CN211742681U - Radioactive solid waste shielding water wall - Google Patents
Radioactive solid waste shielding water wall Download PDFInfo
- Publication number
- CN211742681U CN211742681U CN201822046022.8U CN201822046022U CN211742681U CN 211742681 U CN211742681 U CN 211742681U CN 201822046022 U CN201822046022 U CN 201822046022U CN 211742681 U CN211742681 U CN 211742681U
- Authority
- CN
- China
- Prior art keywords
- shaped steel
- steel box
- solid waste
- radioactive solid
- shielding
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Images
Landscapes
- Buildings Adapted To Withstand Abnormal External Influences (AREA)
Abstract
The utility model relates to a radioactive solid waste handles technical field, specifically discloses a radioactive solid waste shielding waterwall, including L shaped steel case, Z shaped steel case and T shaped steel case, the three concatenation combination encloses into radioactive solid waste temporary storage area with building wall for the radioactive solid waste of keeping in. The utility model discloses shielding waterwall can shield, keep apart radioactive solid waste fast safely, and shielding waterwall's size can set up according to actual need, is convenient for process, dismantles and transports, low cost, safe and reliable.
Description
Technical Field
The utility model belongs to the technical field of radioactive solid waste handles, concretely relates to radioactive solid waste shielding waterwall.
Background
For radioactive solid waste, the treatment mode at home and abroad usually adopts the steps of barreling in a process plant, then sending the barreled solid waste to a solid waste conversion station for sorting, smelting and deeply burying the sorted metal waste, burning the sorted non-metal combustible waste and deeply burying the burned non-metal non-combustible waste, and compressing and deeply burying the sorted non-metal non-combustible waste.
Nuclear fuel reprocessing generates large quantities of solid waste with high levels of radioactivity during commissioning and production operations. Because of large volume and different shapes, the solid waste can not be directly loaded into a round solid waste barrel and then transferred to a production plant. And the production plant is not provided with a solid waste disintegration hot chamber, large pieces and non-circular radioactive solid wastes cannot be disintegrated one by one, and even if the large pieces and the non-circular radioactive solid wastes can be disintegrated, the solid waste conversion station cannot receive the large pieces and the non-circular radioactive solid wastes due to more quantity and types of the large pieces and the non-circular radioactive solid wastes.
Therefore, only radioactive solid wastes that cannot be barreled can be temporarily stored in the production plant. Because the radioactivity level is high, the radioactive solid waste can not be packed in a sealed bag as low-radioactivity solid waste and then accumulated in a certain idle area in a factory building to be provided with an isolation and warning board. To reduce the radioactivity level in the buffer and the exposure dose to the operators in the plant, radioactive solid waste shielding buffers must be provided. Typically, the use of lead sheath or brick is an effective method of shielding radioactive sources. However, the radioactive solid waste is large in volume and large in quantity, and the required storage space is usually dozens of cubes or hundreds of cubes. Therefore, the lead bricks or lead sheets are adopted for shielding, so that the using amount is too large, the price is high, the local bearing load of the floor slab is also greatly increased, and the requirement on the bearing of the floor slab is high. In addition, the support frame is required to be built, the lead shielding wall is built, the building and the dismantling are inconvenient, and the dismantling in the future also requires personnel to closely clean and decontaminate the lead block or the lead skin, so that the irradiation dose of the operating personnel is increased, and the like.
Disclosure of Invention
An object of the utility model is to provide a radioactive solid waste shielding waterwall satisfies radioactive solid waste shielding requirement of keeping in.
The technical scheme of the utility model as follows:
a radioactive solid waste shielding water wall comprises an L-shaped steel box, a Z-shaped steel box and a T-shaped steel box;
water injection ports are respectively arranged on the upper surfaces of the L-shaped steel box, the Z-shaped steel box and the T-shaped steel box;
injecting deionized water into the L-shaped steel box, the Z-shaped steel box and the T-shaped steel box through water injection ports;
lifting lugs are symmetrically arranged on the L-shaped steel box, the Z-shaped steel box and the T-shaped steel box respectively, so that the lifting lugs are convenient to hoist during transportation;
the L-shaped steel box is connected with a building wall body, the T-shaped steel box is used as a corner of the water wall, and the Z-shaped steel box forms a plane wall of the water wall.
