container for storing nuclear wastewater includes a hemispherical shell, a first cement layer, a stirring shaft, and stirring blades. Two hemispherical shells are provided, which can be closed to form a complete, hollow sphere. The first cement layer is disposed on the inner wall of the sphere. The stirring shaft passes through one of the hemispherical shells and the first cement layer, and is rotatably connected to both. The stirring blades are disposed on the stirring shaft and located inside the sphere. The interior of the sphere is filled with cement powder. A water inlet is used to introduce nuclear wastewater into the sphere. By setting the stirring shaft on the hemispherical shell and the stirring blades inside the sphere, the nuclear wastewater can be stirred and solidified inside the sphere. This reduces transfer steps and the amount of equipment the nuclear wastewater comes into contact with, thus reducing the probability of secondary contamination.
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Description

Technical Field

[0001] This invention relates to the field of nuclear wastewater treatment technology, and in particular to a concrete spherical box for sealing nuclear wastewater and its preparation method. Background Technology

[0002] The generation of nuclear wastewater is inevitable during the operation and emergency cooling of nuclear power plants. It primarily originates from the contact between cooling water in the cooling system and reactor core reactants. In emergencies, the large amounts of cooling water injected into the reactor core to prevent nuclear accidents can also create substantial amounts of nuclear wastewater containing high concentrations of radioactive and chemical substances. Improper treatment of this wastewater can cause serious nuclear contamination, posing a long-term and significant threat to the ecological environment and human health. Therefore, the safe disposal of nuclear wastewater is a core issue in the development of the nuclear industry. Currently, cement solidification technology has become the mainstream technology for solidifying nuclear wastewater due to the advantages of cement being an inorganic material, the process being simple, and the solidified body exhibiting strong long-term stability. This process involves mixing and solidifying nuclear wastewater with cement-based materials to form a stable solidified body for the sequestration of nuclear contaminants. However, existing processes have significant drawbacks: multiple stirring operations are required to ensure thorough mixing, leading to cumbersome operation procedures, significantly increasing the risk of nuclear wastewater exposure, and requiring additional treatment for equipment in contact with the wastewater, posing a potential risk of secondary pollution. Summary of the Invention

[0003] Therefore, it is necessary to provide a concrete spherical box for sealing nuclear wastewater and its preparation method to address the problem of excessive transfers and easy exposure during the current solidification process of nuclear wastewater.

[0004] The above objectives are achieved through the following technical solutions: A concrete spherical container for sealing nuclear wastewater includes a hemispherical shell, a first cement layer, a stirring shaft, stirring blades, a water inlet, and a second cement layer. The hemispherical shell is made of aluminum. Two hemispherical shells are provided, which can be closed to form a complete, hollow sphere. The first cement layer is disposed on the inner wall of the sphere. The stirring shaft passes through one of the hemispherical shells and the first cement layer and is rotatably connected to both. The stirring shaft is coaxial with the penetrating hemispherical shell. The stirring blades are disposed on the stirring shaft and located inside the sphere. The stirring shaft has a feed inlet that passes through both ends of the stirring shaft for filling the sphere with cement powder. The water inlet is used to introduce nuclear wastewater into the sphere. The second cement layer is disposed on the outside of the sphere and covers the stirring shaft inside.

[0005] Preferably, the end of the stirring shaft inside the sphere is convex, and a protective shell is fitted on the stirring shaft. The protective shell is located inside the sphere, and the length of the protective shell in the axial direction of the stirring shaft is greater than the thickness of the first cement layer in the radial direction of the hemispherical shell. The stirring shaft is rotatably connected to the first cement layer through the protective shell.

[0006] Preferably, a cap is fitted onto the stirring shaft located outside the hemispherical shell, and the cap is connected to the corresponding hemispherical shell.

[0007] Preferably, the stirring blade includes two sets of blades, one set of blades being located on the side of the other set of blades close to the axis of the stirring shaft; each set has multiple blades, and the multiple blades in the two sets are arranged alternately around the circumferential direction of the stirring shaft, and the side of the outer set of blades close to the first cement layer is provided with a gap between it and the first cement layer.

[0008] Preferably, the blades are spiral-shaped, and the spiral axis of each blade coincides with the axis of the stirring shaft, with the two sets of blades rotating in opposite directions.

[0009] Preferably, the water intake section includes a first water channel, a second water channel, and a sealing element. The first water channel is disposed on the stirring shaft, and the second water channel is disposed on the blade. The first water channel and the second water channel are connected. The blade is provided with multiple branches, each of which is connected to the interior of the sphere and the second water channel respectively. The sealing element is disposed in the first water channel to prevent the nuclear wastewater in the second water channel from flowing out of the first water channel.

[0010] Preferably, each hemispherical shell has a protrusion on its edge, and the two protrusions on the two hemispherical shells are in contact after they are joined together. The two protrusions are respectively provided with reinforcing rings on the sides that are far apart from each other.

