Shielding container and nuclear power plant solid waste transfer device

Abstract

The invention discloses a shielding container and a nuclear power plant solid waste transfer device.The shielding container comprises a shielding container body, the shielding container body comprises an outer shielding barrel, a lead filling structure and an inner shielding barrel, the outer shielding barrel and the inner shielding barrel are connected, a lead filling cavity is defined between the outer shielding barrel and the inner shielding barrel, and the lead filling cavity is filled with the lead filling structure; a cavity with an opening in the top end is formed in the inner side of the inner shielding barrel, and the cavity of the inner shielding barrel is suitable for containing a waste barrel; the density of the lead filling structure is larger than the density of the outer shielding barrel and the density of the inner shielding barrel. And the shielding container cover blocks the opening at the top end of the inner shielding barrel. The transfer risk of radioactive substances in the nuclear power plant is effectively solved, the operability of transportation is greatly improved, and reference is provided for subsequent transfer of fixed wastes in the nuclear power plant.

Description

Technical Field

[0001] This invention relates to the field of solid waste transfer technology for nuclear power plants, specifically to a shielded container and a solid waste transfer device for nuclear power plants. Background Technology

[0002] Highly radioactive waste is generated during the operation of nuclear power plants. After evaporation, concentration, ion exchange, drying, or cement fixation, it is packaged into 200L steel drums. Waste packages containing dried concentrated liquid, dried waste resin, and cement-fixed waste filter elements are transported to a radioactive solid waste temporary storage facility via in-plant transfer equipment for temporary decay. Steel drums with surface dose rates exceeding 2 mSv / h may be present. According to radiation protection requirements, shielding measures must be taken during transportation.

[0003] Nuclear power plants contain different types of units, and solid waste storage facilities are often shared by the entire plant and are built during the first reactor phase. Traditional transport shielding equipment is made entirely of carbon steel casting, resulting in large containers that affect the size of transport equipment. Furthermore, the transport equipment cannot meet the requirements of expanding room capacity due to the limited space of the existing facilities. Summary of the Invention

[0004] In view of this, the present invention provides a shielded container and a solid waste transfer device for nuclear power plants to solve the problem that traditional transport shielded equipment is made entirely of carbon steel casting, resulting in a large container size.

[0005] To achieve the above objectives, the technical solution adopted by the present invention is as follows:

[0006] In a first aspect, the present invention provides a shielding container, comprising:

[0007] The shielding container body includes an outer shielding barrel, a lead-filled structure, and an inner shielding barrel. The outer shielding barrel and the inner shielding barrel are connected and form a lead-filled cavity between them. The lead-filled structure is filled into the lead-filled cavity. The inner side of the inner shielding barrel is set as a cavity with an open top. The cavity of the inner shielding barrel is suitable for holding waste bins. The density of the lead-filled structure is greater than the density of the outer shielding barrel and the density of the inner shielding barrel, respectively.

[0008] A shielding container cover, which is placed at the top opening of the inner shielding barrel.

[0009] The beneficial effects of the above technical solution are as follows: the present invention effectively solves the risk of radioactive material transfer in nuclear power plants, greatly improves the operability of transportation, and provides a reference for the subsequent transfer of solid waste from nuclear power plants.

[0010] This invention employs a three-layer composite design consisting of an outer shielding bucket, a lead-filled structure, and an inner shielding bucket. The high-density characteristics of the lead-filled structure effectively enhance radiation shielding capabilities, ensuring that the surface dose rate of the waste bucket meets safety standards (≤2mSv / h) during transportation.

[0011] Compared to traditional shielding equipment made entirely of carbon steel, the lead-filled cavity design ensures shielding effectiveness while accommodating a denser lead structure inside, thus significantly reducing the overall volume. This solves the problem of transportation equipment being limited in size and unable to adapt to transport in confined spaces due to excessively large containers.

[0012] The inner shielded container's cavity design can directly hold a 200L standard waste container, and the sealing structure of the shielded container lid further ensures the sealing and safety during transportation, making it suitable for the scenario where multiple nuclear power plants share a temporary storage facility.

[0013] Further optimizing the technical solution, the wall thickness of the outer shielding bucket is 20mm; and / or, the wall thickness of the inner shielding bucket is 10mm; and / or, the wall thickness of the lead-filled structure is 140mm; and / or, the thickness of the shielding container cover is not less than 270mm.

