High-level waste shielding container
By designing a three-tiered structure and modular lead shielding layer in the high-level radioactive waste shielding container, the problems of heavy weight and inability to adjust the shielding layer were solved, achieving lightweight and flexible radiation protection.
Patent Information
- Application Number
- CN202520025671.7
- Authority / Receiving Office
- CN · China
- Patent Type
- Utility models(China)
- Current Assignee / Owner
- Filing Date
- 2025-01-06
- Publication Date
- 2026-01-13
- Estimated Expiration
- 2035-01-06
AI Technical Summary
Existing high-level radioactive waste shielding containers are heavy and the shielding layer cannot be adjusted according to different needs, increasing transportation costs and operational risks.
A high-level radioactive waste shielding container including a barrel body and a barrel lid was designed. The inner wall of the barrel body has three steps. The barrel lid and the barrel body are connected by reverse steps. Combined with a lead shielding layer and a covering layer, the outer side of the barrel body has an annular area to reduce weight. The lead shielding layer is made of lead plates stacked into a modular structure, which is convenient for installation and adjustment.
It achieves the goal of reducing container weight, lowering transportation costs, and improving operational safety while maintaining radiation protection effectiveness, and allows for adjustment of the shielding layer thickness to meet different radiation protection requirements.
Smart Images

Figure CN223797157U_ABST
Abstract
Description
Technical Field
[0001] This utility model belongs to the field of radioactive waste container technology, and in particular relates to a high-level radioactive waste shielding container. Background Technology
[0002] With the widespread application of nuclear technology in industry, medicine, and scientific research, the use of radioactive materials is becoming increasingly frequent. These materials generate potentially hazardous radioactive waste during use, including high-level radioactive waste (HRF). HRF primarily originates from HRF liquids and solidified forms generated during spent fuel reprocessing. The radionuclides contained in HRF are characterized by high radioactivity, high toxicity, long half-lives, and exothermic effects. Therefore, specially designed HRF shielding containers are required during handling and transportation.
[0003] Current high-level radioactive waste shielding containers typically consist of a lead-lined barrel and a sealable lid, designed to provide necessary radiation shielding. However, due to the need for thicker materials and denser shielding layers to meet radiation protection requirements, these containers are generally heavy, increasing transportation costs and potentially posing safety hazards during handling and hoisting, thus increasing operational complexity and risk. Furthermore, the shielding requirements for shielding containers vary depending on the type and intensity of radioactive waste. Therefore, shielding containers need to be adaptable to different needs to provide appropriate radiation protection. Utility Model Content
[0004] To address the problems existing in the prior art, this utility model aims to propose a high-level radioactive waste shielding container, which solves the problems of existing radioactive waste containers being too heavy and unable to adjust the shielding layer according to different needs.
[0005] To achieve the above objectives, the technical solution of this utility model is implemented as follows:
[0006] A high-level radioactive waste shielding container includes a barrel body and a barrel lid. The barrel body is hollow and the barrel lid is installed on the top. The inner wall of the barrel body is provided with three steps from top to bottom, and the barrel lid is provided with a reverse step that matches the steps on the barrel body.
[0007] Both the barrel body and the barrel lid include a lead shielding layer for shielding radiation emitted by radioactive materials and a covering layer covering the outside of the lead shielding layer. The upper and lower parts of the barrel body are respectively provided with annular areas not filled with the lead shielding layer near the outer edge.
[0008] Furthermore, the cross-section of the annular region is triangular.
[0009] Furthermore, the lead shielding layer inside the barrel is composed of several stacked lead plates.
[0010] Furthermore, the coating layer is made of carbon steel with a thickness of 14-16 mm.
[0011] Furthermore, the steps on the inner wall of the barrel are annular, and the three steps are stepped, namely the first step, the second step and the third step from top to bottom. The top of the barrel lid is installed on the first step, the middle is installed on the second step, and the bottom is installed on the third step.
[0012] Furthermore, the barrel body and the barrel lid are connected by bolts.
[0013] Furthermore, the top of the barrel is provided with a lifting ring for hoisting the barrel, and multiple lifting rings are evenly distributed on the top of the barrel.
[0014] Furthermore, a lifting plate is provided above the barrel body. The lifting plate is U-shaped and its two ends are respectively connected to a lifting ring.
