Shielding cladding barrel for radioactive waste transfer

Abstract

The shielding cladding barrel for radioactive waste transfer comprises an outer barrel, the top end of the outer barrel is in threaded connection with a barrel cover, a containing base is rotatably installed in an inner cavity of the outer barrel, a plurality of through holes are formed in the top end of the containing base at equal intervals in the circumferential direction, and containing plates are installed on the inner walls of the through holes; the placing plate can support a radioactive waste container, and a lifting device used for jacking up the radioactive waste container placed at the top end of the placing plate is assembled at the bottom end of an inner cavity of the outer barrel; the lifting device comprises a rotating wheel, and the rotating wheel is rotationally installed in an inner cavity of the outer barrel. According to the shielding cladding barrel for radioactive waste transfer, in actual use, it can be guaranteed that the positions of all waste containers are stable after the waste containers are placed, radioactive waste container bags can be automatically pushed out, taking is convenient, taking does not need to be conducted deeply, much radiation is avoided, it can be accurately guaranteed that the positions of materials needing to be taken are aligned with the pushing-out position, and the working efficiency is improved. The operation is convenient.

Description

Technical Field

[0001] The utility model relates to the technical field of radioactive material transport containers, in particular to a shielding cladding barrel used for radioactive waste transport. Background Art

[0002] Alpha waste refers to radioactive solid wastes whose radioactivity of alpha emitter nuclides with a half-life greater than 30 years is greater than 4×10^6Bq / kg in a single package (for near-surface disposal facilities, the average alpha specific activity of multiple packages is greater than 4×10^5Bq / kg). Alpha wastes are mainly produced in spent fuel reprocessing plants and facilities or activities that operate plutonium and other transuranic nuclides. They have a long half-life, high toxicity, and high processing and disposal costs. In actual processing, shielded containers are needed to load radioactive wastes so that they can be transported to the processing center for effective processing. The radioactive waste containers currently used have a single box structure, which only has a chamber for accommodating wastes, and multiple radioactive waste unit packaging containers are placed inside. In order to ensure good sealing, the container cylinder is thick and the space is small, making it inconvenient to take out from it. In addition, multiple radioactive wastes are piled up, the internal radiation is strong, and deep taking will be exposed to greater radiation. Based on the above problems, a shielded cladding barrel for radioactive waste transportation is proposed. Utility Model Content

[0003] The utility model aims to provide a shielding cladding barrel for radioactive waste transportation, so as to solve the problem in the above background technology that the radioactive waste container currently used has a single box structure and is not convenient for taking and placing materials deep into the container.

[0004] To achieve the above-mentioned purpose, the utility model provides the following technical solution: a shielded cladding barrel for radioactive waste transportation, comprising: an outer barrel, a barrel cover being screwed on the top end of the outer barrel, a placement seat being rotatably mounted in the inner cavity of the outer barrel, a plurality of through holes being equidistantly opened in the circumferential direction at the top end of the placement seat, a placement plate being mounted on the inner wall of the through hole, the placement plate being capable of supporting a radioactive waste container, and a lifting device being mounted on the bottom end of the inner cavity of the outer barrel for lifting up the radioactive waste container placed on the top end of the placement plate.

[0005] The lifting device includes: a rotating wheel, which is rotatably installed in the inner cavity of the outer barrel, and the outer wall of the rotating wheel extends out of the outer wall of the outer barrel, a rotating drum is rotatably installed in the inner cavity of the outer barrel, a first sprocket is installed at the top of the rotating wheel, a second sprocket is interference fit on the outer wall of the rotating drum, a chain is meshed and connected to the outer walls of the first sprocket and the second sprocket, a screw is threaded in the inner cavity of the rotating drum, and the top of the screw extends out of the inner cavity of the rotating drum, a slideway is opened on the outer wall of the screw, a slider is installed on the inner wall of the outer barrel, and the slider is slidably embedded in the inner cavity of the slideway, a push plate is installed at the top of the slider, and the position of the push plate corresponds to the position of the through hole.

[0006] Preferably, a limiting groove is opened on the inner wall of the outer barrel along the circumferential direction, the circumferential outer wall of the placement seat is rotatably embedded in the inner cavity of the limiting groove, a plurality of blind grooves are opened on the bottom end of the outer wall of the placement seat along the circumferential direction, a ball is rotatably embedded in the inner cavity of the blind groove, and the ball contacts the bottom end of the inner cavity of the limiting groove.

