Sealing device for stirring and solidifying radioactive wet waste in barrel of nuclear power plant
By designing an automatic adjustment sealing device, the problem of cement ash and radioactive aerosol dispersion when nuclear power plants deal with radioactive wet waste is solved, and effective sealing of equipment and air and safety protection of operators is achieved.
Patent Information
- Application Number
- CN202421373083.4
- Authority / Receiving Office
- CN · China
- Patent Type
- Utility models(China)
- Current Assignee / Owner
- Filing Date
- 2024-06-14
- Publication Date
- 2025-06-06
- Estimated Expiration
- 2034-06-14
AI Technical Summary
When nuclear power plants deal with radioactive wet waste, cement ash and radioactive aerosols will spread into the surrounding environment, causing equipment and air pollution.
A sealing device for the top of the agitator paddle is designed, the device including a base, a dust cover, a lifting assembly and a support frame. Through the lifting assembly driven by the pneumatic unit, the dust cover can automatically rise or fall according to the lifting height of the stirring paddle, thereby achieving sealing with the stirring equipment.
Effective sealing of cement ash and radioactive aerosols is achieved, preventing them from spreading into the surrounding environment, reducing radioactive pollution of equipment and air, and improving safety protection for operators.
Smart Images
Figure CN222943374U_ABST
Abstract
Description
Technical Field
[0001] The utility model relates to the field of nuclear waste treatment, in particular to a sealing device used for stirring and solidifying radioactive wet waste barrels in nuclear power plants. Background Art
[0002] During the operation of a nuclear power plant, wet waste such as radioactive waste resin and concentrated liquid is generated. A cement solidification system is required to stir the wet waste in a metal barrel to form a stable cement solidified body. During the stirring process, when the stirring paddle is lifted to any height for stirring, the sealing surface on the top of the stirring paddle and the stirring device will lose the seal, and cement dust and radioactive aerosols will diffuse into the surrounding environment, causing radioactive contamination of equipment and room air pollution. It is necessary to develop a sealing device between the sealing surface on the top of the stirring paddle and the bottom of the stirring device. The sealing device can be remotely adjusted according to the lifting height of the stirring paddle and can perform a better sealing effect to prevent cement dust and radioactive aerosols from diffusing into the surrounding environment. At the same time, due to the flying radioactive dust, it will cause internal contamination of personnel. Utility Model Content
[0003] The technical problem to be solved by the utility model is to provide a sealing device for stirring and solidifying radioactive wet waste barrels in nuclear power plants, aiming to solve the problem in the prior art that cement dust and radioactive aerosols will diffuse into the surrounding environment during nuclear waste treatment, causing radioactive contamination of equipment and room air pollution.
[0004] The technical solution adopted by the utility model to solve its technical problems includes: a base, a dust cover, a lifting assembly and a supporting frame; the dust cover is arranged on the base, the supporting frame is sleeved on the dust cover, the lifting assembly includes a fixing part and an output element, the fixing part is fixed on the base, the output element is arranged on the fixing part, the output element is provided with an output end, the output end of the output element is connected to the supporting frame, the direction of the output end moves upward from the base, and an elastic sealing ring is provided on the upper part of the dust cover.
[0005] In one embodiment, the output element is a pneumatic unit, and the extended rod of the pneumatic unit is the output end.
[0006] In one embodiment, the pneumatic unit is a cylinder with a guide rod.
[0007] In one embodiment, there are at least two output elements, and the output elements are evenly distributed and seated on the base.
[0008] In one embodiment, the pneumatic unit further comprises a buffer, and the buffer is arranged at an end of the guide rod cylinder away from the extension rod.
[0009] In one embodiment, the supporting frame is a circular metal ring.
[0010] In one embodiment, an exhaust port is further provided under the base.
[0011] In one embodiment, the dust cover is made of metal fiber radiation protection fabric.
[0012] In one embodiment, the base is circular, and the shape of the dust cover matches the base.