[0011] This invention also provides a method for preparing a concrete spherical tank for sealing nuclear wastewater, comprising the following steps: S1, two aluminum plates are stamped into two hemispherical shells by stamping, and cement grout is filled into one of the hemispherical shells; S2, install the stirring shaft onto another hemispherical shell, and place the hemispherical shell with the stirring shaft on the hemispherical shell filled with cement; S3, weld the two hemispherical shells into a sphere to seal the feed port on the stirring shaft; S4. Rotate the sphere to generate centrifugal force in the cement grout inside the sphere until the cement grout inside the sphere solidifies to form the first cement layer. S5, open the feed inlet, add cement powder into the sphere through the feed inlet, and then seal the feed inlet; S6, add nuclear wastewater into the sphere through the water inlet, rotate the sphere so that the sphere and the stirring shaft rotate relative to each other until the cement powder and nuclear wastewater are fully mixed and then stop rotating the sphere; S7, remove the sphere and cover the outside of the sphere with a second cement layer.

[0012] Preferably, in step S4, the sphere rotates around a first axis and a second axis during centrifugal motion. The first axis coincides with the axis of the stirring shaft, and the second axis is perpendicular to the first axis and passes through the center of the sphere.

[0013] Preferably, in steps S4 and S6, the sphere is rotated by a centrifugal device. The centrifugal device includes a support, a rotating frame, and a drive mechanism. The support is fixedly mounted, the rotating frame is rotatably mounted on the support about a second axis, and the sphere is rotatably mounted on the rotating frame about a first axis. The drive mechanism drives the sphere and the rotating frame to rotate. In step S4, the rotating frame and the sphere rotate simultaneously; in step S6, the rotating frame does not rotate, but the sphere rotates.

[0014] The beneficial effects of this invention are as follows: The first cement layer inside the sphere composed of two hemispherical shells serves as the first layer of protection. The aluminum hemispherical shell absorbs some of the radiation source, forming the second layer of protection. The second cement layer wraps around the outside of the sphere, constituting the third layer of protection. A stirring shaft is installed on the hemispherical shell, and stirring blades are installed inside the sphere. The nuclear wastewater can be stirred and solidified inside the sphere, and then sealed by the second cement layer. This reduces the number of transfer steps and the amount of equipment the nuclear wastewater comes into contact with, thus lowering the probability of secondary contamination. Attached Figure Description

[0015] Figure 1 This is a schematic diagram of a concrete spherical box for sealing nuclear wastewater installed on a centrifuge device, as provided in an embodiment of the present invention. Figure 2 for Figure 1 Top view; Figure 3 for Figure 2 Sectional view along the middle AA direction; Figure 4 for Figure 3 Sectional view at point B; Figure 5 for Figure 1 The main view; Figure 6 for Figure 5 A cross-sectional view along the CC direction; Figure 7 for Figure 6 Sectional view at point D; Figure 8 for Figure 6 Sectional view at point E in the middle; Figure 9 for Figure 8 Sectional view at point F; Figure 10 A cross-sectional view of a concrete spherical box for sealing nuclear wastewater provided in an embodiment of the present invention; Figure 11 This is a schematic diagram of the structure of the water injection device provided in an embodiment of the present invention; Figure 12 A split diagram of the rotating frame provided in an embodiment of the present invention.

[0016] in: 100. Hemispherical shell; 101. First cement layer; 102. Connecting shaft; 103. Rotating shaft; 104. Blade; 105. Second cement layer; 106. Feed inlet; 107. Protective shell; 108. Sealing cap; 109. First water channel; 110. Second water channel; 111. First spring; 112. Baffle; 113. Receiving groove; 114. Reinforcing ring; 200. Bracket; 201. Fixing ring; 202. Support rod; 203. Support cylinder; 20 4. Retaining ring; 205. First bevel gear; 206. Second bevel gear; 207. Drive shaft; 208. Groove; 209. Connecting rod; 210. Drive wheel; 211. Fixing plate; 300. Cylinder; 301. Slide plate; 302. Threaded rod; 303. Radiation shielding layer; 304. Conduit; 305. Mounting bracket; 306. Slide rod; 307. Conical truncated cone; 308. Second spring; 309. Rotating plate; 310. Third spring; 311. Slot. Detailed Implementation

[0017] To make the objectives, technical solutions, and advantages of this invention clearer, the invention will be further described in detail below through embodiments and in conjunction with the accompanying drawings. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.

[0018] The component designations used in this document, such as "first" and "second," are merely for distinguishing the described objects and do not have any sequential or technical meaning. The terms "connection" and "linkage" used in this invention, unless otherwise specified, include both direct and indirect connections (linkages). It should be understood that the terms "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," and "counterclockwise," indicating orientations or positional relationships, are based on the orientations or positional relationships shown in the accompanying drawings and are used only for the convenience of describing the invention and simplifying the description. They 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 limiting the invention.

