CN204695795U - Spent Radioactive liquid processing device - Google Patents
Spent Radioactive liquid processing device Download PDFInfo
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- CN204695795U CN204695795U CN201520453779.2U CN201520453779U CN204695795U CN 204695795 U CN204695795 U CN 204695795U CN 201520453779 U CN201520453779 U CN 201520453779U CN 204695795 U CN204695795 U CN 204695795U
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- vaporization chamber
- waste liquid
- radioactive liquid
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- liquid processing
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Abstract
一种放射性废液处理装置，解决目前放射性废液处理中的中低放废液减容和高放废液固化问题，本设计主要由喷雾装置、蒸汽加热装置、电辅助加热装置和双层包壳结构构成，通过将中低放废液进行喷雾热解方式进行蒸发减容，增大液体比表面积以提高蒸发效率，利用核电站发电过程产生的高温高压蒸汽对系统提供能量，从而达到节能目的；本设计为内外双层安全结构，采用负压设计，将蒸发室用高压包裹起来，以防止废液和废气在处理过程泄漏；本设计合理利用核设施产生的高温高压蒸汽及其它相应的资源，并预计将该装置应用于实际的放射性废液处理生产线中，节能、安全、高效、实用。
A radioactive waste liquid treatment device, which solves the problems of medium and low-level waste liquid volume reduction and high-level waste liquid solidification in the current radioactive waste liquid treatment. This design mainly consists of a spray device, a steam heating device, an electric auxiliary heating device and a double-layer bag The shell structure is used to evaporate and reduce volume by spraying and pyrolyzing medium and low-level radioactive waste liquid, increasing the specific surface area of the liquid to improve evaporation efficiency, and using the high-temperature and high-pressure steam generated during the power generation process of nuclear power plants to provide energy for the system, so as to achieve the purpose of energy saving; This design is a double-layer safety structure inside and outside. It adopts negative pressure design and wraps the evaporation chamber with high pressure to prevent leakage of waste liquid and waste gas during the treatment process. This design makes reasonable use of high-temperature and high-pressure steam and other corresponding resources generated by nuclear facilities And it is expected to apply the device in the actual radioactive waste liquid treatment production line, which is energy-saving, safe, efficient and practical.
Description
Technical field
The utility model relates to a kind of Spent Radioactive liquid processing device, and specifically a kind of energy-conservation, safe, efficient Spent Radioactive liquid processing device, belongs to Application of Nuclear Technology field.
Background technology
Along with international nuclear safety more and more comes into one's own, the civilian nuclear industry of national defence all creates a large amount of radioactive liquid wastes, and it is one of subject matter of the current nuclear industry Faced In Sustainable Development of China that the process of these radioactive liquid wastes is disposed.The scale of construction of the middle low radioactive waste liquid of current China is comparatively large, and the major way taked is that evaporation subtracts appearance, and mainly take the evaporation of extensive style to subtract appearance flow process, energy consumption is high, security is low.High activity liquid waste, due to self singularity, due in disaster environment, be very easily discharged in environment, soil boy structure disaster, and processing mode main at present carries out geological disposal after being cured.
Based on the needs of national nuclear safety and Nuclear energy development strategy, the process of radioactive waste is disposed and is related to its sustainable development, and wherein radioactive liquid waste not easily stores because of its mobility, is easy to volatilization, becomes the problem that need process in radioactive waste.For in the feature of low high activity liquid waste, take safety, process problem that energy-conservation technology solves Today radiation waste liquid be extremely urgent.
Summary of the invention
In order to make to subtract appearance for low radioactive waste liquid in current radioactive liquid waste process and this two problems of HLW-solidification is able to effective solution, the utility model provides a kind of Spent Radioactive liquid processing device.
The utility model solves the technical scheme that its technical matters adopts:
Spent Radioactive liquid processing device, is formed primarily of spraying plant, steam heater, electric auxiliary heating device and double-deck containment structure.
