Radioactive waste treatment method and system and waste ventilation filter element crushing and packaging system
By treating the waste ventilation filter element into a glass substrate and melting plasma at high temperature with miscellaneous dry waste, the problems of cement fixed capacity increase and glass frit addition are solved, and the waste treatment cost reduction and capacity reduction effect are improved, and the pressure on nuclear facilities waste inventory is alleviated.
Patent Information
- Application Number
- CN202510646127.9
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-05-19
- Publication Date
- 2025-08-15
AI Technical Summary
In the prior art, the treatment of waste ventilation filter elements adopts cement fixation technology to increase capacity and increase the disposal pressure of radioactive solid waste. In the plasma high-temperature melting process, the addition of glass frit increases the volume of waste, affecting the capacity reduction effect.
The waste ventilation filter element is processed into a glass substrate and used as a raw material for high-temperature melting of plasma. Combined with miscellaneous dry waste, the addition of glass frit is reduced and the high-temperature melting and solidification of waste is achieved.
Effectively reduce waste treatment costs, improve capacity reduction effect, reduce waste inventory pressure in nuclear facilities, and promote the promotion of plasma high-temperature melting technology and waste minimization.
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Figure CN120496904A_ABST
Abstract
Description
Technical Field
[0001] The present invention specifically relates to a radioactive waste treatment method and system and a waste ventilation filter element crushing and packaging system. Background Art
[0002] Spent ventilation filters (also known as HVAC filters, hereinafter referred to as spent ventilation filters) are discarded filter materials removed from heating, ventilation, and air conditioning systems in radioactively controlled areas such as nuclear power plants and reprocessing plants. Ventilation filters are consumables and must be replaced when they reach replacement standards. These spent ventilation filters are a significant waste product at various nuclear power plants, and their radioactivity levels are generally very low. As nuclear facilities age, the number of spent ventilation filters increases annually, increasing inventory pressures and making the disposal of these spent ventilation filters a pressing issue.
[0003] With the continuous development of the nuclear power industry, the total amount of radioactive waste generated by the operation and decommissioning of nuclear power plants in the future will continue to increase. The research and development of high-volume and volume reduction treatment technologies for radioactive waste has become one of the main driving forces and challenges for nuclear safety.
[0004] Currently, dry waste such as spent ventilation filters is typically treated using compaction and cement fixation. This technology increases the volume of radioactive solid waste, which inevitably increases the disposal pressure. Therefore, research on new technologies for reducing the volume of radioactive waste is particularly urgent and of practical significance. Summary of the Invention
[0005] Plasma high-temperature melting technology has the advantages of a wide range of applications, fast reaction speed, low secondary pollution, small tail gas volume, and compact equipment. It can achieve the decomposition, gasification, and combustion of organic waste, the high-temperature melting of inorganic waste, and the solidification of radionuclides in a single system, significantly reducing the volume of waste and obtaining a stable final waste form. In short, plasma high-temperature melting technology is a technology that converts solid waste such as miscellaneous dry waste into a stable glass solid body or glass-like slag by adding glass frit. However, during the waste treatment process, it is still necessary to add glass frit at 10% to 20% of the total amount of materials entering the furnace to form glass-like slag. In other words, although the volume reduction effect is better than the cement fixation method, the addition of glass frit will still increase the volume of the waste to a certain extent, which has a certain negative impact on the minimization of radioactive waste.
[0006] The inventors of the present invention discovered that the ventilation filter media used in facilities such as nuclear power plants are mostly made of glass fiber. Glass fiber is an inorganic non-metallic material with excellent performance, made from glass balls and waste glass through processes such as high-temperature melting, drawing, winding, and weaving. A comparative analysis showed that the main components of waste ventilation filter media highly overlap with the glass material components used in existing plasma high-temperature melting process prototypes. Accordingly, the present invention processes waste ventilation filter media into a form that can be processed by the plasma high-temperature melting process, processes the waste ventilation filter media into a glass substrate, and processes it together with miscellaneous dry waste to reduce the addition of original glass material.