[0019] In this invention, unless otherwise explicitly specified and limited, "above" or "below" the second feature can mean that the first feature is in direct contact with the second feature, or that the first feature is in indirect contact with the second feature through an intermediate medium. Furthermore, "above," "over," and "on top" of 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. "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.

[0020] like Figures 1 to 10 As shown in the figure, an embodiment of the present invention provides a concrete spherical box for sealing nuclear wastewater, comprising a hemispherical shell 100, a first cement layer 101, a stirring shaft, stirring blades, a water inlet, and a second cement layer 105. The hemispherical shell 100 is made of aluminum. Two hemispherical shells 100 are provided, which can be closed to form a complete and hollow sphere. The first cement layer 101 is disposed on the inner wall of the sphere. The stirring shaft passes through one of the hemispherical shells 100 and the first cement layer 101 and is rotatably connected to both. The stirring shaft is coaxial with the penetrating hemispherical shell 100. The stirring blades are disposed on the stirring shaft and located inside the sphere. The stirring shaft is provided with a feed inlet 106, which passes through both ends of the stirring shaft and is used to fill the sphere with cement powder. The water inlet is used to introduce nuclear wastewater into the sphere. The second cement layer 105 is disposed on the outside of the sphere and covers the stirring shaft inside.

[0021] The first cement layer 101 inside the sphere composed of two hemispherical shells 100 serves as the first layer of protection. An aluminum hemispherical shell 100 is used to absorb some of the radiation source, forming the second layer of protection. A second cement layer 105 surrounds the outside of the sphere, constituting the third layer of protection. A stirring shaft is installed on the hemispherical shell 100, and stirring blades are installed inside the sphere. The nuclear wastewater can be stirred and solidified inside the sphere, and then sealed by the second cement layer 105. This reduces the number of transfer steps and the amount of equipment that the nuclear wastewater comes into contact with, thus lowering the probability of secondary contamination.

[0022] In this embodiment, the end of the stirring shaft located inside the sphere is convex, and a protective shell 107 is fitted onto the stirring shaft. The protective shell 107 is located inside the sphere, and its length in the axial direction of the stirring shaft is greater than the thickness of the first cement layer 101 in the radial direction of the hemispherical shell 100. The stirring shaft is rotatably connected to the first cement layer 101 through the protective shell 107. By providing the protective shell 107, the rotation of the stirring shaft can avoid friction with the first cement layer 101, thus preventing wear on the first cement layer 101.

[0023] In this embodiment, a cap 108 is fitted on the stirring shaft located outside the hemispherical shell 100. The cap 108 is connected to the corresponding hemispherical shell 100. The cap 108 blocks the first water channel 109 on the stirring shaft, so that the inside of the sphere is completely isolated from the outside world, thereby improving the radiation isolation effect.

[0024] In this embodiment, the stirring blade includes two sets of blades 104, which are arranged radially along the stirring shaft with a gap between them. Each set contains multiple blades 104, and the multiple blades 104 in the two sets are arranged alternately around the stirring shaft in the circumferential direction. The two sets of blades 104 can more thoroughly stir the cement powder at different positions inside the sphere. The side of the outer set of blades 104 closest to the first cement layer 101 is equally spaced from the first cement layer 101. When the blades 104 rotate relative to the hemispherical shell 100, friction between the blades 104 and the first cement layer 101 is avoided, which would cause wear to the first cement layer 101. At the same time, it is also avoided that the blades 104 and the first cement layer 101 will get stuck when the cement powder passes between them.

[0025] Each blade is crescent-shaped, designed to minimize obstruction to the cement during the mixing process.

[0026] In this embodiment, the blades 104 are helical, and the helical axis of each blade 104 coincides with the axis of the stirring shaft, with the two sets of blades 104 rotating in opposite directions. When the nuclear wastewater enters the interior of the sphere through the water inlet, the hemispherical shell 100 rotates relative to the stirring shaft, and the two sets of blades 104 can guide and stir the cement powder inside the sphere, so that the cement powder and nuclear wastewater are mixed evenly.

[0027] In this embodiment, the water intake section includes a first water channel 109, a second water channel 110, and a sealing component. The first water channel 109 is disposed on the stirring shaft, and the second water channel 110 is disposed on the blade 104. The first water channel 109 and the second water channel 110 are connected. The blade 104 has multiple branches, each of which is connected to the interior of the sphere and the second water channel 110. The sealing component is disposed inside the first water channel 109 to prevent the nuclear wastewater in the second water channel 110 from flowing out of the first water channel 109. Multiple sealing components, first water channels 109, and second water channels 110 are provided. Each first water channel 109 corresponds to one second water channel 110. Each second water channel 110 is disposed on one blade 104. Each blade 104 has multiple branches, and each branch on the blade 104 is connected to the corresponding second water channel 110. The branches on the blade 104 allow the nuclear wastewater to be sprayed more evenly within the sphere, promoting the mixing of cement powder and nuclear wastewater.