[0014] To further optimize the technical solution, the outer shielding barrel and / or the inner shielding barrel and / or the shielding container cover are made of carbon steel.

[0015] The technical solution has been further optimized, and the density of the carbon steel is 7800 kg / m³. 3 The density of the lead-filled structure is 11300 kg / m³. 3 .

[0016] The beneficial effects of the above technical solution are as follows: the high density of the lead-filled structure allows it to achieve a radiation shielding effect superior to carbon steel of the same thickness with a thickness of only 140mm, without needing to increase the overall thickness to improve protection capabilities, thus indirectly supporting the compact design of the device. Compared to a pure carbon steel shielding solution, the lead-filled structure can achieve the same shielding effect with a thinner thickness, reducing the total amount of material used, lowering the overall weight of the device, and improving the load adaptability of the transport equipment.

[0017] To further optimize the technical solution, the shielding container cover is a double-layered, progressive trapezoidal bucket cover structure; the shielding container cover includes a shielding container cover body, a first plug, and a second plug. The shielding container cover body is placed on the top of the outer shielding bucket and surrounds part of the side wall of the outer shielding bucket. The first plug and the second plug are arranged from top to bottom at the bottom of the shielding container cover body. The outer diameters of the first plug and the second plug decrease sequentially from top to bottom, and the outer diameter of the bottom end face of the first plug is larger than the outer diameter of the top end face of the second plug.

[0018] The top of the inner shielding barrel is provided with a first groove and a second groove that are respectively connected to the cavity of the inner shielding barrel. The first plug is adapted to the first groove, and the second plug is adapted to the second groove.

[0019] The beneficial effects of the above technical solution are as follows: the progressive outer diameter design of the first and second plugs, combined with the double-layer groove of the inner shielding barrel, forms a stepped sealing structure, which not only increases the radiation shielding path length, but also improves the tightness of the connection between the shielding container cover and the shielding container body through physical fitting, effectively preventing the risk of leakage due to vibration during transportation.

[0020] The trapezoidal plug's outer diameter decreases from top to bottom, automatically guiding the cap and the center of the container to align during the sealing process. This reduces human error, improves the efficiency of rapid sealing in radioactive environments, and reduces the exposure time of operators.

[0021] The nested structure of the double-layer plug and groove disperses the pressure generated by the weight of the shielding container cover. The design of the outer shielding barrel sidewall being surrounded by the shielding container cover body further enhances the top support strength, avoids the risk of deformation due to material fatigue during long-term use, and improves the overall structural stability of the device.

[0022] To further optimize the technical solution, a positioning guide device is detachably installed inside the cavity of the inner shielding bucket. The positioning guide device is adapted to guide the waste bucket to slide into the cavity of the inner shielding bucket.

[0023] The beneficial effects of the above technical solution are as follows: the positioning and guiding device can guide the waste bin to slide into the cavity of the inner shielding bin along a preset path, reducing manual alignment operations. Especially in a radioactive environment, it can reduce the working difficulty and exposure time of operators, and improve loading efficiency. The positioning and guiding device ensures that the waste bin can be accurately lifted into the container during the hoisting process, achieving rapid centering. At the same time, it can play a role in positioning and protection during the transfer process.

[0024] To further optimize the technical solution, the positioning and guiding device is a barrel structure with an open top, and the top of the barrel structure is chamfered; and / or, the positioning and guiding device is made of polytetrafluoroethylene.

[0025] Secondly, the present invention also provides a nuclear power plant solid waste transfer device, comprising:

[0026] Shielding container;

[0027] Waste bins, the waste bins being adapted to store fixed waste.

[0028] To further optimize the technical solution, multiple lifting rings are provided on the outer wall of the shielding container cover, and multiple lifting interfaces are provided on the waste bin. The lifting rings and lifting interfaces have the same specifications.

[0029] The beneficial effects of the above technical solution are as follows: the lifting ring and the lifting interface have the same specifications, so a set of lifting tools can be used to lift 200L steel drums, saving time for changing lifting tools.

[0030] Further optimization of the technical solution also includes an automatic lifting device, which comprises:

[0031] A hook, the hook being adapted for connection to a crane;

[0032] The first lifting device is disposed at the bottom end of the hook and is adapted to grip the shielding container cover of the shielding container.