[0007] In summary, the technical problem to be solved by the present invention is to address the above-mentioned deficiencies in the prior art and provide a radioactive waste treatment method. This method is ingeniously designed, simple, and rationally designed. It reuses spent ventilation filter cartridges that would otherwise be cement-fixed, thereby reducing waste treatment costs and effectively improving waste volume reduction. The present invention also provides a radioactive waste treatment system and a system for crushing and packaging spent ventilation filter cartridges.
[0008] The present invention provides a method for treating radioactive waste, comprising the following steps:
[0009] Processing a waste ventilation filter element to obtain a glass substrate;
[0010] The glass frit containing the glass substrate is used to perform plasma high-temperature melting treatment on the miscellaneous dry waste to be processed to obtain glass-like slag.
[0011] Furthermore, the processing of the waste ventilation filter element to obtain the glass substrate specifically includes:
[0012] Disassemble the waste ventilation filter element to obtain the core body;
[0013] Crushing the core into a set size;
[0014] The crushed core is weighed and packaged to obtain a glass substrate.
[0015] The present invention also provides a radioactive waste treatment system, comprising: a waste ventilation filter element crushing and packaging system, used to process the waste ventilation filter element to obtain a glass substrate; a plasma high-temperature melting treatment system, connected to the waste ventilation filter element crushing and packaging system, used to use glass material containing the glass substrate to perform plasma high-temperature melting treatment on miscellaneous dry waste to be treated to obtain glass-like slag.
[0016] The present invention also provides a waste ventilation filter element crushing and packaging system, comprising: a disassembling device for disassembling the waste ventilation filter element to obtain a core body; a crushing device, connected to the disassembling device, for crushing the core body to a set size; a weighing and packaging device, connected to the crushing device, for weighing and packaging the crushed core body to obtain a glass substrate; the disassembling device, the crushing device and the weighing and packaging device are sequentially connected in series in front of the feed port of the plasma high-temperature melting treatment system to input the glass substrate into the plasma high-temperature melting treatment system as a processing substrate for the glass material used in the plasma high-temperature melting treatment.
[0017] Furthermore, the disassembly equipment includes a stamping device and a first conveying device, the stamping device is used to stamp the waste ventilation filter element to separate the core body of the waste ventilation filter element from the shell plate, and one end of the first conveying device is arranged below the stamping device, and the other end is arranged above the inlet of the crushing equipment for conveying the core body.
[0018] Furthermore, the disassembly equipment also includes a glove box, the stamping device is arranged inside the glove box, and the core body is discharged through the outlet of the glove box. The end of the first conveying device located below the stamping device is directly opposite to the outlet of the glove box. The external cover of the first conveying device is provided with a shielding cover, one end of the shielding cover is sealed to the outlet of the glove box, and the other end is sealed to the inlet of the crushing equipment.
[0019] Furthermore, in the shielding cover, the section connected to the inlet of the crushing equipment is a sealing section with a sloped bottom surface, and a sealing door is provided inside the shielding cover at the starting point of the slope of the sealing section. The sealing door is opened and closed between the sealing section and other sections of the shielding cover to separate the internal space of the glove box from the internal space of the crushing equipment.
[0020] Furthermore, the waste ventilation filter element crushing and packaging system also includes a gas processing device, which is connected to the internal space of the glove box, the sealing section and the weighing and packaging equipment, and is used to make the interior of the glove box, the sealing section and the weighing and packaging equipment a negative pressure environment relative to the atmospheric environment.
[0021] Furthermore, the crushing equipment includes a crusher and a second conveying device, the crusher is used to crush the core entering the crusher into a set size, the set size is not greater than 10cm×10cm; the second conveying device is connected between the outlet of the crusher and the inlet of the weighing and packaging equipment.