[0028] The stirring shaft includes a connecting shaft 102 and a rotating shaft 103. The rotating shaft 103 is rotatably connected to one of the hemispherical shells 100, with one end extending into the interior of the shell. The connecting shaft 102 and the rotating shaft 103 are coaxial and connected by bolts. The connecting shaft 102 is located outside the shell. A first water channel 109 passes through the connecting shaft 102 and the rotating shaft 103 along the axial direction of the rotating shaft 103, with a convex surface located on the end of the rotating shaft 103 inside the shell. The feed inlet 106 passes through the rotating shaft 103 and the connecting shaft 102.

[0029] Each sealing component includes a first spring 111 and a baffle 112. The end of the connecting shaft 102 near the rotating shaft 103 has the same number of receiving grooves 113 as the first water channels 109. The receiving grooves 113 are coaxial with and communicate with the first water channels 109, and the projected size of the receiving grooves 113 in the axial direction of the connecting shaft 102 is larger than the projected size of the first water channels 109 in the axial direction of the connecting shaft 102. The first spring 111 is disposed on the end of the rotating shaft 103 near the connecting shaft 102 and is located in one of the receiving grooves 113. The baffle 112 is disposed on the end of the first spring 111 away from the rotating shaft 103 and abuts against the connecting shaft 102. When the baffle 112 abuts against the connecting shaft 102, it divides the corresponding first water channel 109 on the connecting shaft 102 into two completely separated parts.

[0030] In this embodiment, each hemispherical shell 100 has a protrusion on its edge. When the two hemispherical shells 100 are closed together, the two protrusions on them contact each other. The two protrusions are respectively provided with reinforcing rings 114 on their opposite sides. The two reinforcing rings 114 clamp the two protrusions, which can improve the overall hardness of the protrusions.

[0031] The working principle of the concrete spherical container for sealing nuclear wastewater provided in the above embodiment is as follows: A certain amount of cement slurry is filled into one hemispherical shell 100. Then, a rotating shaft 103 passes through the other hemispherical shell 100, and blades 104 are placed inside the hemispherical shell 100. The two hemispherical shells 100 are welded together to form a complete sphere. The cement slurry inside the sphere is centrifuged by a centrifugal device to form a first cement layer 101. Then, cement powder is added into the sphere through the feed port 106, and then the feed port 106 is sealed. Nuclear wastewater is injected into the sphere through the first water channel 109, while the sphere and blades 104 rotate relative to each other, promoting the mixing of nuclear wastewater and cement powder. Finally, a second cement layer 105 is wrapped around the outside of the sphere.

[0032] This invention also provides a method for preparing a concrete spherical tank for sealing nuclear wastewater, the steps of which are as follows: S1. Two aluminum plates are stamped into two hemispherical shells 100 by stamping. Cement grout is filled into one hemispherical shell 100, and the other hemispherical shell 100 is stamped again to create a through hole that matches the rotating shaft 103. After the two hemispherical shells 100 are stamped, two bosses are cut out at the edges of the two hemispherical shells 100 for subsequent welding.

[0033] S2, the stirring shaft is installed onto another hemispherical shell 100 and passes through the through hole in the hemispherical shell 100, so that the protective shell 107 contacts the hemispherical shell 100, and the protective shell 107 is welded to the hemispherical shell 100. At this time, the blade 104 is inside the hemispherical shell 100. The hemispherical shell 100 with the stirring shaft is placed on the hemispherical shell 100 filled with cement, so that the bosses on the two hemispherical shells 100 contact each other.

[0034] S3, the two hemispherical shells 100 are welded into a sphere by the boss, and a reinforcing ring 114 is set on the side of the two bosses that are far apart from each other. Then, the sphere is installed on the centrifuge device by the reinforcing ring 114 to avoid damage to the surface of the aluminum sphere.

[0035] S4. The centrifugal device rotates the sphere, causing centrifugal force to be generated in the cement slurry inside the sphere. During the centrifugal process, the cement slurry, under the action of centrifugal force, adheres to the inner wall of the sphere composed of two hemispherical shells 100, forming a hollow shell with a thickness less than that of the protective shell 107. The cement slurry on the convex surface will slide down the convex surface guided by the curvature of the convex surface until the cement slurry inside the sphere solidifies to form the first cement layer 101. After solidification, the first cement layer 101 will not submerge the protective shell 107, and the protective shell 107 and the rotating shaft 103 can still rotate relative to each other. When the sphere is in centrifugal motion, it rotates around the first axis and the second axis. The first axis coincides with the axis of the stirring shaft, and the second axis is perpendicular to the first axis and passes through the center of the sphere.

