CN211628716U - Solid nuclear waste treatment device - Google Patents
Solid nuclear waste treatment device Download PDFInfo
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- CN211628716U CN211628716U CN201922334789.5U CN201922334789U CN211628716U CN 211628716 U CN211628716 U CN 211628716U CN 201922334789 U CN201922334789 U CN 201922334789U CN 211628716 U CN211628716 U CN 211628716U
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Abstract
The utility model provides a solid nuclear waste treatment device, including dissolving the cauldron, the filter house, supercritical oxidation cauldron, vapour and liquid separator and monitoring discharge tank, dissolving the cauldron and having water inlet and feed inlet, be equipped with catalyst box and ultraviolet generator in dissolving the cauldron, catalyst box is used for splendid attire catalyst medicine, ultraviolet generator is used for providing the ultraviolet ray, solid nuclear waste flows to the filter house after dissolving the cauldron and handling, flow to supercritical oxidation cauldron after filter house carries out filtration treatment, get the gas-liquid phase mixture after the mineralization treatment is carried out to supercritical oxidation cauldron, gas-liquid phase mixture flows to vapour and liquid separator and separates the back, the liquid phase flow is to the monitoring discharge tank, discharge after the jar detects up to standard through the monitoring. The solid nuclear waste treatment device can realize the efficient degradation of the solid nuclear waste, realize the effective volume reduction of the solid nuclear waste, and has the advantages of simple structure, small occupied area, reduced procedures, improved reuse rate of secondary waste liquid, low water consumption and reduced treatment cost of the solid nuclear waste.
Description
Technical Field
The utility model relates to a nuclear waste disposal technical field especially relates to a solid nuclear waste treatment device.
Background
In the operation and maintenance process of the nuclear power station, radioactive gas, liquid and solid wastes, referred to as three wastes for short, are generated, the annual output of the radioactive wastes, particularly the solid nuclear wastes, is gradually increased along with the increase of the unit operation time, and for the safety consideration, the recommended limit of the national nuclear facility supervision and control organization on the output of the solid nuclear waste goods package of an operation unitA value of 50m3Reactor year, much lower than the actual annual production of each nuclear power operating unit, it is seen that minimization of radioactive waste has become a serious task for each nuclear power plant.
The solid waste mainly comprises waste ion exchange resin, concentrated solution, waste filter element and other technical waste, wherein the majority of the waste is technical waste, and the output of the waste is up to 200 barrels/pile-year in a million kilowatt unit as an example, and the waste accounts for about 60 percent of the total volume of the radioactive goods bag. The main waste types are:
(1) compressible wastes (protective articles, plastic cloth, plastic bags, rags, gloves and the like) account for 70 percent of the total amount of the technical wastes, and are temporarily stored after being compressed;
(2) incompressible wastes with small radioactivity (metal blocks, small tools and metal pipes) account for 20 percent of the total amount of technical wastes, and are directly barreled without compression;
(3) the solid waste with strong radioactivity (the surface dose rate is more than or equal to 2mSv/h) accounts for 10 percent of the total amount of the technical waste, and is put into a concrete barrel for solidification.
For disposal of compressible waste, there are two conventional methods: one is mechanical compaction and transportation to a professional disposal plant for disposal, and the other is incineration, however, the bale density of the compressible waste after mechanical compaction is increased, and in addition, no on-site incineration disposal facility is built or planned in the nuclear power plant, which makes the conventional disposal of the compressible waste difficult to meet the current requirements.
Therefore, it is desirable to provide a solid nuclear waste disposal apparatus that addresses the above-mentioned deficiencies.
SUMMERY OF THE UTILITY MODEL
An object of the utility model is to provide a simple structure's solid nuclear waste processing apparatus can realize the high-efficient degradation of solid nuclear waste matter, finally turns into carbon dioxide and water, realizes the effective volume reduction of solid nuclear waste matter.
In order to realize the above-mentioned purpose, the utility model provides a solid nuclear waste treatment device, discharge the jar including dissolving cauldron, filter house, supercritical oxidation cauldron, vapour and liquid separator and monitoring, it has water inlet and feed inlet to dissolve the cauldron, be equipped with catalyst box and ultraviolet generator in the dissolution cauldron, the catalyst box is used for splendid attire catalyst medicine, ultraviolet generator is used for providing the ultraviolet ray, and solid nuclear waste warp flow direction after dissolving the cauldron and handling the filter house, warp the filter house flows to flow direction behind the filtration processing supercritical oxidation cauldron, warp the supercritical oxidation cauldron carries out the gas-liquid phase mixture after the mineralization treatment, gas-liquid phase mixture flow direction after vapour and liquid separator separates, the liquid phase flows to the monitoring discharge the jar, warp the monitoring discharge the jar and detect discharge after up to standard.