[0022] Furthermore, the weighing and packaging equipment includes a weighing device, a packaging device and a third conveying device. The weighing device is connected to the crushing device and is used to weigh the core fragments crushed by the crushing device. The packaging device is used to package the weighed core fragments. The third conveying device is used to transport the glass substrate obtained after packaging to the feed port of the plasma high-temperature melting processing system.
[0023] The radioactive waste treatment method of the present invention processes spent ventilation filter cartridges to obtain a glass substrate. Glass frit containing this glass substrate is then used to perform a plasma high-temperature melting treatment on miscellaneous dry waste to produce a glass-like slag. This radioactive waste treatment method not only consumes the spent ventilation filter cartridges themselves, but also uses the waste product as a raw material for treating other radioactive waste, reusing the spent ventilation filter cartridges that would otherwise be cement-fixed. This not only significantly reduces waste treatment costs for the spent ventilation filter cartridges, but also reduces the cost of the glass frit used in the plasma high-temperature melting treatment.
[0024] More importantly, both the input materials (miscellaneous dry waste) and the base materials of the treatment ingredients (the base material of the glass material is a glass base material) of the plasma high-temperature melting treatment process are radioactive wastes. Therefore, the volume increase of both types of radioactive wastes is reduced during the plasma high-temperature melting treatment. Therefore, during the treatment process, not only can the volume reduction effect of the plasma high-temperature melting process be further improved, but the volume reduction treatment of the waste ventilation filter element can also be achieved. This is of great significance for the promotion of plasma high-temperature melting technology and waste minimization, and can greatly alleviate the waste inventory and disposal pressure of nuclear facilities by quickly consuming the number of waste ventilation filters. BRIEF DESCRIPTION OF THE DRAWINGS
[0025] Figure 1 1 is a schematic diagram of a process for obtaining a glass substrate by treating radioactive waste in Example 1 of the present invention;
[0026] Figure 2 It is a structural diagram of the waste ventilation filter element crushing and packaging system in Example 3 of the present invention.
[0027] In the figure: 1. Disassembly equipment; 11. Glove box; 12. First conveyor; 13. Shielding cover; 131. Sealing section; 132. Sealing door; 2. Crushing equipment; 21. Crusher;
[0028] 22. Second conveying device; 3. Weighing and packaging equipment; 31. Weighing device; 32. Packing device; 33. Third conveying device; 4. Gas processing equipment. DETAILED DESCRIPTION
[0029] The following will be combined with the accompanying drawings to clearly and completely describe the technical solutions of the present invention. Obviously, the embodiments described are only some embodiments of the present invention, not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without making any creative efforts are within the scope of the present invention.
[0030] In the description of the present invention, it should be noted that the terms "upper" and "lower" and the like indicating directions or positional relationships are based on the directions or positional relationships shown in the accompanying drawings and are only for the convenience and simplification of the description. They do not indicate or imply that the device or element referred to must have a specific direction, be constructed and operated in a specific direction. Therefore, they should not be understood as limitations on the present invention.
[0031] In the description of the present invention, the terms “first”, “second” and “third” are used for descriptive purposes only and should not be understood as indicating or implying relative importance.
[0032] In the description of the present invention, it should be noted that, unless otherwise expressly specified or limited, the terms "connect," "dispose," "install," "fix," etc. should be understood in a broad sense. For example, they may refer to fixed connection, detachable connection, or integral connection; they may refer to direct connection, indirect connection through an intermediate medium, or internal communication between two components. Those skilled in the art will understand the specific meanings of the above terms in the present invention based on specific circumstances.
[0033] Example 1
[0034] The radioactive waste treatment method of this embodiment can adopt the treatment system of Example 2, and the method includes the following steps:
[0035] Processing a waste ventilation filter element to obtain a glass substrate;
[0036] The miscellaneous dry waste to be processed is subjected to plasma high-temperature melting treatment by using glass frit containing a glass matrix to obtain glass-like slag.