[0036] The centrifuge device includes a support 200, a rotating frame, and a drive mechanism. The support 200 is fixedly installed, the rotating frame is rotatably installed on the support 200, and the sphere is rotatably installed on the rotating frame. The rotation axis of the sphere is perpendicular to the rotation axis of the rotating frame. The drive mechanism is used to drive the sphere and the rotating frame to rotate.

[0037] Specifically, such as Figure 1 , Figure 2 , Figure 5 , Figure 7 and Figure 12As shown, the rotating frame includes a fixed ring 201, a support rod 202, a support cylinder 203, a retaining ring 204, a first bevel gear 205, a second bevel gear 206, and a transmission shaft 207. The support rod 202 and the support cylinder 203 are respectively installed on the outer circumferential surface of the fixed ring 201, and the support rod 202 and the support cylinder 203 are coaxial. The bracket 200 is provided with a mounting seat, and the support rod 202 and the support cylinder 203 are respectively rotatably mounted on the mounting seat. One end of the fixed ring 201 has a groove 208. Two reinforcing rings 114 on the sphere are rotatably mounted in the groove 208. The reinforcing rings 114 are coaxial with the fixed ring 201. The retaining ring 204 is threadedly connected to the fixed ring 201 by bolts, and the retaining ring 204 is coaxial with the fixed ring 201. The retaining ring 204 is located on the side of the fixed ring 201 with the groove 208, and the retaining ring 204 can seal the groove 208.

[0038] The groove 208 is provided with multiple connecting rods 209, which are arranged around the circumferential direction of the fixed ring 201. Each connecting rod 209 is rotatably connected to the fixed ring 201 and the retaining ring 204 respectively, and the rotation axis of the connecting rod 209 is parallel to the axis of the fixed ring 201. Each connecting rod 209 is provided with a drive wheel 210, and the multiple drive wheels 210 are in contact with the circumferential surface of the reinforcing ring 114 respectively.

[0039] One of the connecting rods 209 has its axis along the longitudinal axis of the support cylinder 203. One end of the connecting rod 209 passes through the fixing ring 201. A first bevel gear 205 is sleeved on the connecting rod 209 and located on one side of the fixing ring 201. A fixing plate 211 is provided on the mounting base where the support cylinder 203 is located. A drive shaft 207 is rotatably mounted on the fixing plate 211 and coaxial with the support cylinder 203. A second bevel gear 206 is sleeved on the drive shaft 207 and fixedly connected to it. The second bevel gear 206 is located inside the support cylinder 203 and meshes with the first bevel gear 205. A notch is provided on the support cylinder 203, and the first bevel gear 205 is located at the notch. The drive mechanism drives the drive shaft 207 and the support rod 202 to rotate, causing the ball to rotate on its own axis while rotating with the fixing ring 201. The cement slurry inside the ball is then evenly adhered to the inner wall of the ball by centrifugal force.

[0040] Both the fixed ring 201 and the retaining ring 204 have multiple guide wheels on the side near the reinforcing ring 114. The multiple guide wheels are arranged around the circumference of the fixed ring 201, and each guide wheel is rotatably mounted on the corresponding fixed ring 201 or reinforcing ring 114. The extension line of the rotation axis of each guide wheel passes through the axis of the fixed ring 201 and the two are perpendicular to each other. The guide wheels on the fixed ring 201 and the retaining ring 204 are in contact with the corresponding reinforcing ring 114. When the reinforcing ring 114 rotates, it can drive the guide wheels to rotate, thereby reducing the friction between the reinforcing ring 114 and the fixed ring 201 and the retaining ring 204.

[0041] There are two drive mechanisms, one for driving the drive shaft 207 to rotate and the other for driving the support rod 202 to rotate. Each drive mechanism includes a first motor, a gearbox, a first pulley, a second pulley, and a transmission belt. The first motor and gearbox are mounted on the bracket 200, and the output end of the first motor is connected to the input end of the gearbox. The first pulley is located at the output end of the gearbox, and the second pulley is mounted on the support rod 202 or the drive shaft 207. The transmission belt is wound around the first and second pulleys.

[0042] After the reinforcing ring 114 on the sphere is placed in the groove 208, the retaining ring 204 is then installed on the reinforcing ring 114 and bolted to it. At this point, the sphere can rotate relative to the reinforcing ring 114. The feed inlet 106 on the mixing shaft is sealed with a rubber stopper to prevent the cement slurry inside the sphere from spilling out during centrifugation. Then, the two first motors are started. The two first motors drive the corresponding first rotating wheel to rotate through their respective gearboxes. The first rotating wheel drives the corresponding second rotating wheel to rotate through a transmission belt. The two second rotating wheels drive the corresponding transmission shaft 207 and support rod 202 to rotate respectively. The support rod 202 drives the fixing ring 201 to rotate, and the fixing ring 201 drives the sphere to rotate around the support rod 202. At the same time, the transmission shaft 207 drives the second bevel gear 206 to rotate, the second bevel gear 206 drives the first bevel gear 205 to rotate, the first bevel gear 205 drives one of the connecting rods 209 to rotate, the connecting rod 209 drives the corresponding drive wheel 210 to rotate, the drive wheel 210 drives the reinforcing ring 114 to rotate in the groove 208, and the reinforcing ring 114 drives the ball to rotate around the axis of the rotating shaft 103.

