CN214476451U - Drying barrel for drying radioactive wet waste of nuclear power station - Google Patents
Drying barrel for drying radioactive wet waste of nuclear power station Download PDFInfo
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- CN214476451U CN214476451U CN202022242017.1U CN202022242017U CN214476451U CN 214476451 U CN214476451 U CN 214476451U CN 202022242017 U CN202022242017 U CN 202022242017U CN 214476451 U CN214476451 U CN 214476451U
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Abstract
The utility model relates to a nuclear power station radioactive wet waste drying process technical field specifically discloses a drying barrel for drying nuclear power station radioactive wet waste. The drying barrel comprises a vertical ventilation column, a barrel body, a lower ventilation pore plate and an air inlet, wherein the lower ventilation pore plate is transversely arranged at the middle lower part of the inner space of the barrel body, the vertical ventilation column is vertically arranged on the lower ventilation pore plate, and the air inlet is formed in the barrel wall at the lower part of the barrel body. Because set up lower part vent hole board and vertical ventilation column in this drying barrel, the hot-air can be through even spreading the bucket inner space of air vent, effectively takes away the moisture of wet wastes material to promote the stoving effect, improved drying efficiency.
Description
Technical Field
The utility model belongs to the technical field of the wet waste material drying process of nuclear power station radioactivity, concretely relates to drying bucket for dry nuclear power station radioactive wet waste material.
Background
Radioactive wastes generated in the operation of nuclear power plants due to personnel and maintenance activities mainly comprise personal protective articles, scrapped tools and appliances subjected to radioactive pollution, equipment parts and the like. It also includes radioactive wet waste (containing a certain amount of free water), such as cotton, mostly as stain-removing wipes, shoe covers, labour protection supplies, etc. In order to meet the requirement that the volume of free liquid in a waste bag in safety standards (GB12711-2018) of low and medium level radioactive solid waste bags is less than 1% of the volume of solid waste, wet waste needs to be dried.
The original design of the second stage of Qinshan is that wet waste is directly put into a 200L steel drum for drying, and after moisture is removed, the waste is compressed and barreled. Because the cotton textile has strong heat insulation, the deep part of the waste steel drum can not be effectively heated after the top cotton textile is dried; in addition, because the steel drum is closed, the drying air flow can not effectively flow, so that the drying effect is poor, and the working efficiency is very low.
SUMMERY OF THE UTILITY MODEL
An object of the utility model is to provide a drying bucket for dry nuclear power station radioactive wet waste to promote the stoving effect, improve the drying efficiency of radioactive wet waste.
The technical scheme of the utility model as follows: a drying bucket for drying nuclear power station radioactive wet waste which characterized in that: the vertical ventilating device comprises a vertical ventilating column, a barrel body, a lower ventilating pore plate and an air inlet, wherein the lower ventilating pore plate is transversely arranged at the middle lower part of the inner space of the barrel body, the vertical ventilating column is vertically arranged on the lower ventilating pore plate, and the air inlet is formed in the barrel wall at the lower part of the barrel body.
A bottom conical water containing disc is transversely arranged in the space at the lower side of the air inlet in the barrel body.
And a hand-screwed drainage cock is arranged at the center of the conical water containing disc at the bottom.
A pair of heavy handles is symmetrically arranged at the upper middle part of the outer wall of the barrel body.
The vertical ventilation columns are of cylindrical structures, the number of the vertical ventilation columns is three, and the vertical ventilation columns are uniformly and vertically placed above the lower ventilation hole plate.
The air inlet is rectangular, six in number and evenly distributed around the periphery of the lower part of the barrel body.
The vertical ventilating column, the barrel body and the lower ventilating hole plate are all made of stainless steel.
The outer wall of the barrel body is provided with a plurality of circles of corrugated bulges.
The barrel body is of a cylindrical structure, and the volume of the barrel body is 200 liters.
The utility model discloses a show the effect and lie in: a drying bucket for dry nuclear power station radioactive wet waste, set up lower part vent hole board and vertical ventilation column in its staving, the hot-air can be through even spreading the bucket inner space of air vent, effectively takes away the moisture of wet waste, promotes stoving effect, improves drying efficiency.
Drawings
Fig. 1 is a perspective sectional view of a drying barrel for drying radioactive wet waste of a nuclear power station according to the present invention.
In the figure: 1. a vertical aeration column; 2. a heavy duty handle; 3. a barrel body; 4. a lower vent hole plate; 5. a water containing disc with a conical bottom; 6. screwing the drainage cock by hand; 7. and an air inlet.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and specific embodiments.