[0037] The radioactive waste treatment method of this embodiment not only consumes the waste ventilation filter element (also called waste ventilation filter element, or simply waste filter element) itself, but also uses the products of the waste ventilation filter element as raw materials to treat other radioactive wastes, and reuses the waste ventilation filter element that should have been fixed with cement. It not only drastically reduces the waste treatment cost of the waste ventilation filter element, but also reduces the cost of glass material used in plasma high-temperature melting treatment.
[0038] More importantly, the incoming materials and the base materials for the plasma high-temperature melting treatment process are both radioactive wastes. Therefore, the volume increase of both types of radioactive waste is reduced during the plasma high-temperature melting treatment. Therefore, during the treatment process, not only can the volume reduction effect of the plasma high-temperature melting process be further improved, but the volume reduction of the spent ventilation filters can also be achieved. This is of great significance for the promotion of plasma high-temperature melting technology and waste minimization. Furthermore, by rapidly consuming the number of spent ventilation filters, it can greatly alleviate the pressure on nuclear facility waste inventory and disposal. In the foregoing and following text, the treatment technology "plasma high-temperature melting" is a general term referring to an existing treatment technology for radioactive waste, so the "high temperature" therein does not refer to a specific temperature alone.
[0039] In this embodiment, the waste ventilation filter element is processed to obtain a glass substrate, specifically comprising:
[0040] Disassemble the waste ventilation filter element to obtain the core body;
[0041] Crushing the core to a set size;
[0042] The crushed cores are weighed and packaged to obtain a glass substrate.
[0043] The method of this embodiment cleverly utilizes the material properties of the waste filter element itself, reuses the waste material that originally required separate capacity expansion treatment, replaces a certain amount of required glass material, and reduces the amount of original glass material added.
[0044] The glass frit containing the glass substrate is a glass frit with the glass substrate as the main material. The glass substrate can be used as part or all of the material of the glass frit. When the glass substrate only partially replaces the original glass frit, other commonly used materials in the existing glass frit can be combined with the glass substrate as a feed package.
[0045] The set size of the core crushing can be specifically selected according to the miscellaneous dry waste to be processed. Specifically, a consistent set size range can be selected according to the original glass material size range required for plasma high-temperature melting of different miscellaneous dry wastes to perform core crushing.
[0046] After combining the waste ventilation filter element crushing and packaging system of Example 3, the specific process is as follows Figure 1As shown, the solid-line frame represents the object or product to be processed, the outer dashed-line frame represents the processing equipment, and the inner dashed-line frame represents the processing process. In this embodiment, the weighed and packaged glass substrate serves as the feed package for the plasma high-temperature melting process. Due to its disassembly and crushing, the feed package's parameters meet the feed requirements of the plasma high-temperature melting furnace and can replace some of the glass frit required for plasma high-temperature melting. This not only effectively treats spent ventilation filters generated by nuclear facility operations, but also further improves the operational economy and waste minimization of the plasma high-temperature melting process.
[0047] Example 2
[0048] The radioactive waste treatment system of this embodiment can be used to implement the treatment method of Example 1. The radioactive waste treatment system specifically includes:
[0049] A waste ventilation filter element crushing and packaging system is used to process the waste ventilation filter element to obtain a glass substrate; specifically, the waste ventilation filter element crushing and packaging system of Example 3 can be used;
[0050] The plasma high-temperature melting treatment system is connected to the waste ventilation filter element crushing and packaging system, and is used to use glass materials containing glass substrates processed from the waste ventilation filter elements to perform plasma high-temperature melting treatment on miscellaneous dry waste to be processed to obtain glass-like slag.
[0051] Example 3
[0052] The waste ventilation filter element crushing and packaging system of this embodiment is as follows: Figure 2 Shown, including:
[0053] Disassembling equipment 1, used to disassemble the waste ventilation filter element to obtain the core body;
[0054] Crushing equipment 2, connected to dismantling equipment 1, is used to crush the core to a set size;
[0055] The weighing and packaging device 3 is connected to the crushing device 2 and is used to weigh and package the crushed cores to obtain glass substrates;
[0056] The disassembling equipment 1, the crushing equipment 2 and the weighing and packaging equipment 3 are connected in series in front of the feed port of the plasma high-temperature melting treatment system in sequence, so as to input the glass substrate as the processing substrate of the glass material used in the plasma high-temperature melting treatment into the plasma high-temperature melting treatment system, while consuming the waste ventilation filter element, it can also process other miscellaneous dry waste.