[0007] Preferably, the outer wall of the placement seat is provided with a plurality of slots equidistantly along the circumference, and the inner cavity of the limiting groove is provided with a plurality of built-in cavities equidistantly along the circumference, one end of the built-in cavity is installed on the inner wall of the built-in cavity, and a locking ball is installed on the other end of the spring, and the outer wall of the locking ball extends out of the inner cavity of the built-in cavity and is locked in the inner cavity of the slot.

[0008] Preferably, a partition plate is installed on the outer wall of the placement seat, and the partition plate corresponds to the positions of the plurality of through holes.

[0009] Preferably, an observation hole is provided on the outer wall of the barrel cover, and a sealing cover is screwed to the observation hole.

[0010] Preferably, a handle is installed on the top of the barrel cover.

[0011] Compared with the prior art, the beneficial effects of the utility model are as follows: the shielded cladding barrel for radioactive waste transportation realizes the positioning and placement of each radioactive waste through each through hole and the placement plate, and ensures that the position of each waste container is fixed and stable through the partition plate, and the first sprocket uses the chain to drive the second sprocket and the rotating drum to rotate by rotating the rotating wheel, so that the screw moves upward and the material package at the current position is pushed out, and after the screw is reset, the partition plate is rotated to use the cooperation of the card ball and the card groove to rotate and position the through hole at the adjacent position, so that the radioactive waste can be pushed out again. In actual use, it can ensure that the position of each waste container is stable after being placed, and it can also automatically push out the radioactive waste container package, which is convenient for taking, without going deep inside to take it, avoiding exposure to more radiation, and can accurately ensure that the position of the material to be taken is aligned with the pushing position, which is convenient for operation. BRIEF DESCRIPTION OF THE DRAWINGS

[0012] Figure 1 It is a schematic diagram of the structure of the utility model.

[0013] Figure 2 It is a structural schematic diagram of the observation port of the utility model.

[0014] Figure 3 It is a structural schematic diagram of the placement seat of the utility model.

[0015] Figure 4 It is a top view of the limiting groove of the utility model.

[0016] Figure 5 It is a front cross-sectional view of the outer cylinder of the utility model.

[0017] In the figure: 1, outer barrel, 2, barrel cover, 3, placement seat, 4, through hole, 5, placement plate, 6, limit groove, 7, rolling ball, 8, card slot, 9, built-in cavity, 10, spring, 11, card ball, 12, partition plate, 13, rotating wheel, 14, first sprocket, 15, rotating drum, 16, second sprocket, 17, chain, 18, screw, 19, slide, 20, slider, 21, push plate, 22, sealing cover, 23, observation hole, 24, handle. DETAILED DESCRIPTION

[0018] The following will be combined with the drawings in the embodiments of the utility model to clearly and completely describe the technical solutions in the embodiments of the utility model. Obviously, the described embodiments are only part of the embodiments of the utility model, not all of the embodiments. Based on the embodiments in the utility model, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the utility model.

[0019] See also Figure 1-5 The utility model provides a technical solution of a shielded cladding barrel for the transportation of radioactive waste: a shielded cladding barrel for the transportation of radioactive waste, comprising: an outer barrel 1, a barrel cover 2 is screwed on the top of the outer barrel 1, an observation hole 23 is opened on the outer wall of the barrel cover 2, a sealing cover 22 is screwed on the observation hole 23, the sealing cover 22 is rotated to leave the inner cavity of the observation hole 23, and the internal situation of the outer barrel 1 can be conveniently observed through the observation hole 23. The outer barrel 1, barrel cover 2, and sealing cover 22 are all made of stainless steel outer shells, and the inner support is made of lead plate that can isolate radiation. After being closed, radiation leakage can be effectively prevented. In addition, a handle 24 is installed on the top of the barrel cover 2 to facilitate the removal and placement of the barrel cover 2.