[0043] In another embodiment, the drive wheel 210 is a gear and the reinforcing ring 114 is an external gear ring. The drive wheel 210 meshes with the reinforcing ring 114, making the transmission between the drive wheel 210 and the reinforcing ring 114 more stable.

[0044] In step S4, when the sphere is centrifuged, the rotating frame and the sphere rotate simultaneously.

[0045] S5, open the feed inlet 106, add cement powder into the sphere through the feed inlet 106, and then seal the feed inlet 106 by blocking the feed inlet 106 with a radiation-proof rubber plug or cement block to prevent the cement powder inside the sphere from flowing out.

[0046] S6. The rotating frame does not rotate. Nuclear wastewater is added into the sphere through the water injection device and water inlet. The sphere is rotated so that the sphere rotates relative to the stirring shaft until the cement powder and nuclear wastewater are fully mixed and then the rotation of the sphere stops.

[0047] When nuclear wastewater is injected into the first channel, it enters the second channel 110 through the first channel 109, and then exits through a branch channel into the interior of the sphere to mix with the cement powder inside the sphere. Through the relative rotation of the sphere and the rotating shaft 103, the nuclear wastewater and cement powder inside the sphere are mixed together. At the same time, one of the drive mechanisms is activated, causing the drive shaft 207 to rotate, which in turn causes the sphere to rotate around the rotating shaft 103. The blades 104 rotate relative to the sphere, stirring the cement powder inside the sphere.

[0048] Specifically, such as Figure 4 , Figure 8 and Figure 11 As shown, the water injection device includes a clamping sleeve 300, a sliding plate 301, a threaded rod 302, and a positioning assembly. Multiple planes are provided on the circumferential surface of the connecting shaft 102. The clamping sleeve 300 is slidably sleeved on the connecting shaft 102 along its axial direction and is engaged with the connecting shaft 102 circumferentially through the planes on the connecting shaft 102. The clamping sleeve 300 is covered with a radiation-shielding layer 303. The sliding plate 301 is slidably disposed within the clamping sleeve 300 along its axial direction. The threaded rod 302 is rotatably disposed within the clamping sleeve 300 and extends along its axial direction. The threaded rod 302 is driven by a second motor and is threadedly connected to the sliding plate 301. The slide plate 301 is provided with a number of conduits 304 equal to the number of first water channels 109 on one side near the connecting shaft 102. Each conduit 304 corresponds to one first water channel 109 and can slide in the corresponding first water channel 109. One end of each conduit 304 on the slide plate 301 is connected to a pipeline for transporting nuclear wastewater. Each conduit 304 is provided with a mounting bracket 305, a sliding rod 306, a truncated cone 307, and a second spring 308. The mounting bracket 305 is fixedly installed on the inner wall of the conduit 304. The sliding rod 306 is slidably mounted on the mounting bracket 305 along the axial direction of the conduit 304. The truncated cone 307 has a large end and a small end. The large end of the truncated cone 307 is connected to the sliding rod 306, and the truncated cone 307 is located on the side of the sliding rod 306 away from the sliding plate 301. The inner wall of the end of the conduit 304 away from the sliding plate 301 is provided with a conical surface that is adapted to the truncated cone 307. When the truncated cone 307 approaches the end of the conduit 304 with the conical surface, it can seal the end of the conduit 304 through its own conical surface and the conical surface on the conduit 304. When the truncated cone 307 contacts the conical surface of the conduit 304, the small end of the truncated cone 307 extends out from the conduit 304. The second spring 308 is sleeved on the slide rod 306 and its two ends are connected to the mounting bracket 305 and the cone 307 respectively. The elasticity of the second spring 308 is greater than that of the first spring 111. The positioning assembly is used to position the retaining sleeve 300 on the connecting shaft 102 before the baffle 112 abuts against the cone 307, so as to prevent the retaining sleeve 300 from being moved away from the connecting shaft 102 by the reaction force during the injection of nuclear wastewater.