[0015] Furthermore, there are two lifting plates, which are arranged in a cross shape above the barrel.
[0016] Furthermore, the top of the bucket lid is provided with a second lifting ring for hoisting the bucket lid, and multiple second lifting rings are evenly distributed on the top of the bucket lid.
[0017] Compared with existing technologies, the high-level radioactive waste shielding container of this invention has the following advantages:
[0018] (1) The high-radioactive waste shielding container of the present invention is placed in the inner cavity of the barrel. The barrel lid is fitted with the step of the barrel through the groove on it to ensure the sealing effect. At the same time, the lead shielding layer provides necessary radiation protection. The annular area between the inner wall and the outer wall of the barrel that is not filled with lead shielding layer reduces the weight of the container while maintaining the structural strength.
[0019] (2) The high-level radioactive waste shielding container of this utility model has a lead shielding layer made up of several lead plates stacked together, which provides effective radiation shielding, realizes modular design, facilitates installation and replacement, and the thickness of the lead shielding layer can be adjusted as needed to meet different radiation protection requirements. Attached Figure Description
[0020] The accompanying drawings, which form part of this utility model, are used to provide a further understanding of the utility model. The illustrative embodiments of the utility model and their descriptions are used to explain the utility model and do not constitute an undue limitation of the utility model. In the drawings:
[0021] Figure 1 A schematic diagram of the overall structure provided for an embodiment of this utility model;
[0022] Figure 2 for Figure 1 Sectional view of AA in the middle;
[0023] Figure 3 Top view of the overall structure provided for an embodiment of this utility model;
[0024] Figure 4 A schematic diagram of the barrel structure provided for an embodiment of this utility model;
[0025] Figure 5 for Figure 4 BB section view;
[0026] Figure 6 A schematic diagram of the bucket lid structure provided for an embodiment of this utility model;
[0027] Figure 7 for Figure 6 CC section view.
[0028] Explanation of reference numerals in the attached figures:
[0029] 1. Barrel body; 11. Annular area; 12. First step; 13. Second step; 14. Third step; 15. Lifting ring one; 16. Lifting plate; 17. Lifting step; 2. Barrel lid; 21. Bolt; 22. Lifting ring two; 3. Lead shielding layer inside the barrel; 31. Lead plate. Detailed Implementation
[0030] It should be noted that, unless otherwise specified, the embodiments and features described in these embodiments can be combined with each other.
[0031] In the description of this utility model, it should be understood that the terms "center," "longitudinal," "lateral," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," and "outer," etc., indicating the orientation or positional relationship, are based on the orientation or positional relationship shown in the accompanying drawings and are only for the convenience of describing this utility model and 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, and therefore should not be construed as a limitation of this utility model. Furthermore, the terms "first," "second," etc., are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of indicated technical features. Thus, a feature defined with "first," "second," etc., may explicitly or implicitly include one or more of that feature. In the description of this utility model, unless otherwise stated, "a plurality of" means two or more.
[0032] In the description of this utility model, it should be noted that, unless otherwise explicitly specified and limited, the terms "installation," "connection," and "joining" 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 utility model based on the specific circumstances.
[0033] The present invention will now be described in detail with reference to the accompanying drawings and embodiments.
[0034] like Figures 1 to 7 As shown, a high-level radioactive waste shielding container includes a barrel body 1 and a barrel cover 2. The barrel body 1 has a hollow inner cavity and the barrel cover 2 is installed on the top. The inner wall of the barrel body 1 is provided with three steps from top to bottom. The barrel cover 2 is provided with a reverse step that matches the steps on the barrel body 1.
[0035] Both the barrel body 1 and the barrel lid 2 include a lead shielding layer for shielding radiation emitted by radioactive materials and a covering layer covering the outside of the lead shielding layer. The upper and lower parts of the barrel body 1 are respectively provided with annular regions 11 that are not filled with lead shielding layer near the outer edge.
[0036] The high-level radioactive waste shielding container of this invention achieves sealing through the interaction of the steps on the inner wall of the barrel 1 and the reverse steps on the lid 2. A sealing ring can be set at the connection between the barrel 1 and the lid to enhance the sealing and stability of the container and prevent the leakage of radioactive materials.