[0057] The waste ventilation filter element crushing and packaging system of this embodiment can perform waste filter element disassembly, element crushing, element fragment weighing, and element fragment packaging. The waste filter element disassembly process is performed by disassembly equipment 1 (a waste filter element and filter material separation glove box); the element crushing process is performed by crushing equipment 2 (a waste filter element crushing device); and the element fragment weighing and element fragment packaging processes are performed by weighing and packaging equipment 3 (a waste filter element fragment weighing and packaging device).
[0058] The system of this embodiment pre-treats waste ventilation filter cartridges generated by nuclear facility operations to achieve crushing, weighing, and packaging of waste filter cartridge filter materials (cores), laying the foundation for volume reduction of waste filter cartridge filter materials, replacement of a certain proportion of currently required glass frit, and further improving the waste minimization level of plasma high-temperature melting technology.
[0059] In this embodiment, the disassembly apparatus 1 includes a stamping device and a first conveyor 12. The stamping device is used to stamp the waste ventilation filter element, separating the core from the shell. This stamping device can be implemented using conventional stamping equipment combined with conventional sorting components, and will not be described in detail here. One end of the first conveyor 12 is located below the stamping device and the other end is located above the inlet of the crushing device 2. It is used to transport the core from the stamping device to the crushing device 2.
[0060] In this embodiment, the disassembly equipment 1 also includes a glove box 11, and a punching device is arranged inside the glove box 11. The core material is discharged through the outlet of the glove box 11. The end of the first conveyor 12 located below the punching device is directly below the outlet of the glove box 11. The outer cover of the first conveyor 12 is provided with a shielding cover 13. One end of the shielding cover 13 is sealed to the outlet of the glove box 11, and the other end is sealed to the inlet of the crushing equipment 2. In this embodiment, the punching device in the glove box 11 can punch the core of the waste ventilation filter element, so that the core is separated from the metal shell plate. The filter material (core) is sent to the crushing equipment 2 through the first conveyor 12. The glove box 11 itself and the shielding cover 13 can prevent the aerosols and dust generated by the disassembly from being inhaled into the human body. In this embodiment, the exterior of the second conveyor 22 and the weighing and packaging equipment 3 (including the third conveyor 33) described below can be provided with a shielding structure similar to the glove box 11.
[0061] In this embodiment, the section of shielding cover 13 connecting to the entrance of crushing equipment 2 is a sealed section 131 with a sloped bottom surface. Inside shielding cover 13, a sealed door 132 is provided at the beginning of the slope of sealed section 131. Sealed door 132 is openably and closably positioned between sealed section 131 and the remaining sections of shielding cover 13, separating the interior of glove box 11 from the interior of crushing equipment 2. This separates glove box 11, or the area where the disassembly equipment 1 is performed, from the area where the crushing equipment 2 is performed, dividing the shielded environment into sections and further facilitating leak prevention.
[0062] In this embodiment, the waste ventilation filter element crushing and packaging system also includes a gas processing device 4, which is connected to the internal space of the glove box 11, the sealing section 131 and the weighing and packaging device 3, and is used to make the interior of the glove box 11, the interior of the sealing section 131 (or the interior of the crushing device 2 connected to the sealing section 131) and the weighing and packaging device 3 all present a negative pressure environment relative to the atmospheric environment. This micro-negative pressure environment can prevent radioactive impurities such as dust from operations such as core punching from escaping into the working environment. The specific gas processing equipment can adopt vacuum equipment such as fans, and butterfly valves can be set on the pipelines connected to each internal area to control the size of the negative pressure. Filters can also be set on the pipelines to filter impurities in the sucked gas.