[0049] Multiple positioning components are provided, arranged around the circumferential direction of the clamping cylinder 300. Each positioning component includes a rotating plate 309 and a third spring 310. The rotating plate 309 is rotatably mounted on the clamping cylinder 300 and has a first end and a second end. The first end and the second end are arranged along the axial direction of the clamping cylinder 300, and the first end is farther away from the connecting shaft 102 than the second end. The rotation axis of the rotating plate 309 is perpendicular to the rotation axis of the clamping cylinder 300 and is located between the first end and the second end. The circumferential surface of the connecting shaft 102 is provided with multiple slots 311 arranged along the circumferential direction of the connecting shaft 102. The second end of the rotating plate 309 has a protrusion on the side near the axis of the clamping cylinder 300. After the rotating plate 309 rotates, the protrusion can be engaged into the slot 311. The third spring 310 is located on the side of the rotating plate 309 away from the protrusion, and its two ends are connected to the rotating plate 309 and the retaining sleeve 300 respectively. It is used to pull the rotating plate 309 to rotate and make the protrusion move away from the retaining slot 311. The side of the sliding plate 301 near the connecting shaft 102 is chamfered. After the sliding plate 301 moves closer to the connecting shaft 102, it can contact the first end of the rotating plate 309 and push the rotating plate 309 to rotate through the chamfer.

[0050] Specifically, after the first cement layer 101 is formed, when nuclear wastewater needs to be injected into the sphere, the connecting shaft 102 must first be in a horizontal position. Then, the clamping sleeve 300 is aligned with the connecting shaft 102 and fitted onto it. Next, the second motor is started, which drives the threaded rod 302 to rotate. The rotation of the threaded rod 302 will drive the sliding plate 301 to move closer to the connecting shaft 102 in the clamping sleeve 300. The sliding plate 301 gradually moves closer to and contacts the first end of the rotating plate 309. After the sliding plate 301 contacts the rotating plate 309, it pushes the rotating plate 309 to rotate. The rotation of the rotating plate 309 stretches the third spring 310, and the protrusion on the second end of the rotating plate 309 gradually moves closer to the slot 311 until it rotates into the slot 311. At this time, the rotating plate 309 uses the protrusion and the slot 311 to make the clamping sleeve 300 and the connecting shaft 102 engage in the axial direction of the clamping sleeve 300.

[0051] As the threaded rod 302 continues to rotate, the slide plate 301 drives multiple conduits 304 to insert into the corresponding first water channel 109. Continuing forward, when the small end of the cone 307 abuts against the baffle 112 in the corresponding receiving groove 113 of the first water channel 109, the baffle 112 moves away from the abutting connecting shaft 102 and compresses the first spring 111. The compressed first spring 111 increases its elastic potential energy, increasing the resistance experienced by the cone 307. The second spring 308 is also gradually compressed, and the cone 307 begins to move closer to the mounting bracket 305. The conduits 304 connect with the receiving groove 113, and the nuclear wastewater in the conduits 304 passes through the receiving groove 113 and then enters the first water channel 109. The nuclear wastewater entering the first water channel 109 then enters the corresponding second water channel 110 and is discharged from the branch channel.

[0052] When the clamp 300 engages with the connecting shaft 102, one of the drive mechanisms is activated to drive the transmission shaft 207 to rotate. The transmission shaft 207 drives the corresponding connecting rod 209 to rotate through the second bevel gear 206 and the first bevel gear 205. The connecting rod 209 drives the reinforcing ring 114 to rotate through the drive wheel 210. The reinforcing ring 114 drives the sphere formed by the two hemispherical shells 100 to rotate relative to the blade 104 around the axis of the rotating shaft 103. The nuclear wastewater discharged from the branch channel on the blade 104 comes into contact with and mixes with the cement powder.

[0053] Once the amount of nuclear wastewater entering the sphere reaches a preset value, the second motor is activated to reverse. The second motor drives the threaded rod 302 to reverse, which in turn moves the sliding plate 301 away from the connecting shaft 102. The contact force between the cone 307 and the baffle 112 decreases. The second spring 308 first resets, causing the cone 307 to contact the conical surface on the guide tube 304. As the guide tube 304 moves, the baffle 112 gradually slides in the receiving groove 113 under the action of the first spring 111, finally contacting the connecting shaft 102, thus isolating the first water channel 109. The sphere then continues to rotate until the nuclear wastewater and cement powder inside are evenly mixed.

[0054] Then continue to rotate the threaded rod 302 to separate the slide plate 301 from the rotating plate 309. The protrusion comes out of the slot 311 under the action of the third spring 310. Then remove the retainer 300 from the connecting shaft 102 and cover the connecting shaft 102 with the cap 108. Weld the cap 108 and the hemispherical shell 100 together.

[0055] S7. Remove the sphere and cover its exterior with a second cement layer 105. Specifically, after covering the connecting shaft 102 with a cap 108 and welding it to the hemispherical shell 100, remove the sphere from the centrifuge and immerse it in an existing mold containing cement slurry. Once the cement slurry in the mold has solidified, the second cement layer 105 is formed. The nuclear wastewater sealing operation is complete.

[0056] 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.

[0057] The embodiments described above are merely illustrative of several implementations of the present invention, and while the descriptions are specific and detailed, they should not be construed as limiting the scope of the invention. It should be noted that those skilled in the art can make various modifications and improvements without departing from the concept of the present invention, and these modifications and improvements all fall within the scope of protection of the present invention. Therefore, the scope of protection of the present invention should be determined by the appended claims.