[0037] A lead shielding layer is installed inside the container body 1 and the lid 2 to shield against radiation emitted by radioactive materials. The lead shielding layer provides necessary radiation protection, ensuring that the dose rate on the outer surface of the container meets safe transport standards. Lead, as an effective radiation shielding material, can significantly reduce the impact of radioactive materials on the environment and personnel.
[0038] In a preferred embodiment of this utility model, the cross-section of the annular region 11 is triangular.
[0039] In practical use, by setting annular areas 11 without lead shielding layer at the upper outer edge and the lower outer edge of the barrel 1, the overall weight of the container can be reduced. While maintaining the necessary shielding effect, the weight of the container is optimized, making it easier to transport and handle.
[0040] In a preferred embodiment of this utility model, the lead shielding layer 3 located inside the barrel is composed of a plurality of lead plates 31 stacked together.
[0041] In practical use, the lead shielding layer 3 located inside the barrel is composed of multiple lead plates 31 stacked layer by layer. By using stacked lead plates 31, the lead shielding layer 3 inside the barrel can achieve a modular design, facilitating installation and replacement. Furthermore, the size and shape of the lead shielding layer can be adjusted as needed to meet different radiation protection requirements, avoiding the problems associated with traditional lead casting processes. This reduces processing costs by 50% and weight by 20%, thus reducing lead pollution. The size and shape of the lead plates 31 are determined according to the size of the barrel. In this embodiment, the thickness of the lead plates 31 is preferably 100mm.
[0042] In a preferred embodiment of this utility model, the coating layer is made of carbon steel, and the thickness of the carbon steel is 14-16 mm.
[0043] In practical use, the carbon steel thickness is preferably 15mm, and the carbon steel is covered with a lead shielding layer so that the barrel body 1 and the barrel lid 2 can withstand various external forces that may be encountered during transportation and use, such as impact, pressure and vibration, ensuring the safe sealing of radioactive materials during transportation and preventing container damage and leakage of radioactive materials caused by external forces.
[0044] In a preferred embodiment of the present invention, the steps on the inner wall of the barrel 1 are annular, and the three steps are stepped, namely the first step 12, the second step 13 and the third step 14 from top to bottom. The top of the barrel lid 2 is installed on the first step 12, the middle part is installed on the second step 13, and the bottom is installed on the third step 14.
[0045] In practical use, the end of the second step 13 is chamfered. By matching the reverse step on the lid 2 with the step, the sealing and stability between the lid 2 and the body 1 are ensured. The three steps are designed in a stepped shape to prevent direct radiation emission. By changing the propagation path of the radiation, the scattering and absorption of radiation inside the container are increased, thereby improving the radiation shielding effect.
[0046] In a preferred embodiment of this utility model, the barrel body 1 and the barrel lid 2 are connected by bolts 21.
[0047] In practical use, the lid 2 is provided with bolt holes for mounting bolts 21, and the second step 13 of the barrel body 1 is provided with an internally threaded countersunk hole. The threaded end of the stud passes through the top of the lid 2 and is threadedly connected to the barrel body 1 at the second step 13, providing sufficient fastening force to ensure that the lid 2 will not loosen during transportation or use, improving the sealing between the barrel body 1 and the lid 2, and preventing the leakage of radioactive materials. Through multiple evenly distributed bolts, pressure is evenly applied to the lid 2, ensuring the sealing of the entire contact surface.
[0048] In a preferred embodiment of the present invention, the top of the barrel 1 is provided with a lifting ring 15 for hoisting the barrel 1, and a plurality of the lifting rings 15 are evenly distributed on the top of the barrel 1.
[0049] In practical use, the preferred number of lifting rings 15 is four. The lifting rings 15 are designed to connect to lifting equipment, such as the hooks of cranes or forklifts. Through these lifting rings 15, the barrel 1 can be safely lifted and moved. Multiple lifting rings 15 are evenly distributed on the top of the barrel 1 to ensure uniform force during lifting and avoid deformation or damage to the barrel 1 due to excessive local force.
[0050] In a preferred embodiment of this utility model, a lifting plate 16 is provided above the barrel body 1. The lifting plate 16 is U-shaped and its two ends are respectively connected to a lifting ring 15.