[0020] A placement seat 3 is rotatably installed in the inner cavity of the outer barrel 1, and a plurality of through holes 4 are equidistantly opened at the top of the placement seat 3 along the circumferential direction. A placement plate 5 is installed on the inner wall of the through hole 4. The placement plate 5 is an annular structure with a diameter smaller than the inner cavity of the through hole 4. The radioactive waste is pre-processed and packaged into a corresponding small-volume stainless steel tank. The tank body is an existing general container. The placement plate 5 can support the radioactive waste container and can place the radioactive waste container on the top of the placement plate 5. In addition, a partition plate 12 is installed on the outer wall of the placement seat 3, and the partition plate 12 corresponds to the positions of the plurality of through holes 4, which is convenient for positioning the radioactive waste container and ensures that it can remain stable when moving up and down. A limiting groove 6 is opened in the circumferential direction on the inner wall of the outer barrel 1, and the circumferential outer wall of the placement seat 3 is rotatably embedded in the inner cavity of the limiting groove 6. The bottom end of the outer wall of the placement seat 3 is circumferentially opened. Blind groove, the inner cavity of the blind groove is rolled with a rolling ball 7 embedded therein, and the rolling ball 7 contacts with the bottom end of the inner cavity of the limiting groove 6, the rolling of the rolling ball 7 facilitates the rotation of the placement seat 3, and the length of the rolling ball 7 extending out of the blind groove is less than its own radius to prevent it from falling out, the outer wall of the placement seat 3 is equidistantly provided with a plurality of slots 8 along the circumferential direction, the inner cavity of the limiting groove 6 is equidistantly provided with a plurality of built-in cavities 9 along the circumferential direction, one end of the built-in cavity 9 is installed with one end of a spring 10, and a locking ball 11 is installed at the other end of the spring 10, and the outer wall of the locking ball 11 extends out of the inner cavity of the built-in cavity 9 and is locked in the inner cavity of the locking groove 8, the locking ball 11 is locked into the inner cavity of the locking groove 8 to facilitate the determination of the rotation position of the placement seat 3, so as to facilitate the determination of the position of the through hole 4, when the locking ball 11 is forced to move toward the inner cavity of the built-in cavity 9, the spring 10 can be compressed, and the initial state is restored after the external force is removed, thereby ensuring that the locking ball 11 is reset.

[0021] The bottom end of the inner cavity of the outer barrel 1 is equipped with a lifting device for lifting the radioactive waste container placed on the top of the placement plate 5 upwards, and the lifting device includes: a rotating wheel 13, the rotating wheel 13 is rotatably installed in the inner cavity of the outer barrel 1, and the outer wall of the rotating wheel 13 extends out of the outer wall of the outer barrel 1, and the inner cavity of the outer barrel 1 is rotatably installed with a rotating drum 15, the top of the rotating wheel 13 is installed with a first sprocket 14, the outer wall of the rotating drum 15 is interference-fitted with a second sprocket 16, and the outer walls of the first sprocket 14 and the second sprocket 16 are meshed and connected with a chain 17, and the first sprocket 14 is driven by the chain 17, when the first sprocket 14 is connected with the second sprocket 16, the first sprocket 14 is connected with the second sprocket 16, and the first sprocket 14 is connected with the second sprocket 16. When rotating with the rotating wheel 13, the second sprocket 16 can drive the rotating drum 15 to rotate. The inner cavity of the rotating drum 15 is threaded with a screw 18, and the top of the screw 18 extends out of the inner cavity of the rotating drum 15. The outer wall of the screw 18 is provided with a slideway 19. A slider 20 is installed on the inner wall of the outer barrel 1, and the slider 20 is slidably embedded in the inner cavity of the slideway 19. The slider 20 can limit the slideway 19. When the rotating drum 15 rotates, the screw 18 can only move up and down without rotating. A push plate 21 is installed on the top of the slider 20, and the push plate 21 corresponds to the position of the through hole 4.

[0022] The detailed connection means are well-known technologies in the art. The following mainly introduces the working principle and process, and no longer explains the electrical control.

[0023] When in use, each radioactive waste container is placed on the top of each placement plate 5, and the barrel cover 2 is rotated to close the outer barrel 1. When it is necessary to take it, the barrel cover 2 is opened, and the rotating wheel 13 is rotated to rotate the first sprocket wheel 14 together. The second sprocket wheel 16 and the rotating drum 15 rotate synchronously by the transmission of the chain 17. The slider 20 limits the slideway 19, and the screw 18 can move upward. The push plate 21 penetrates the inner cavity of the through hole 4 to push out the material bag at this position, and then the material bag can be taken out. Then, the rotating wheel 13 is rotated in the opposite direction to reset the screw 18 and the push plate 21. The movable partition plate 12 rotates the placement seat 3, and the outer wall of the placement seat 3 is used to retract the card ball 11 and compress the spring 10. When the other card slot 8 is aligned with the card ball 11, the elastic force of the spring 10 is used to make the card ball 11 fit into the inner cavity of the card slot 8 to achieve positioning. At this time, the other through hole 4 corresponds to the position of the push plate 21. In actual use, it can not only automatically push out the radioactive waste container for easy removal, avoiding people from going deep into it to remove it and prevent strong radiation, but also can rotate and position the material container, so as to facilitate the selection of the radioactive waste container that needs to be taken.