[0033] The second lifting device is located at the bottom end of the hook and is adapted to grip the waste bin. Attached Figure Description

[0034] To more clearly illustrate the specific embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the specific embodiments or the prior art will be briefly introduced below. Obviously, the drawings described below are some embodiments of the present invention. For those skilled in the art, other drawings can be obtained from these drawings without creative effort.

[0035] Figure 1 This is a schematic diagram of the structure of the nuclear power plant solid waste transfer device provided by the present invention.

[0036] Figure 2 This is a schematic diagram of the structure of the lid of the waste bin in the solid waste transfer device for nuclear power plants provided by the present invention.

[0037] Figure 3 The diagram shows the calculation results of the shielding container in the nuclear power plant solid waste transfer device provided by the present invention.

[0038] Figure 4 This is a schematic diagram of the structure of the automatic lifting device for the nuclear power plant solid waste transfer device provided by the present invention.

[0039] Figure label:

[0040] 1. Shielding container; 11. Shielding container cover; 111. First plug; 112. Second plug; 113. Shielding container cover body; 114. Lifting ring; 12. Outer shielding barrel; 13. Lead-filled structure; 14. Inner shielding barrel; 15. Positioning guide device.

[0041] 2. Waste bin;

[0042] 3. Automatic lifting device; 31. Hook; 32. First lifting device; 33. Second lifting device. Detailed Implementation

[0043] The technical solution of the present invention will now be clearly and completely described with reference to the accompanying drawings. Obviously, the described embodiments are only some, not all, of the embodiments of the present invention. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0044] In the description of this invention, it should be noted that the terms "center," "upper," "lower," "left," "right," "vertical," "horizontal," "inner," and "outer," etc., indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings. They are used only for the convenience of describing the invention and for simplifying the description, and 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. Therefore, they should not be construed as limitations on the invention. Furthermore, the terms "first" and "second" are used for descriptive purposes only and should not be construed as indicating or implying relative importance.

[0045] In the description of this invention, it should be noted that, unless otherwise explicitly specified and limited, the terms "installation," "connection," and "linking" should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral connection; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; and they can refer to the internal connection of two components. Those skilled in the art can understand the specific meaning of the above terms in this invention based on the specific circumstances.

[0046] Furthermore, the technical features involved in the different embodiments of the present invention described below can be combined with each other as long as they do not conflict with each other.

[0047] Nuclear power plants contain different types of units, and solid waste storage facilities are often shared by the entire plant and are established during the first reactor phase. Traditional transportation methods use shielding equipment made entirely of carbon steel castings, resulting in large containers that affect the size of transportation equipment. Furthermore, the transportation equipment cannot meet the requirements for expanding room capacity due to the limited space available for transfer.

[0048] Based on this, the present invention proposes a shielded container that can be used in situations where space is limited and transportation is impossible, while still meeting the requirements for future nuclear power applications.

[0049] The specific embodiments of the present invention will now be described in detail with reference to the nuclear power plant solid waste transfer device of the first aspect of the present invention.

[0050] According to an embodiment of the present invention, in a first aspect, a shielding container is provided, combined with Figures 1 to 4As shown, it includes the shielding container body and the shielding container cover 11.

[0051] The shielding container body includes an outer shielding barrel 12, a lead-filled structure 13, and an inner shielding barrel 14. The outer shielding barrel 12 and the inner shielding barrel 14 are connected and form a lead-filled cavity between them. The lead-filled structure 13 fills the lead-filled cavity. The inner side of the inner shielding barrel 14 is configured as a cavity with an open top, and the cavity of the inner shielding barrel 14 is suitable for holding the waste barrel 2. The density of the lead-filled structure 13 is greater than the density of both the outer shielding barrel 12 and the inner shielding barrel 14.

[0052] The shielding container cover 11 is sealed at the top opening of the inner shielding barrel 14.

[0053] The aforementioned shielding container employs a three-layer composite design consisting of an outer shielding barrel 12, a lead-filled structure 13, and an inner shielding barrel 14. The high-density characteristics of the lead-filled structure 13 effectively enhance radiation shielding capabilities, ensuring that the surface dose rate of the waste container meets safety standards (≤2mSv / h) during transportation.

[0054] Compared to traditional shielding equipment made entirely of carbon steel, the lead-filled cavity design ensures shielding effectiveness while housing a denser lead-filled structure 13 inside, thus significantly reducing the overall volume and solving the problem of transportation equipment being limited in size and unable to adapt to transport in confined spaces due to excessively large containers.