Compared with the prior art, the solid nuclear waste processing apparatus of this application, in the solid nuclear waste gets into the dissolving kettle through the feed inlet, the solvent can flow into the dissolving kettle from the water inlet in, the solvent can dissolve the solid nuclear waste in the dissolving kettle, but splendid attire catalyst medicine degrades the solid nuclear waste in the dissolving kettle with the cooperation oxidant in the catalyst box, ultraviolet generator can provide the ultraviolet ray and carry out the photolysis to the solid nuclear waste in the dissolving kettle, and introduce the oxidizing power that the ultraviolet ray can promote the oxidant. Therefore, the solid nuclear waste can be dissolved, degraded and photolyzed in the same dissolving kettle, the simplification of the device is realized, and the cost of the device is greatly reduced. The filtering part can be used for effectively removing radioactive particles in the solution. The supercritical oxidation is carried out by using a supercritical oxidation kettle, so that the organic solution is mineralized to be completely converted into carbon dioxide, water and inorganic salt. Utilize gas-liquid separator to separate the gas-liquid phase mixture, the gaseous phase result is discharged to the existing exhaust treatment system of nuclear power plant, and the liquid phase flows to monitoring discharge tank, process monitoring discharge tank detects and discharges after up to standard, and the gas after the processing is discharged to the existing gas treatment system of power plant, and the liquid after the processing is discharged to the existing waste liquid collecting system of power plant, need not increase extra gas, liquid treatment system. Therefore, the solid nuclear waste treatment device is simple in structure, small in occupied area, less in working procedures, capable of achieving efficient degradation of the solid nuclear waste, and finally converting the solid nuclear waste into carbon dioxide and water, and achieving effective volume reduction of the solid nuclear waste.
Preferably, the dissolving kettle is externally connected with an external circulating pump and a heat exchanger.
Preferably, the filtering part comprises a Y-shaped filter, a primary filter and a fine filter, and the solution flowing out of the dissolving kettle is sequentially treated by the Y-shaped filter, the primary filter and the fine filter.
Preferably, the filter pore size of the Y-type filter is 10-40 μm, the filter pore size of the primary filter is 5 μm, and the filter pore size of the fine filter is 0.25 μm.
Preferably, the catalyst box is detachably mounted in the dissolving kettle.
Preferably, the ultraviolet generator is detachably mounted in the dissolving kettle.
Preferably, a COD detector is arranged in the supercritical oxidation kettle.
Preferably, a radioactivity monitor and a pH direct-reading monitor are arranged in the monitoring discharge tank.
Preferably, a water outlet of the monitoring discharge tank is communicated with the water inlet of the dissolving kettle.
Preferably, a temporary storage tank is arranged between the filtering part and the supercritical oxidation kettle and is used for storing the solution processed by the filtering part so as to control the solution to enter the supercritical oxidation kettle in batches.
Drawings
FIG. 1 is a schematic structural view of the solid nuclear waste disposal apparatus of the present invention.
Description of the symbols:
the solid nuclear waste treatment device 100, the dissolving kettle 10, the water inlet 11, the feed inlet 12, the external circulating pump 13, the heat exchanger 14, the filtering part 20, the Y-shaped filter 21, the discharge pump 22, the primary filter 23, the fine filter 25, the supercritical oxidation kettle 30, the COD detector 31, the gas-liquid separator 40, the driving pump 41, the monitoring discharge tank 50, the radioactivity monitor 51, the pH direct reading monitor 53, the reuse water pump 55, the catalyst box 60, the ultraviolet generator 70 and the temporary storage tank 80.
Detailed Description
To explain technical solutions, structural features, and achieved technical effects of the present invention in detail, the following detailed description is given with reference to the accompanying drawings in conjunction with specific embodiments.
Referring to fig. 1, a solid nuclear waste treatment apparatus 100 of the present application includes a dissolving kettle 10, a filtering part 20, a supercritical oxidation kettle 30, a gas-liquid separator 40 and a monitoring discharge tank 50, the dissolving kettle 10 has a water inlet 11 and a feed inlet 12, a catalyst box 60 and an ultraviolet generator 70 are disposed in the dissolving kettle 10, the catalyst box 60 is used for holding catalyst drugs, the ultraviolet generator 70 is used for providing ultraviolet light, the solid nuclear waste flows to the filtering part 20 after being treated by the dissolving kettle 10, flows to the supercritical oxidation kettle 30 after being filtered by the filtering part 20, obtains a gas-liquid mixture after being mineralized by the supercritical oxidation kettle 30, the gas-liquid mixture flows to the gas-liquid separator 40 for separation, the liquid flows to the monitoring discharge tank 50, and is discharged after being detected by the monitoring discharge tank 50 to reach the standard.