[0013] The implementation of the utility model has the following beneficial effects: by arranging a dust cover and an output element on the base, the output end of the output element will drive the dust cover to rise, and the dust cover rises to the bottom of the stirring device, and the dust cover is well sealed with the bottom of the stirring device. When sealing is not required, the output end of the output element will drive the dust cover to descend. The whole process is fully automatic and does not require manual operation, thereby achieving protection against radiation dust and improving the safety protection of operators. BRIEF DESCRIPTION OF THE DRAWINGS
[0014] In order to more clearly illustrate the technical solution of the utility model, the utility model will be further described below in conjunction with the accompanying drawings and embodiments. It should be understood that the following drawings only show certain embodiments of the utility model, and therefore should not be regarded as limiting the scope. For ordinary technicians in this field, other relevant drawings can be obtained based on these drawings without creative work. In the drawings:
[0015] Figure 1 This is an overall structural diagram of a sealing device for stirring and solidifying radioactive wet waste in a nuclear power plant in an embodiment of the utility model when it is raised;
[0016] Figure 2 This is an overall structural diagram of a sealing device for stirring and solidifying radioactive wet waste in a nuclear power plant in an embodiment of the utility model when it is lowered;
[0017] Figure 3 The utility model is a cross-sectional view of a sealing device used for stirring and solidifying radioactive wet waste barrels in nuclear power plants in one embodiment.
[0018] Figure Annotation
[0019] 1. Dust cover; 2. Output element; 3. Guide rod; 4. Fixing piece; 5. Base; 6. Exhaust port; 7. Support frame. DETAILED DESCRIPTION
[0020] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, the specific implementation methods of the present invention are now described in detail with reference to the accompanying drawings. In the following description, it should be understood that the directions or positional relationships indicated by "front", "back", "up", "down", "left", "right", "longitudinal", "horizontal", "vertical", "horizontal", "top", "bottom", "inside", "outside", "head", "tail", etc. are based on the directions or positional relationships shown in the accompanying drawings, are constructed and operated in a specific direction, and are only for the convenience of describing the present technical solution, rather than indicating that the device or element referred to must have a specific direction, and therefore cannot be understood as a limitation to the present invention.
[0021] It should also be noted that, unless otherwise clearly specified and limited, the terms such as "installed", "connected", "connected", "fixed", "set" 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. When an element is referred to as being "on" or "under" another element, the element can be "directly" or "indirectly" located on the other element, or there may be one or more intermediate elements. The terms "first", "second", "third", etc. are only for the convenience of describing the present technical solution, and cannot be understood as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Therefore, the features defined as "first", "second", "third", etc. can explicitly or implicitly include one or more of the features. For those of ordinary skill in the art, the specific meanings of the above terms in the present utility model can be understood according to the specific circumstances.
[0022] Figures 1 to 3A sealing device for stirring and solidifying radioactive wet waste barrels in nuclear power plants in one embodiment of the utility model is shown. The sealing device for stirring and solidifying radioactive wet waste barrels in nuclear power plants can be used to seal the stirring device, and may include: a base 5, a dust cover 1, a lifting assembly and a support frame 7; the dust cover 1 is arranged on the base 5, the support frame 7 is sleeved on the dust cover 1, the lifting assembly includes a fixing member 4 and an output element 2, the fixing member 4 is fixed on the base 5, the output element 2 is arranged on the fixing member 4, the output element 2 is provided with an output end, the output end of the output element 2 is connected to the support frame 7, the output end moves upward from the base 5, and an elastic sealing ring is provided on the upper part of the dust cover 1. By arranging the dust cover 1 and the output element 2 on the base 5, the output end of the output element 2 will drive the dust cover 1 to rise, the dust cover 1 rises to the bottom of the stirring device, and the dust cover 1 is well sealed with the bottom of the stirring device. When sealing is not required, the output end of the output element 2 will drive the dust cover 1 to descend, and the whole process is fully automatic, without manual operation, to achieve protection against radioactive dust and improve the safety protection of operators.
[0023] In a specific embodiment, the dust cover 1 is folded to reduce its volume and height.
[0024] In one embodiment, the output element 2 may include a pneumatic unit, the extension rod of the pneumatic unit is the output end, the pneumatic unit has stable power, low cost, and can provide linear motion. There are at least two output elements, and the output elements are evenly arranged on the base.
[0025] It is understandable that the output element 2 may be other types of drives, such as an electric cylinder, a screw drive, etc.
[0026] In one embodiment, the pneumatic unit may include a cylinder with a guide rod, and the guide rod 3 can limit the extension rod to move only in a straight line, reduce the deviation in other directions, improve the straightness of the movement, and enable the dust cover 1 to rise in a straight line.
[0027] In one embodiment, the pneumatic unit may include a limit sensor, which is arranged on the guide rod 3 or the extension rod. The limit sensor can sense that the guide rod 3 or the extension rod has reached the specified position, and then stop the movement of the cylinder to prevent the cylinder from continuously outputting power, causing the dust cover 1 to abut against the stirring equipment, causing damage to the dust cover 1, thereby increasing the service life of the device.