[0055] The inner shielded container's cavity design can directly hold a 200L standard waste container, and the sealing structure of the shielded container lid further ensures the sealing and safety during transportation, making it suitable for the scenario where multiple nuclear power plants share a temporary storage facility.

[0056] In some embodiments, the outer shielding barrel 12 has a wall thickness of 20 mm; and / or, the inner shielding barrel 14 has a wall thickness of 10 mm; and / or, the lead-filled structure 13 has a wall thickness of 140 mm; and / or, the shielding container cover 11 has a thickness of not less than 270 mm.

[0057] In one specific embodiment, to achieve a slimmer shielding container and to ensure that the dose rate level on the outer surface of the shielding container is ≤2 mSv / h and the dose rate at 2m from the outer surface is ≤0.1 mSv / h during transportation, the shielding container structure adopts a barrel body and bottom with an outer wall of 20mm carbon steel, an inner wall of 10mm carbon steel, and a 140mm lead filling in the middle; the shielding container cover 11 is made of carbon steel plate or forging, with a thickness of not less than 270mm. A schematic diagram of the lead filling structure is shown below. Figure 1 This ensures that the dimensions meet the relevant requirements.

[0058] The composite design of a 140mm thick lead-filled structure combined with a 20mm outer shield and a 10mm inner shield utilizes the high density of lead to form an efficient radiation barrier, which can stably control the surface dose rate of the waste container below the safe threshold (≤2mSv / h) and meet radiation protection requirements.

[0059] Compared to traditional full-body carbon steel shielding equipment, the shielding efficiency of the 140mm lead-filled layer is far higher than that of steel of the same thickness. Under the premise of ensuring the shielding effect, the total thickness of the composite structure (outer barrel + lead layer + inner barrel = 170mm) is significantly less than the thickness required for pure steel design, reducing the overall volume of the device and adapting to the transportation needs of the confined space in nuclear power plants.

[0060] The shielding container lid, with a thickness of ≥270mm, specifically enhances radiation protection in the vulnerable top area, avoiding the risk of dose rate exceeding the standard due to changes in orientation during transportation, and improving overall safety.

[0061] The wall thickness parameters of the outer and inner shielding barrels balance structural support strength with lightweight materials. The lead-filled structure is filled inside the cavity, which not only avoids the safety hazards of direct exposure of lead materials, but also ensures structural stability during long-term use through the constraint of the metal barrel.

[0062] The outer shielding barrel 12 and / or the inner shielding barrel 14 and / or the shielding container cover 11 are made of carbon steel.

[0063] More specifically, the density of carbon steel is 7800 kg / m³. 3 The density of lead-filled structure 13 is 11300 kg / m³. 3 The high density characteristics of lead-filled structures (11300 kg / m³) 3 This allows it to achieve radiation shielding performance superior to carbon steel of the same thickness with a thickness of only 140mm, without needing to increase the overall thickness to improve protection capabilities, indirectly supporting the compact design of the device. Compared to pure carbon steel shielding solutions, lead-filled structures can achieve the same shielding effect with a thinner thickness, reducing the total amount of material used, lowering the overall weight of the device, and improving the load adaptability of transportation equipment.

[0064] Based on the maximum source of waste, filter cartridges or dried salt must be packed into 200L steel drums and sealed, and then transferred to shielded containers for transport. The 200L steel drums have a wall thickness of 1.5mm, and the density of the carbon steel material is 7800kg / m³. 3 Considering the density of the lead-filled material is 11300 kg / m³ 3Considering that the shielding container consists of three parts—the body, the lid, and the bottom—and taking into full account the information of each waste source, and based on the assumption that one waste filter element is packed into each waste container, the volume reduction ratio of the concentrated liquid after drying is 8, and the volume reduction ratio of waste resin and waste activated carbon is 2, with a filling rate calculated at 100%, the outer wall of the body and bottom is made of 20mm thick carbon steel, the inner wall is made of 10mm thick carbon steel, and the lead filling thickness in the middle is 140mm. The top cover is made of carbon steel plate or forging, with a thickness of not less than 270mm. For specific thickness details, please refer to [link / reference needed]. Figure 2 .