And the water injection device also comprises a water injection plug matched with the water injection port.
The L-shaped steel box, the Z-shaped steel box and the T-shaped steel box are spliced and combined with the building wall to form a radioactive solid waste temporary storage area for temporarily storing radioactive solid waste.
The wall thickness of the L-shaped steel box, the Z-shaped steel box and the T-shaped steel box is 5-10 mm, and the wall thickness can be adjusted according to the weight of water.
The shielding thickness of the deionized water is calculated according to a radiation protection manual and in combination with the radioactivity level of the source item.
The beneficial effects of the utility model reside in that:
(1) the utility model discloses shielding waterwall can shield, keep apart radioactive solid waste fast safely.
(2) The utility model discloses the size of shielding water wall can set up according to actual need, is convenient for process, dismantles and transports, low cost, safe and reliable.
(3) Engineering application shows, will the utility model discloses shielding waterwall sets up in the good environment of ventilating and exhausting, can reduce gamma radioactivity to be less than or equal to 25 mu Sv/h's orange zone radioactivity control standard, has the shielding effect of good alpha, beta, gamma ray and neutron.
Drawings
FIG. 1 is a schematic view of a shield water wall structure;
FIG. 2 is a schematic view of an L-shaped steel box;
FIG. 3 is a schematic view of a Z-section steel box;
FIG. 4 is a schematic view of a T-section steel box;
fig. 5 is a schematic view of a water injection port plug.
In the figure: 1-L-shaped steel box; 2-Z-shaped steel boxes; 3-T-shaped steel boxes; 4-water injection port; 5-water injection hole plug; 6-lifting lugs; 7-a radioactive solid waste holding zone; 8-building a wall body.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and specific embodiments.
A radioactive solid waste-shielding waterwall as shown in FIG. 1 comprises an L-shaped steel box 1, a Z-shaped steel box 2 and a T-shaped steel box 3.
As shown in fig. 2 to 4, water injection ports 4 are respectively formed on the upper surfaces of the L-shaped steel box 1, the Z-shaped steel box 2 and the T-shaped steel box 3. As shown in fig. 5, a water filling port plug 5 is provided to be mated with the water filling port 4.
And deionized water is injected into the L-shaped steel box 1, the Z-shaped steel box 2 and the T-shaped steel box 3 through a water injection port 4. The shielding thickness of the deionized water is calculated according to a radiation protection manual and in combination with the radioactivity level of the source item. When the shielding water wall is dismantled, a liquid siphon method is adopted, and deionized water in the L-shaped steel tank 1, the Z-shaped steel tank 2 and the T-shaped steel tank 3 is completely emptied by using hoses through the water injection ports 4.
The wall thickness of the L-shaped steel box 1, the Z-shaped steel box 2 and the T-shaped steel box 3 is 5-10 mm, and the wall thickness can be adjusted according to the weight of water.
L shaped steel case 1, Z shaped steel case 2 and T shaped steel case 3 go up respectively the symmetry and be equipped with lug 6, hoist when being convenient for transport.
The L-shaped steel box 1 is connected with the building wall body 1, the T-shaped steel box 3 is used as a corner of the water wall, and the Z-shaped steel box 2 forms a plane wall of the water wall. L shaped steel case 1, Z shaped steel case 2 and the 3 concatenation combinations of T shaped steel case enclose radioactive solid waste temporary storage area 7 with building wall 1 for the radioactive solid waste of temporary storage.
Claims (5)
1. A radioactive solid waste shielding waterwall, characterized in that: comprises an L-shaped steel box (1), a Z-shaped steel box (2) and a T-shaped steel box (3);
water injection ports (4) are respectively arranged on the upper surfaces of the L-shaped steel box (1), the Z-shaped steel box (2) and the T-shaped steel box (3);
injecting deionized water into the L-shaped steel box (1), the Z-shaped steel box (2) and the T-shaped steel box (3) through a water injection port (4);
lifting lugs (6) are symmetrically arranged on the L-shaped steel box (1), the Z-shaped steel box (2) and the T-shaped steel box (3) respectively, so that the lifting lugs are convenient to hoist during transportation;
the L-shaped steel box (1) is connected with a building wall body, the T-shaped steel box (3) is used as a corner of the water wall, and the Z-shaped steel box (2) forms a plane wall of the water wall.