[0028] In a specific embodiment, the limit sensor is a metal proximity sensor, which directly senses the position of the guide rod 3 or the extension rod, and has low cost and high reliability.
[0029] In a specific embodiment, a buffer is also provided on the pneumatic unit, and the buffer is arranged on the guide rod 3. When the guide rod 3 rises, the bottom of the guide rod 3 will contact the buffer, slowing down the speed of the guide rod 3, and then slowing down the rising speed of the dust cover 1, which can prevent the dust cover 1 from directly hitting the stirring equipment.
[0030] The pneumatic unit may include a buffer in one embodiment, and the buffer is arranged at one end of the cylinder with the guide rod 3 away from the extension rod.
[0031] It is understandable that the buffer can be one of a hydraulic buffer, a polyurethane buffer, and a spring buffer.
[0032] Figure 3 As shown, the support skeleton 7 may include in one embodiment, the support skeleton 7 is a circular metal ring, and the circular metal ring can support the upper part of the dust cover 1 to rise evenly to abut the stirring equipment, so as to avoid the dust leakage caused by deformation of a part of the dust cover 1 due to lack of support.
[0033] In one embodiment, the base 5 may include an exhaust port 6 disposed below the base 5 , and the exhaust port 6 is used to exhaust dust.
[0034] In one embodiment, the dust cover 1 may include: the dust cover 1 is made of metal fiber radiation-proof fabric, and the radiation-proof fabric can effectively block radiation.
[0035] It can be understood that the dust cover 1 can be made of other fabrics with radiation protection, such as multi-element fabrics, copper / nickel ion fabrics, silver fiber fabrics, and unidirectional anti-static fabrics.
[0036] In one embodiment, the base 5 and the dust cover 1 may include: the base 5 is circular, and the shape of the dust cover 1 matches the base 5 .
[0037] It can be understood that the above embodiments only express the preferred implementation methods of the utility model, and the descriptions thereof are relatively specific and detailed, but they cannot be understood as limiting the patent scope of the utility model. It should be pointed out that, for ordinary technicians in this field, without departing from the concept of the utility model, the above-mentioned technical features can be freely combined, and several deformations and improvements can be made, which all belong to the protection scope of the utility model. Therefore, all equivalent changes and modifications made to the scope of the claims of the utility model should fall within the scope of the claims of the utility model.
Claims
1. A sealing device for stirring and solidifying radioactive wet waste in a nuclear power plant barrel, characterized in that: include: A base (5), a dust cover (1), a lifting assembly and a supporting frame (7); The dust cover (1) is arranged on the base (5), the support frame (7) is sleeved on the dust cover (1), the lifting assembly comprises a fixing part (4) and an output element (2), the fixing part (4) is fixed on the base (5), the output element (2) is arranged on the fixing part (4), the output element (2) is provided with an output end, the output end of the output element (2) is connected to the support frame (7), the direction of the output end moves upward from the base (5), and an elastic sealing ring is provided on the upper part of the dust cover (1).
2. A sealing device for stirring and solidifying radioactive wet waste in a nuclear power plant according to claim 1, characterized in that: The output element (2) is a pneumatic unit, and the extended rod of the pneumatic unit is the output end.
3. A sealing device for stirring and solidifying radioactive wet waste in a nuclear power plant according to claim 2, characterized in that: The pneumatic unit is a cylinder with a guide rod.
4. A sealing device for stirring and solidifying radioactive wet waste in a nuclear power plant according to claim 3, characterized in that: The pneumatic unit further comprises a buffer, which is arranged at one end of the guide rod cylinder away from the extension rod.
5. The sealing device for stirring and solidifying radioactive wet waste in a nuclear power plant according to claim 1, characterized in that: There are at least two output elements (2), and the output elements (2) are evenly distributed and seated on the base (5).
6. The sealing device for stirring and solidifying radioactive wet waste in a nuclear power plant according to claim 1, characterized in that: The supporting frame (7) is a circular metal ring.
7. A sealing device for stirring and solidifying radioactive wet waste in a nuclear power plant according to claim 1, characterized in that: An exhaust port (6) is also provided below the base (5).
8. The sealing device for stirring and solidifying radioactive wet waste in a nuclear power plant according to claim 1, characterized in that: The dust cover (1) is made of metal fiber radiation-proof fabric.
9. The sealing device for stirring and solidifying radioactive wet waste in a nuclear power plant according to claim 1, characterized in that: The base (5) is circular, and the shape of the dust cover (1) matches that of the base (5).