Spraying plant: be made up of radioactive liquid waste process pipeline, high-pressure gas pipelines, exhaust-gas treatment pipeline and atomization of liquid shower nozzle, a part and the atomization of liquid shower nozzle of described pipeline are all positioned at vaporization chamber;
Steam heater: high temperature and high pressure steam pipeline, high temperature and high pressure steam entrance is all connected with this facility with jet chimney outlet, and high temperature and high pressure steam pipeline is in the shape of a spiral around vaporization chamber;
Electric auxiliary heating device: the resistance wire that can produce high heat, equally in the shape of a spiral around vaporization chamber, comprises the electric heater unit positive pole being placed in vaporization chamber top and the electric heater unit negative pole being placed in vaporization chamber bottom;
Double-deck containment structure: containing vaporization chamber involucrum and Spent Radioactive liquid processing device involucrum, described involucrum is all in cylindric;
Steam heater and electric auxiliary heating device are in the shape of a spiral around vaporization chamber involucrum, evaporation indoor temperature is raised, radioactive liquid waste via be positioned at evaporation chamber liquid dispensing apparatus the atomization of liquid shower nozzle atomization after, evaporation in vaporization chamber and concentrated, final product is stored in the waste collection pond below vaporization chamber;
Spent Radioactive liquid processing device involucrum, makes whole device be in sealing state by all parts enclose except the described entrance of part and outlet wherein; Exhaust-gas treatment lower end of duct is placed in vaporization chamber internal upper part, and exhaust-gas treatment pipe outlet is connected with the three-protection design system of nuclear facilities, and radioactive emission is by the three-protection design system process of nuclear facilities.
The beneficial effects of the utility model are: make that waste treatment process is more energy-conservation, efficient, safety, environmental protection, cost be low.The design uses high temperature and high pressure steam unnecessary in nuclear facilities (such as: nuclear power station), adopt the mode of spray pyrolysis effectively can improve the efficiency of liquid waste processing simultaneously, the rock that can be used for high activity liquid waste is solid, during underway low radioactive waste liquid evaporation and concentration, does not need extra power; And can, in high level liquid waste processing, be forerunner's firming body by high level liquid waste processing; The negative pressure screening energy adopted solves radiomaterial release, ensures the security of processing procedure; Exhaust treatment system, vapour system all can adopt the subsystem of present nuclear facilities, need not build corresponding disposal system again, saves the cost of liquid waste processing.The design takes double layer security structure, thus realizes the effective optimization process to radioactive liquid waste.
Accompanying drawing explanation
Below in conjunction with drawings and Examples, the present invention will be described further.
Fig. 1 is one-piece construction schematic diagram of the present utility model.
In figure: 1. radioactive liquid waste entrance, 1-1. radioactive liquid waste process pipeline, 2. jet chimney outlet, 3. Spent Radioactive liquid processing device involucrum, 4. atomization of liquid shower nozzle, 5. high temperature and high pressure steam entrance, 5-1. high temperature and high pressure steam pipeline, 6. high-pressure gas pipelines entrance, 6-1. high-pressure gas pipelines, 7. exhaust-gas treatment pipe outlet, 7-1. exhaust-gas treatment pipeline, 8. electric heater unit positive pole, 8-1. resistance wire, 9. vaporization chamber involucrum, 9-1. vaporization chamber, 10. electric heater unit negative pole, 11. waste collection ponds.
Embodiment
Spent Radioactive liquid processing device, as shown in Figure 1, is formed primarily of spraying plant, steam heater, electric auxiliary heating device and double-deck containment structure.
In figure, adopt inside and outside double-deck containment structure, be so more conducive to preventing radioactive liquid waste, waste gas from revealing.Described jet chimney gateway is connected with nuclear facilities system, whole device provides heat by the high temperature and high pressure steam in the described jet chimney of nuclear facilities generation inflow and described auxiliary electric heater unit, high temperature and high pressure steam pipeline and electric auxiliary heating device are in the shape of a spiral around vaporization chamber, radioactive liquid waste flows into from radioactive liquid waste entrance, atomization of liquid shower nozzle via liquid dispensing apparatus is atomized, so more be conducive to the evaporation of radioactive liquid waste in vaporization chamber and concentrated, final product is stored in waste collection pond.The waste gas produced in whole process is connected with the three-protection design system of nuclear facilities via exhaust-gas treatment pipe outlet, carries out last exhaust-gas treatment.