2. The radioactive solid waste shielding waterwall of claim 1, wherein: and the water injection device also comprises a water injection plug (5) which is matched with the water injection port (4).
3. The radioactive solid waste shielding waterwall of claim 2, wherein: l shaped steel case (1), Z shaped steel case (2) and T shaped steel case (3) concatenation combination and building wall enclose radioactive solid waste temporary storage area (7) for the temporary storage of radioactive solid waste.
4. A radioactive solid waste shielding waterwall as recited in claim 3, wherein: the wall thickness of the L-shaped steel box (1), the Z-shaped steel box (2) and the T-shaped steel box (3) is 5-10 mm, and the wall thickness can be adjusted according to the weight of water.
5. The radioactive solid waste shielding waterwall of claim 4, wherein: the shielding thickness of the deionized water is calculated according to a radiation protection manual and in combination with the radioactivity level of the source item.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201822046022.8U CN211742681U (en) | 2018-12-06 | 2018-12-06 | Radioactive solid waste shielding water wall |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201822046022.8U CN211742681U (en) | 2018-12-06 | 2018-12-06 | Radioactive solid waste shielding water wall |
Publications (1)
Publication Number | Publication Date |
---|---|
CN211742681U true CN211742681U (en) | 2020-10-23 |
Family
ID=72848908
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201822046022.8U Active CN211742681U (en) | 2018-12-06 | 2018-12-06 | Radioactive solid waste shielding water wall |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN211742681U (en) |
-
2018
- 2018-12-06 CN CN201822046022.8U patent/CN211742681U/en active Active
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN106531266B (en) | Spent fuel transfer passage shielding device | |
CN103345951A (en) | (U, np) O2transmutation fuel pellet and target preparation process | |
Romanato | Advantages of dry hardened cask storage over wet storage for spent nuclear fuel | |
CN211742681U (en) | Radioactive solid waste shielding water wall | |
CN203673837U (en) | Radwaste solidified body containing container | |
CN204966068U (en) | Pollution -free and easy -to -use well high level waste deals with container | |
CN104347146A (en) | Nuclear power station high-dose-rate compressible maintenance waste disposal method | |
JP2015004555A (en) | Method of retrieving fuel debris from boiling water nuclear plant and work house system | |
CN102855952A (en) | Low-activity waste radioactive source reorganizing device and method thereof | |
You et al. | Design and construction of an advanced spent fuel conditioning process facility (ACPF) | |
CN208111102U (en) | A kind of storage container after detector containing high-enriched uranium is retired | |
CN212724747U (en) | Integrated shielding container for transporting and storing out-of-pile nuclear measurement intermediate range detector | |
van Leeuwen | Radioactive waste management-future CO 2 emissions | |
CN215600101U (en) | Transportation device for activated secondary neutron source | |
CN201166993Y (en) | Bucket type protecting device for feeding charge into a neutron source stick | |
CN107068220A (en) | It is a kind of to realize the criticality safety control method that nuclear fuel densification is placed | |
Wang et al. | Study of the Regular Pattern Between the Geometric Characteristics of Radioactive Package and Its External Radiation Dose Rate | |
Morris et al. | Contingency options for the dry storage of Magnox spent fuel in the UK | |
Yang et al. | The Dose Constraint Calculation of High Radioactivity Level Waste Canister Surface | |
CN118588336A (en) | Radioactive shielding structure and method for pressurized water reactor spent fuel off-stack storage operation | |
Yoshino | Tokai-1 Decommissioning Project: The First Challenge in Japan | |
Quapp | DUCRETE TM Shielding Applications in the Yucca Mountain Repository | |
Stepennov | Gremikha Project: Plans for handling CPS rods from VVR submarines at the Gremikha Division of NWC “SevRAO”–RosRAO Branch and their removal to the Regional Center for Conditioning and Long-term Storage of Radioactive Waste in Saida Bay. Agenda item 3.3 (Presentation in English) | |
Romanato | Safe advantage on dry interim spent nuclear fuel storage | |
Hillebrand et al. | Concept for dismantling the reactor vessel and the biological shield of the compact sodium cooled nuclear reactor facility (KNK) |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
GR01 | Patent grant | ||
GR01 | Patent grant |