Claims

1. A concrete spherical container for sealing nuclear wastewater, characterized in that, include: The system comprises a hemispherical shell, a first cement layer, a stirring shaft, stirring blades, a water inlet, and a second cement layer. The hemispherical shell is made of aluminum. Two hemispherical shells are provided, which can be closed to form a complete, hollow sphere. The first cement layer is located on the inner wall of the sphere. The stirring shaft passes through one of the hemispherical shells and the first cement layer and is rotatably connected to both. The stirring shaft is coaxial with the penetrating hemispherical shell. The stirring blades are located on the stirring shaft and inside the sphere. The stirring shaft has a feed inlet that passes through both ends of the stirring shaft and is used to fill the sphere with cement powder. The water inlet is used to introduce nuclear wastewater into the sphere. The second cement layer is located on the outside of the sphere and covers the stirring shaft inside.

2. The concrete spherical box for sealing nuclear wastewater according to claim 1, characterized in that, The stirring shaft has a convex end inside the sphere, and a protective shell is fitted on the stirring shaft. The protective shell is located inside the sphere, and the length of the protective shell in the axial direction of the stirring shaft is greater than the thickness of the first cement layer in the radial direction of the hemispherical shell. The stirring shaft is rotatably connected to the first cement layer through the protective shell.

3. A concrete spherical tank for sealing nuclear wastewater according to claim 1, characterized in that, A cap is fitted onto the stirring shaft located outside the hemispherical shell, and the cap is connected to the corresponding hemispherical shell.

4. A concrete spherical container for sealing nuclear wastewater according to claim 1, characterized in that, The stirring blade includes two sets of blades, one set of blades being located on the side of the other set of blades close to the axis of the stirring shaft; each set has multiple blades, and the multiple blades in the two sets are arranged alternately around the circumferential direction of the stirring shaft, with a gap between the side of the outer set of blades close to the first cement layer and the first cement layer.

5. A concrete spherical tank for sealing nuclear wastewater according to claim 4, characterized in that, The blades are spiral-shaped, and the spiral axis of each blade coincides with the axis of the stirring shaft. The two sets of blades rotate in opposite directions.

6. A concrete spherical tank for sealing nuclear wastewater according to claim 4, characterized in that, The water intake section includes a first water channel, a second water channel, and a sealing component. The first water channel is located on the stirring shaft, and the second water channel is located on the blade. The first water channel and the second water channel are connected. The blade has multiple branches, each of which is connected to the interior of the sphere and the second water channel. The sealing component is located inside the first water channel to prevent nuclear wastewater in the second water channel from flowing out of the first water channel.

7. A concrete spherical tank for sealing nuclear wastewater according to claim 1, characterized in that, Each hemispherical shell has a protrusion on its edge. When the two hemispherical shells are joined together, the two protrusions on them come into contact. The two protrusions that are far apart from each other are respectively provided with reinforcing rings.

8. A method for preparing a concrete spherical tank for sealing nuclear wastewater, utilizing the concrete spherical tank for sealing nuclear wastewater as described in any one of claims 1 to 7, characterized in that, The steps are as follows: S1, two aluminum plates are stamped into two hemispherical shells by stamping, and cement grout is filled into one of the hemispherical shells; S2, install the stirring shaft onto another hemispherical shell, and place the hemispherical shell with the stirring shaft on the hemispherical shell filled with cement; S3, weld the two hemispherical shells into a sphere to seal the feed port on the stirring shaft; S4. Rotate the sphere to generate centrifugal force in the cement grout inside the sphere until the cement grout inside the sphere solidifies to form the first cement layer. S5, open the feed inlet, add cement powder into the sphere through the feed inlet, and then seal the feed inlet; S6, add nuclear wastewater into the sphere through the water inlet, rotate the sphere so that the sphere and the stirring shaft rotate relative to each other until the cement powder and nuclear wastewater are fully mixed and then stop rotating the sphere; S7, remove the sphere and cover the outside of the sphere with a second cement layer.

9. A method for preparing a concrete spherical tank for sealing nuclear wastewater according to claim 8, characterized in that, In step S4, the sphere rotates around the first axis and the second axis when it is in centrifugal motion. The first axis coincides with the axis of the stirring shaft, and the second axis is perpendicular to the first axis and passes through the center of the sphere.

10. A method for preparing a concrete spherical box for sealing nuclear wastewater according to claim 9, characterized in that, In steps S4 and S6, the sphere is rotated by a centrifugal device. The centrifugal device includes a support, a rotating frame, and a drive mechanism. The support is fixedly installed, the rotating frame is rotatably mounted on the support around a second axis, and the sphere is rotatably mounted on the rotating frame around a first axis. The drive mechanism is used to drive the sphere and the rotating frame to rotate. In step S4, the rotating frame and the sphere rotate simultaneously. In step S6, the rotating frame does not rotate, but the sphere rotates.