[0024] In the description of the present invention, it should be understood that the terms "coaxial", "bottom", "one end", "top", "center position", "other end", "upper", "one side", "top", "inside", "front", "center", "two ends" and the like indicate positions or positional relationships based on the positions or positional relationships shown in the drawings, and are only for the convenience of describing the present invention 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; at the same time, unless otherwise clearly specified and limited, the terms "snapping", "plugging", "welding", "installation", "setting", "interference fit", "screw connection", "pin connection" and the like should be understood in a broad sense, for example, it can be a fixed connection, a detachable connection, or an integral one; it can be a mechanical connection or an electrical connection; it can be directly connected or indirectly connected through an intermediate medium, it can be the internal connection of two elements or the interaction relationship between two elements. Unless otherwise clearly defined, for ordinary technicians in this field, the specific meanings of the above terms in the present invention can be understood according to specific circumstances.

[0025] Although embodiments of the present invention have been shown and described, it will be appreciated by those skilled in the art that various changes, modifications, substitutions and variations may be made to the embodiments without departing from the principles and spirit of the present invention, and that the scope of the present invention is defined by the appended claims and their equivalents.

Claims

1. A shielding cladding barrel for radioactive waste transportation, characterized in that: include: An outer barrel (1), the top end of the outer barrel (1) being screwed with a barrel cover (2), the inner cavity of the outer barrel (1) being rotatably mounted with a placement seat (3), the top end of the placement seat (3) being provided with a plurality of through holes (4) equidistantly arranged along the circumferential direction, the inner wall of the through hole (4) being mounted with a placement plate (5), the placement plate (5) being capable of supporting a radioactive waste container, and the bottom end of the inner cavity of the outer barrel (1) being equipped with a lifting device for lifting the radioactive waste container placed on the top end of the placement plate (5) upwards; The lifting device comprises: a rotating wheel (13), the rotating wheel (13) being rotatably mounted in the inner cavity of the outer barrel (1), and the outer wall of the rotating wheel (13) extending out of the outer wall of the outer barrel (1), a rotating drum (15) being rotatably mounted in the inner cavity of the outer barrel (1), a first sprocket (14) being mounted on the top end of the rotating wheel (13), a second sprocket (16) being interference-fitted on the outer wall of the rotating drum (15), and the outer walls of the first sprocket (14) and the second sprocket (16) being meshingly connected. A chain (17) is connected, the inner cavity of the rotating drum (15) is threaded with a screw rod (18), and the top end of the screw rod (18) extends out of the inner cavity of the rotating drum (15), the outer wall of the screw rod (18) is provided with a slideway (19), the inner wall of the outer barrel (1) is provided with a slider (20), and the slider (20) is slidably embedded in the inner cavity of the slideway (19), and the top end of the slider (20) is provided with a push plate (21), and the push plate (21) corresponds to the position of the through hole (4).

2. The shielding cladding barrel for radioactive waste transportation according to claim 1, characterized in that: The inner wall of the outer barrel (1) is provided with a limiting groove (6) along the circumferential direction, the circumferential outer wall of the placement seat (3) is rotatably embedded in the inner cavity of the limiting groove (6), and the bottom end of the outer wall of the placement seat (3) is provided with a plurality of blind grooves along the circumferential direction, and a rolling ball (7) is rotatably embedded in the inner cavity of the blind groove, and the rolling ball (7) contacts the bottom end of the inner cavity of the limiting groove (6).

3. The shielding cladding barrel for radioactive waste transportation according to claim 2, characterized in that: The outer wall of the placement seat (3) is provided with a plurality of slots (8) equidistantly along the circumference, and the inner cavity of the limiting groove (6) is provided with a plurality of built-in cavities (9) equidistantly along the circumference. One end of a spring (10) is mounted on the inner wall of the built-in cavity (9), and a locking ball (11) is mounted on the other end of the spring (10), and the outer wall of the locking ball (11) extends out of the inner cavity of the built-in cavity (9) and is locked in the inner cavity of the slot (8).

4. The shielding cladding barrel for radioactive waste transportation according to claim 3, characterized in that: A partition plate (12) is installed on the outer wall of the placement seat (3), and the partition plate (12) corresponds to the positions of the plurality of through holes (4).

5. A shielding cladding barrel for radioactive waste transportation according to any one of claims 1 to 4, characterized in that: An observation hole (23) is provided on the outer wall of the barrel cover (2), and a sealing cover (22) is screwed to the observation hole (23).

6. A shielding cladding barrel for radioactive waste transportation according to any one of claims 1 to 4, characterized in that: A handle (24) is installed at the top end of the barrel cover (2).

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