[0065] In some embodiments, since the shielding container is highly radioactive, in order to minimize working time, the shielding container cover 11 is configured as a double-layered, progressive trapezoidal barrel cover structure.

[0066] The shielding container cover 11 includes a shielding container cover body 113, a first plug 111, and a second plug 112. The shielding container cover body 113 covers the top of the outer shielding barrel 12 and surrounds part of the side wall of the outer shielding barrel 12. The first plug 111 and the second plug 112 are arranged from top to bottom at the bottom of the shielding container cover body 113. The outer diameters of the first plug 111 and the second plug 112 decrease from top to bottom, and the outer diameter of the bottom end face of the first plug 111 is larger than the outer diameter of the top end face of the second plug 112.

[0067] The top of the inner shielding barrel 14 is provided with a first groove and a second groove that are respectively connected to the cavity of the inner shielding barrel 14. The first plug 111 is adapted to the first groove, and the second plug 112 is adapted to the second groove.

[0068] The upper part of the shielded container cover 11 is straight up and down to facilitate the sealing of the shielded container. The middle part is increased with a neck to facilitate the container body to support the container cover. The lower part is in the form of a bevel to facilitate the centering of the 200L steel drum during the insertion process. Based on the height of the 200L steel drum, considering the margin and loading capacity, the internal height is set at 940mm.

[0069] In this embodiment, the progressive outer diameter design of the first plug 111 and the second plug 112, combined with the double-layer groove of the inner shielding barrel, forms a stepped sealing structure, which not only increases the radiation shielding path length, but also improves the connection tightness between the shielding container cover 11 and the shielding container body through physical fitting, effectively preventing the risk of leakage due to vibration during transportation.

[0070] The trapezoidal plug's outer diameter decreases from top to bottom, automatically guiding the cap and the center of the container to align during the sealing process. This reduces human error, improves the efficiency of rapid sealing in radioactive environments, and reduces the exposure time of operators.

[0071] The nested structure of the double-layer plug and groove disperses the pressure generated by the weight of the shielding container cover 11. The design of the outer shielding barrel side wall being surrounded by the shielding container cover body further enhances the top support strength, avoids the risk of deformation due to material fatigue during long-term use, and improves the overall structural stability of the device.

[0072] In some embodiments, in order to achieve safety during hoisting and transportation, an internal and external positioning method is proposed. A positioning guide device 15 is detachably provided inside the cavity of the inner shielding bucket 14. The positioning guide device 15 is adapted to guide the waste bucket 2 to slide into the cavity of the inner shielding bucket 14.

[0073] In this embodiment, the positioning and guiding device guides the waste bin 2 along a preset path into the cavity of the inner shielding bin 14, reducing manual alignment operations. Especially in a radioactive environment, it reduces the difficulty of the operator's work and the exposure time, and improves loading efficiency. The positioning and guiding device ensures that the waste bin 2 can be accurately lifted into the container during the hoisting process, achieving rapid centering. At the same time, it can play a role in positioning and protection during the transfer process.

[0074] The guide structure ensures that the waste bin 2 is placed centered inside the inner shielding bin 14, avoiding insufficient local radiation shielding thickness due to misalignment and ensuring stable shielding performance (surface dose rate ≤2mSv / h).

[0075] The detachable design facilitates the individual inspection, replacement, or cleaning of the guide device, avoiding the need to disassemble the entire shielding container due to component damage, thus reducing maintenance costs and downtime.

[0076] If it is necessary to adapt to different sizes of waste bins in the future, quick adjustments can be made by replacing the positioning and guiding device, thereby enhancing the device's adaptability to diverse transportation needs.

[0077] More specifically, the positioning guide device 15 is a barrel structure with an open top, and the top of the barrel structure is chamfered. The chamfered top structure forms a smooth transition slope. When the waste bin 2 is placed from above, the chamfer can automatically correct minor alignment deviations, reduce rigid collisions between metal parts, reduce the need for manual adjustment, and improve the rapid loading efficiency in a radioactive environment.