As shown in fig. 1, a drying barrel for drying radioactive wet waste of a nuclear power station comprises a vertical ventilation column 1, a barrel body 3, a lower ventilation pore plate 4 and an air inlet 7, wherein the barrel body 3 is cylindrical, the lower ventilation pore plate 4 is transversely arranged at the middle lower part of the inner space of the barrel body 3, a plurality of vertical ventilation columns 1 are vertically arranged on the lower ventilation pore plate 4, and a plurality of ventilation holes are respectively arranged on the lower ventilation pore plate 4 and the vertical ventilation columns 1; an air inlet 7 is formed in the barrel wall at the lower part of the barrel body 3, the number of the air inlets 7 is 4, and the air inlets 7 are rectangular and uniformly distributed around the periphery of the lower part of the barrel body 3 so as to facilitate hot air to rapidly and uniformly enter the barrel body 3; a bottom conical water containing disc 5 is transversely arranged in the space below an air inlet 7 in the barrel body 3, a cofferdam with a certain height is reserved at the bottom of the bottom conical water containing disc 5 and the barrel bottom, and a hand-screwed drainage cock 6 is arranged at the horizontal center of the bottom conical water containing disc 5 so as to drain condensed water out of the barrel; two symmetrical heavy handles 2 are arranged at the middle upper part of the outer wall of the barrel body 3.
Claims (7)
1. A drying bucket for drying nuclear power station radioactive wet waste which characterized in that: including vertical ventilation post (1), staving (3), lower part vent hole board (4) and air intake (7), wherein, lower part vent hole board (4) have transversely been put to the well lower part of staving (3) inner space, vertical ventilation post (1) has vertically been placed on lower part vent hole board (4), air intake (7) have been seted up to the bucket wall of staving (3) lower part, the flourishing water tray of bottom toper (5) have transversely been put to staving (3) inside air intake (7) downside space, the flourishing water tray of bottom toper (5) central point puts and is equipped with hand and twists drainage cock (6).
2. Drying vat for radioactive wet wastes of nuclear power plants according to claim 1, characterized in that: a pair of heavy handles (2) are symmetrically arranged at the upper middle part of the outer wall of the barrel body (3).
3. Drying vat for radioactive wet wastes of nuclear power plants according to claim 1, characterized in that: the vertical ventilation columns (1) are of cylindrical structures, are three in number and are uniformly and vertically placed above the lower ventilation hole plate (4).
4. Drying vat for radioactive wet wastes of nuclear power plants according to claim 1, characterized in that: the air inlets (7) are rectangular, are six in number and are uniformly distributed around the periphery of the lower part of the barrel body (3).
5. Drying vat for radioactive wet wastes of nuclear power plants according to claim 1, characterized in that: the vertical ventilation column (1), the barrel body (3) and the lower ventilation pore plate (4) are all made of stainless steel.
6. Drying vat for radioactive wet wastes of nuclear power plants according to claim 1, characterized in that: the outer wall of the barrel body (3) is provided with a plurality of circles of corrugated bulges.
7. Drying vat for radioactive wet wastes of nuclear power plants according to claim 1, characterized in that: the barrel body (3) is of a cylindrical structure, and the volume of the barrel body is 200 liters.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202022242017.1U CN214476451U (en) | 2020-10-10 | 2020-10-10 | Drying barrel for drying radioactive wet waste of nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202022242017.1U CN214476451U (en) | 2020-10-10 | 2020-10-10 | Drying barrel for drying radioactive wet waste of nuclear power station |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN214476451U true CN214476451U (en) | 2021-10-22 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202022242017.1U Active CN214476451U (en) | 2020-10-10 | 2020-10-10 | Drying barrel for drying radioactive wet waste of nuclear power station |
Country Status (1)
| Country | Link |
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| CN (1) | CN214476451U (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN116153548A (en) * | 2022-12-30 | 2023-05-23 | 江苏佳核新能源科技有限公司 | High-integrity container for medium-low-level radioactive waste and manufacturing mold thereof |
-
2020
- 2020-10-10 CN CN202022242017.1U patent/CN214476451U/en active Active
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN116153548A (en) * | 2022-12-30 | 2023-05-23 | 江苏佳核新能源科技有限公司 | High-integrity container for medium-low-level radioactive waste and manufacturing mold thereof |
| CN116153548B (en) * | 2022-12-30 | 2024-03-26 | 江苏佳核新能源科技有限公司 | High-integrity container for medium-low-level radioactive waste and manufacturing mold thereof |
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