Be understandable that, above about specific descriptions of the present utility model, the technical scheme described by the utility model embodiment is only not limited to for illustration of the utility model, those of ordinary skill in the art is to be understood that, still can modify to the utility model or equivalent replacement, to reach identical technique effect; Needs are used, all within protection domain of the present utility model as long as meet.
Claims (3)
1. a Spent Radioactive liquid processing device, forms primarily of spraying plant, steam heater, electric auxiliary heating device and double-deck containment structure, it is characterized in that:
Spraying plant: be made up of radioactive liquid waste process pipeline, high-pressure gas pipelines, exhaust-gas treatment pipeline and atomization of liquid shower nozzle, a part and the atomization of liquid shower nozzle of described pipeline are all positioned at vaporization chamber;
Steam heater: high temperature and high pressure steam pipeline, high temperature and high pressure steam entrance is all connected with this facility with jet chimney outlet, and high temperature and high pressure steam pipeline is in the shape of a spiral around vaporization chamber;
Electric auxiliary heating device: the resistance wire that can produce high heat, equally in the shape of a spiral around vaporization chamber, comprises the electric heater unit positive pole being placed in vaporization chamber top and the electric heater unit negative pole being placed in vaporization chamber bottom;
Double-deck containment structure: containing vaporization chamber involucrum and Spent Radioactive liquid processing device involucrum, described involucrum is all in cylindric.
2. Spent Radioactive liquid processing device according to claim 1, is characterized in that: Spent Radioactive liquid processing device involucrum, and by all parts enclose outside entrance described in remove portion and outlet wherein, whole device is in sealing state.
3. Spent Radioactive liquid processing device according to claim 1, it is characterized in that: exhaust-gas treatment lower end of duct is placed in vaporization chamber internal upper part, exhaust-gas treatment pipe outlet is connected with the three-protection design system of nuclear facilities.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520453779.2U CN204695795U (en) | 2015-06-17 | 2015-06-17 | Spent Radioactive liquid processing device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520453779.2U CN204695795U (en) | 2015-06-17 | 2015-06-17 | Spent Radioactive liquid processing device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN204695795U true CN204695795U (en) | 2015-10-07 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201520453779.2U Expired - Fee Related CN204695795U (en) | 2015-06-17 | 2015-06-17 | Spent Radioactive liquid processing device |
Country Status (1)
| Country | Link |
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| CN (1) | CN204695795U (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105405485A (en) * | 2015-10-23 | 2016-03-16 | 西南科技大学 | Radioactive liquid waste treatment device |
| CN106803439A (en) * | 2015-11-26 | 2017-06-06 | 大亚湾核电运营管理有限责任公司 | Mobile purifier, Liquid Radwaste Treatment and method for nuclear power station |
| CN109073129A (en) * | 2016-10-28 | 2018-12-21 | 获劳动红旗勋章和Czsr劳动勋章的水压试验设计院联合股份公司 | Electric heating bath apparatus for decontamination |
| CN112607819A (en) * | 2020-12-18 | 2021-04-06 | 杭州景业智能科技股份有限公司 | Nuclear industry high-level radioactive waste liquid evaporation-calcination system and evaporation-calcination method |
-
2015
- 2015-06-17 CN CN201520453779.2U patent/CN204695795U/en not_active Expired - Fee Related
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105405485A (en) * | 2015-10-23 | 2016-03-16 | 西南科技大学 | Radioactive liquid waste treatment device |
| CN106803439A (en) * | 2015-11-26 | 2017-06-06 | 大亚湾核电运营管理有限责任公司 | Mobile purifier, Liquid Radwaste Treatment and method for nuclear power station |
| CN109073129A (en) * | 2016-10-28 | 2018-12-21 | 获劳动红旗勋章和Czsr劳动勋章的水压试验设计院联合股份公司 | Electric heating bath apparatus for decontamination |
| CN112607819A (en) * | 2020-12-18 | 2021-04-06 | 杭州景业智能科技股份有限公司 | Nuclear industry high-level radioactive waste liquid evaporation-calcination system and evaporation-calcination method |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20151007 Termination date: 20160617 |
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| CF01 | Termination of patent right due to non-payment of annual fee |