[0063] In this embodiment, the crushing device 2 includes a crusher 21 and a second conveyor 22. The crusher 21 is used to crush the cores entering the crusher 21 into a set size, which is set to no larger than 10 cm x 10 cm. The second conveyor 22 is connected between the outlet of the crusher 21 and the inlet of the weighing and packaging device 3. The crushing device 2 in this embodiment has the technical performance of a sealed crushing chamber and low-speed crushing, and can tear the waste ventilation filter core into small pieces. The size of the crushed waste filter core after use is no larger than 10 cm x 10 cm.
[0064] In this embodiment, the weighing and packaging equipment 3 includes a weighing device 31, a packaging device 32, and a third conveyor 33. The weighing device 31 is connected to the crushing device 2 and is used to weigh the core fragments after being crushed by the crushing device 2. The packaging device 32 is used to package the weighed core fragments. The third conveyor 33 is used to transport the packaged glass substrate to the feed port of the plasma high-temperature melting processing system. Waste ventilation filter elements generated by nuclear facility operations are processed by the system's weighing and packaging equipment 3 to form waste filter element glass substrate feed packages. Any dimension (i.e., length, width, and height) of the waste filter element glass substrate feed package is no greater than 50 cm, and the processing capacity of waste ventilation filter elements generated by nuclear facility operations reaches 50 kg / h.
[0065] This embodiment belongs to the field of radioactive waste treatment technology, specifically a system for crushing and packaging spent ventilation filter cartridges for nuclear facilities. This system can perform waste filter cartridge disassembly, core crushing, core fragment weighing, and core fragment packaging processes. This system processes spent ventilation filter cartridges generated during nuclear facility operations into waste filter cartridge glass substrate feed packages. These waste filter cartridge glass substrate feed packages can be no larger than 500 mm in any dimension (i.e., length, width, and height), meeting the feed requirements of high-temperature plasma melting treatment systems used in nuclear facilities.
[0066] The system of this embodiment includes a waste filter element and filter material separation glove box (dismantling equipment 1), a waste filter element crushing device (crushing equipment 2) and a waste filter element fragment weighing and packaging device (weighing and packaging equipment 3); the waste filter element disassembly process is performed by the waste filter element and filter material separation glove box; the core body crushing process is performed by the waste filter element crushing device; the core body fragment weighing and core body fragment packaging processes are performed by the waste filter element fragment weighing and packaging device. Among them, the waste filter element and filter material separation glove box can perform a core punching operation on the waste ventilation filter element core to separate the core from the metal shell plate, and the filter material (core) is sent to the crusher 21 through the conveyor belt (first conveyor device 12). The glove box 11 is at a slightly negative pressure to ensure that the fly ash generated during the punching process does not escape into the environment; the waste filter element crushing device has the technical performance of crushing cavity sealing and low-speed crushing, and can tear the waste ventilation filter element core into small pieces. The size of the crushed waste filter element core is no more than 10cm×10cm, which is convenient for the waste filter element fragment weighing and packaging device to perform the core fragment weighing and core fragment packaging process; the waste filter element fragment weighing and packaging device has a capacity of processing waste ventilation filter elements generated by the operation of nuclear facilities up to 50kg / h, which can meet the feed requirements of plasma high-temperature melting technology.
[0067] It will be understood that the above embodiments are merely exemplary embodiments for illustrating the principles of the present invention, and the present invention is not limited thereto. Those skilled in the art will appreciate that various modifications and improvements can be made without departing from the spirit and substance of the present invention, and such modifications and improvements are also considered to be within the scope of protection of the present invention.
Claims
1. A method for treating radioactive waste, characterized in that: The following steps are involved: Processing a waste ventilation filter element to obtain a glass substrate; The glass frit containing the glass substrate is used to perform plasma high-temperature melting treatment on the miscellaneous dry waste to be processed to obtain glass-like slag.