[0078] The positioning and guiding device 15 is made of polytetrafluoroethylene (PTFE) and is used to position and protect the 200L steel drum, preventing it from tipping over or scratching the QR code during hoisting. PTFE has an extremely low coefficient of friction (static friction coefficient 0.04–0.1), which significantly reduces contact resistance during the sliding of the waste drum 2, minimizing the risk of scratches on the outer surface of the metal waste drum. Simultaneously, its excellent wear resistance (wear rate <0.01 mm³ / N·m) ensures the structural accuracy of the guiding device after long-term use, avoiding positioning deviations caused by frictional wear. PTFE has extremely strong corrosion resistance, withstanding the corrosion from acidic and alkaline waste liquids and radioactive aerosols that may be present in the nuclear power plant environment. Furthermore, its low attenuation coefficient for gamma rays and beta rays will not interfere with the radiation shielding performance of the inner shielding drum 14, ensuring that the overall surface dose rate of the device is controlled within a safe threshold (≤2 mSv / h).

[0079] Polytetrafluoroethylene (PTFE) maintains stable mechanical properties within a temperature range of -200°C to 260°C, making it suitable for the high-temperature operating conditions of nuclear facilities; its density is only 2.2 g / cm³. 3 Compared to metal guide structures, it can reduce the weight of the positioning device by about 60%, making it easier to disassemble and maintain manually and reducing the physical load in the radioactive area.

[0080] The non-stick properties of the polytetrafluoroethylene (PTFE) material prevent radioactive dust or debris from adhering, reducing the risk of cross-contamination; and no small molecules are released under long-term irradiation, meeting the cleanliness requirements of nuclear safety grade materials and avoiding secondary contamination of the surface of waste container 2.

[0081] According to an embodiment of the present invention, in a second aspect, a solid waste transfer device for a nuclear power plant is provided, comprising a shielded container 1 and a waste bin 2. The waste bin 2 is adapted to store fixed waste. The waste bin 2 includes a lid and a body.

[0082] In some embodiments, since the equipment weighs over ten tons, the strength of the lead layer cannot be guaranteed using traditional grooving processes. To address this issue, multiple lifting rings 114 are provided on the outer wall of the shielded container cover body 113. The waste bin 2 is provided with multiple lifting interfaces; details of the 200L bin cover lifting interface can be found [link to details]. Figure 3 To maximize efficiency in the shortest possible time, the lifting ring 114 is made to the same specifications as the lifting interface, allowing a single set of lifting tools to be used for lifting 200L steel drums, thus saving time on changing lifting tools.

[0083] A locking device is installed between the cover of the shielding container and the shielding container to ensure that the filter cartridge and the dry salt container can be effectively contained during transportation. Even if the transfer device is overturned, the cover of the shielding container will not fall off. At the same time, the cover and the shielding container body are provided with bolt holes and are fixed with pins.

[0084] A positioning block is installed on the outside of the shielded container 1 to fix and position it with the positioning device on the internal transfer device.

[0085] The shielded container lid is equipped with a remote automatic cap-sealing device, which includes an automatic lifting device 3, a crane, and other structures. This device enables the remote automatic cap-sealing of 200L steel drum lids and shielded container lids.

[0086] The automatic lifting device 3 includes a hook 31, a first lifting device 32, and a second lifting device 33. The hook 31 is adapted to be connected to a crane. The first lifting device 32 is located at the bottom end of the hook 31 and is adapted to grip the shielding container cover 11 of the shielding container 1. The first lifting device has a first gripper, which opens and closes when activated by a hydraulic cylinder or a pneumatic cylinder, thereby enabling the gripping and release of the shielding container cover 11. The second lifting device 33 is located at the bottom end of the hook 31 and is adapted to grip the waste bin 2. The second lifting device 33 has a second gripper, which opens and closes when activated by a hydraulic cylinder or a pneumatic cylinder, thereby enabling the gripping and release of the waste bin 2.

[0087] Furthermore, the second lifting device 33 can also be positioned below the hook 31 via a lifting structure. When the first lifting device clamps the shielding container cover 11, the second lifting device 33 can be raised to a clamping position away from the first lifting device via the lifting structure, thus avoiding interference from the first lifting device. When the second lifting device clamps the waste bin 2, the second lifting device can be lowered to a clamping position away from the first lifting device via the lifting structure, thus avoiding interference from the first lifting device.

[0088] When placing the waste bin 2, the waste bin 2 can be hoisted by the second lifting device 33 and then placed into the interior of the shielding container 1. Then, the shielding container cover 11 is placed at the opening of the shielding container body by the first lifting device 32 and the shielding container cover 11 is fixed to the shielding container body by bolts.