[0051] There are two lifting plates 16, which are arranged in a cross shape above the barrel body 1.
[0052] In actual use, the lifting plate 16 is U-shaped, with each end connected to a lifting ring 15. The two lifting plates 16 are arranged in a cross shape, which helps to evenly distribute the force during lifting, reduce the swaying and rotation of the barrel 1 during the lifting process, and ensure the smooth operation of the lifting.
[0053] The lower part of the barrel body 1 is provided with a hoisting step 17 for hoisting.
[0054] In a preferred embodiment of the present invention, the top of the bucket lid 2 is provided with a second lifting ring 22 for hoisting the bucket lid 2, and a plurality of the second lifting rings 22 are evenly distributed on the top of the bucket lid 2.
[0055] In practical use, the barrel lid 2 has a lead shielding layer inside, and the barrel lid 2 has mounting holes for installing lifting rings 22. The number of lifting rings 22 is preferably four. The design of the lifting rings 22 ensures the safety of the barrel lid 2 during the lifting process, preventing damage to the barrel lid 2 or leakage of radioactive materials due to improper lifting. The evenly distributed lifting rings 22 help improve the stability of the barrel lid 2 during the lifting process, reduce swaying of the barrel lid 2, and ensure a smooth lifting operation.
[0056] Working principle of high-level radioactive waste shielding containers:
[0057] The high-level radioactive waste is placed into the inner cavity of the container 1. Then, the lid 2 is placed on the container 1 by matching the step on the lid with the step on the container 1. The connection between the lid 2 and the container 1 is ensured by tightening the bolt 21, thereby ensuring a sealing effect.
[0058] The above description is only a preferred embodiment of the present utility model and is not intended to limit the present utility model. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of the present utility model should be included within the protection scope of the present utility model.
Claims
1. A high-level waste shielding container, comprising a barrel body (1) and a barrel cover (2), the barrel body (1) having a hollow inner cavity and a top portion mounting the barrel cover (2); characterized in that: the inner wall of the barrel body (1) is provided with three steps from top to bottom, and the barrel cover (2) is provided with reverse steps matching the steps on the barrel body (1); the barrel body (1) and the barrel cover (2) each comprise a lead shielding layer for shielding radiation emitted by radioactive substances and a cladding layer cladded outside the lead shielding layer, wherein the upper portion and the lower portion of the barrel body (1) are respectively provided with annular regions (11) not filled with the lead shielding layer near the outer edges.
2. A high level waste shielding container according to claim 1 characterised in that: The annular regions (11) are triangular in cross section.
3. A high level waste shielding container according to claim 1 characterised in that: The lead shielding layer (3) inside the barrel body is stacked by a plurality of lead plates (31).
4. The high-level waste shielding container of claim 1, wherein: The cladding layer is made of carbon steel with a thickness of 14-16 mm.
5. The high-level waste shielding container of claim 1, wherein: The steps of the inner wall of the barrel body (1) are annular and the three steps are ladder-shaped, comprising a first step (12), a second step (13) and a third step (14) from top to bottom, the top portion of the barrel cover (2) is mounted on the first step (12), the middle portion is mounted on the second step (13), and the bottom portion is mounted on the third step (14).
6. The high-level waste shielding container of claim 1, wherein: The barrel body (1) and the barrel cover (2) are connected by bolts (21).
7. The high-level waste shielding container of claim 1, wherein: The barrel body (1) is provided with a lifting ring I (15) for lifting the barrel body (1) on the top portion, and a plurality of lifting rings I (15) are uniformly distributed on the top portion of the barrel body (1).
8. A high level waste shielded container according to claim 7, characterised in that: The barrel body (1) is provided with a lifting plate (16) above, and the lifting plate (16) is U-shaped and connected with one lifting ring I (15) at each end.
9. A high level waste shielded container according to claim 8, characterised in that: The number of the lifting plate (16) is two, and the two lifting plates (16) are cross-shaped arranged above the barrel body (1).
10. The high-level waste shielding container of claim 1, wherein: The barrel cover (2) is provided with a lifting ring II (22) for lifting the barrel cover (2) on the top portion, and a plurality of lifting rings II (22) are uniformly distributed on the top portion of the barrel cover (2).