2. The radioactive waste treatment method according to claim 1, characterized in that: The processing of the waste ventilation filter element to obtain the glass substrate specifically includes: Disassemble the waste ventilation filter element to obtain the core body; Crushing the core into a set size; The crushed core is weighed and packaged to obtain a glass substrate.
3. A radioactive waste treatment system, characterized in that: include: Waste ventilation filter element crushing and packaging system, used to process waste ventilation filter elements to obtain glass substrates; The plasma high-temperature melting treatment system is connected to the waste ventilation filter element crushing and packaging system, and is used to use glass material containing the glass substrate to perform plasma high-temperature melting treatment on the miscellaneous dry waste to be processed to obtain glass-like slag.
4. A waste ventilation filter element crushing and packaging system, characterized in that: include: Disassembling equipment (1) is used to disassemble the waste ventilation filter element to obtain the core body; A crushing device (2), connected to the dismantling device (1), is used to crush the core to a set size; A weighing and packaging device (3) is connected to the crushing device (2) and is used to weigh and package the crushed core to obtain a glass substrate; The disassembling device (1), the crushing device (2) and the weighing and packaging device (3) are sequentially connected in series in front of the feed port of the plasma high-temperature melting treatment system to input the glass substrate as the processing substrate of the glass material used in the plasma high-temperature melting treatment into the plasma high-temperature melting treatment system.
5. The waste ventilation filter element crushing and packaging system according to claim 4, characterized in that: The dismantling device (1) comprises a punching device and a first conveying device (12), The punching device is used to punch the waste ventilation filter element to separate the core of the waste ventilation filter element from the shell plate. One end of the first conveying device (12) is arranged below the punching device, and the other end is arranged above the inlet of the crushing device (2), for conveying the core body.
6. The waste ventilation filter element crushing and packaging system according to claim 5, characterized in that: The dismantling equipment (1) further includes a glove box (11), The punching device is arranged inside the glove box (11) and discharges the core through the outlet of the glove box (11). The end of the first conveying device (12) located below the punching device is directly below the outlet of the glove box (11). The outer cover of the first conveying device (12) is provided with a shielding cover (13), one end of the shielding cover (13) is sealed connected to the outlet of the glove box (11), and the other end is sealed connected to the inlet of the crushing device (2).
7. The waste ventilation filter element crushing and packaging system according to claim 6, characterized in that: In the shielding cover (13), the section connected to the inlet of the crushing device (2) is a sealing section (131) with a sloped bottom surface. A sealing door (132) is provided inside the shielding cover (13) at the beginning of the slope of the sealing section (131). The sealing door (132) is openably and closably arranged between the sealing section (131) and other sections of the shielding cover (13) to separate the internal space of the glove box (11) from the internal space of the crushing equipment (2).
8. The waste ventilation filter element crushing and packaging system according to claim 7, characterized in that: Also includes gas processing equipment (4), The gas processing equipment (4) is connected to the glove box (11), the sealing section (131) and the internal space of the weighing and packaging equipment (3). It is used to make the interior of the glove box (11), the interior of the sealing section (131), and the interior of the weighing and packaging equipment (3) all present a negative pressure environment with respect to the atmospheric environment.
9. The waste ventilation filter element crushing and packaging system according to claim 4, characterized in that: The crushing device (2) includes a crusher (21) and a second conveying device (22), The crusher (21) is used to crush the core entering the crusher (21) into a set size, and the set size is no larger than 10 cm×10 cm; The second conveying device (22) is connected between the outlet of the crusher (21) and the inlet of the weighing and packaging equipment (3).
10. The waste ventilation filter element crushing and packaging system according to claim 4, characterized in that: The weighing and packaging equipment (3) comprises a weighing device (31), a packaging device (32) and a third conveying device (33). The weighing device (31) is connected to the crushing device (2) and is used to weigh the core fragments after being crushed by the crushing device (2). The packing device (32) is used to pack the weighed core fragments. The third conveying device (33) is used to transport the packaged glass substrate to the feed port of the plasma high-temperature melting treatment system.
Citation Information
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