[0089] When removing the waste bin 2, the shielding container cover 11 is removed by the first lifting device 32, and then the waste bin 2 is lifted out of the shielding container 1 by the second lifting device 33.

[0090] Obviously, the above embodiments are merely illustrative examples for clear explanation and are not intended to limit the implementation. Those skilled in the art will recognize that other variations or modifications can be made based on the above description. It is neither necessary nor possible to exhaustively list all possible implementations here. However, obvious variations or modifications derived therefrom are still within the scope of protection of this invention.

Claims

1. A shielded container, characterized in that, Comprising: A shielding container body, which comprises an outer shielding barrel (12), a lead filling structure (13) and an inner shielding barrel (14), the outer shielding barrel (12) and the inner shielding barrel (14) are connected and a lead filling cavity is formed between them, the lead filling structure (13) is filled in the lead filling cavity, the inner side of the inner shielding barrel (14) is provided as a top opening cavity, the cavity of the inner shielding barrel (14) is suitable for containing a waste barrel (2); the density of the lead filling structure (13) is greater than the density of the outer shielding barrel (12) and the density of the inner shielding barrel (14) respectively; A shielding container cover (11) is sealed at the top opening of the inner shielding barrel (14).

2. The shielded container of claim 1, wherein, The wall thickness of the outer shielding barrel (12) is 20mm; and / or, the wall thickness of the inner shielding barrel (14) is 10mm; and / or, the wall thickness of the lead filling structure (13) is 140mm; and / or, the thickness of the shielding container cover (11) is not less than 270mm.

3. The shielded container of claim 1, wherein, The outer shielding barrel (12) and / or the inner shielding barrel (14) and / or the shielding container cover (11) is carbon steel.

4. The shielded container of claim 3, wherein, The carbon steel has a material density of 7800 kg / m 3 The leaded structure (13) has a material density of 11300 kg / m 3 .

5. The shielded container of claim 1, wherein, The shielding container cover (11) is a double-layer progressive trapezoidal barrel cover structure; the shielding container cover (11) comprises a shielding container cover body (113), a first plug (111) and a second plug (112), the shielding container cover body (113) covers the top end of the outer shielding barrel (12) and surrounds part of the side wall of the outer shielding barrel (12), the first plug (111) and the second plug (112) are arranged from top to bottom at the bottom end of the shielding container cover body (113), the outer diameters of the first plug (111) and the second plug (112) decrease in turn from top to bottom, and the bottom end face outer diameter of the first plug (111) is greater than the top end face outer diameter of the second plug (112); The top end of the inner shielding barrel (14) is provided with a first groove and a second groove which respectively communicate with the cavity of the inner shielding barrel (14), the first plug (111) is matched with the first groove, and the second plug (112) is matched with the second groove.

6. The shielded container of claim 1, wherein, A positioning guide device (15) is detachably arranged inside the cavity of the inner shielding barrel (14), and the positioning guide device (15) is suitable for guiding the waste barrel (2) to slide into the cavity of the inner shielding barrel (14).

7. The shielded container of claim 6, wherein, The positioning guide device (15) is a top opening barrel structure, and the top end of the barrel structure is provided with a chamfer; and / or, the material of the positioning guide device (15) is polytetrafluoroethylene.

8. A nuclear power plant solid waste transfer device, characterized by, Comprising: The shielding container (1) of any one of claims 1-7; A waste barrel (2) suitable for storing fixed waste.

9. The nuclear power plant solid waste transfer device of claim 8, wherein, A plurality of lifting rings (114) are arranged on the outer side wall of the shielding container cover (11), and a plurality of lifting interfaces are arranged on the waste barrel (2), and the lifting rings (114) and the lifting interfaces are of the same specification.

10. The nuclear power plant solid waste transfer device of claim 9, wherein, Further comprising an automatic lifting device (3), which comprises: A hook (31) suitable for being connected with a crane; A lifting ring (114) is arranged on the outer side wall of the shielding container cover (11), and a plurality of lifting interfaces are arranged on the waste barrel (2), and the lifting rings (114) and the lifting interfaces are of the same specification. - a first lifting tool (32) arranged at the bottom end of the hook (31), which first lifting tool (32) is adapted to grip the shielding container lid (11) of the shielding container (1); - a second lifting tool (33) arranged at the bottom end of the hook (31), which second lifting tool (33) is adapted to grip the waste barrel (2).

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