Wherein the solid nuclear waste can be dissolved, degraded and photolyzed in the dissolving tank 10. In this embodiment, the solid nuclear waste is a solid polyvinyl alcohol material, but not limited thereto. Specifically, the solid nuclear waste enters the dissolving kettle 10 through the feed inlet 12, the solvent can flow into the dissolving kettle 10 from the water inlet 11, the solvent can dissolve the solid nuclear waste in the dissolving kettle 10, the catalyst box 60 can contain the catalyst medicine to cooperate with the oxidant to degrade the solid nuclear waste in the dissolving kettle 10, the ultraviolet generator 70 can provide ultraviolet light to photolyze the solid nuclear waste in the dissolving kettle 10, and the introduction of the ultraviolet light can promote the oxidizing capability of the oxidant. Therefore, the solid nuclear waste can be dissolved, degraded and photolyzed in the same dissolving kettle 10, so that the device is simplified, and the cost of the device is greatly reduced. Further, be equipped with heat preservation, thermocouple, relief valve in the dissolving kettle 10 to the temperature of solution in the better control dissolving kettle 10, dissolving kettle 10 is inside still to have the filtration grid. Furthermore, the dissolution kettle 10 is externally connected with an external circulating pump 13 and a heat exchanger 14, the external circulating pump 13 is used for conveying the solution in the dissolution kettle 10 to the heat exchanger 14 for heat exchange, and then the solution is conveyed back to the dissolution kettle 10 to adjust the temperature.
Referring to fig. 1, the catalyst box 60 is detachably installed in the dissolving tank 10, so that the catalyst box 60 can be replaced conveniently, the process of replacing the catalyst box 60 is simple, and the economy is improved. The ultraviolet generator 70 is detachably mounted in the dissolving kettle 10, so that the ultraviolet generator 70 is convenient to detach and replace, and engineering application is convenient. The ultraviolet generator 70 includes an ultraviolet lamp and a quartz casing wrapped on the surface of the ultraviolet lamp. Preferably, the wavelength of the ultraviolet light in the ultraviolet lamp tube is controlled to be 150 to 250nm, and preferably, the wavelength of the ultraviolet light is controlled to be 150 to 200 nm. Further, the ultraviolet generator 70 is installed at the lower portion of the dissolution tank 10 and below the catalyst box 60, thereby improving degradation efficiency.
With continued reference to fig. 1, the filtering portion 20 includes a Y-filter 21, a primary filter 23 and a fine filter 25, and the solution flowing out of the dissolving tank 10 is sequentially processed by the Y-filter 21, the primary filter 23 and the fine filter 25. That is to say, adopt tertiary nuclear level filter equipment to carry out filtration treatment to solution, can effectively remove radioactive particulate matter and ionic state nuclide in the solution. Further, the filter pore size of the Y-type filter 21 is 10 to 40 μm, the filter pore size of the primary filter 23 is 5 μm, and the filter pore size of the fine filter 25 is 0.25 μm. Further, a drain pump 22 is provided between the Y-filter 21 and the primary filter 23 to improve the filtering efficiency.
Referring to fig. 1, a COD detector 31 is disposed in the supercritical oxidation reactor 30 to detect the COD content in the solution. The radioactivity monitoring instrument 51 and the pH direct reading instrument 53 are arranged in the monitoring discharge tank 50. The radioactive activity monitor 51 is used for detecting the radioactive concentration of the liquid product, the pH direct-reading monitor 53 is used for detecting the pH of the liquid product, and the liquid product can be discharged after reaching the standard after being detected. Further, the delivery port of monitoring discharge tank 50 communicates in the water inlet 11 of dissolving kettle 10, that is to say, can flow into dissolving kettle 10 as the solvent as multiplexing rivers after detecting up to standard, and multiplexing water is the solution that adopts this application solid nuclear waste processing apparatus 100 to handle back and detect up to standard. Namely, the solvent can adopt a part of deionized water and reuse water, thereby reducing the discharge amount of secondary waste water, improving the reuse rate of secondary waste liquid, saving the solvent, reducing the using amount of water, having low water consumption and greatly reducing the treatment cost of solid nuclear waste. In the specific implementation process, when the radioactive concentration is less than 37Bq/L, the solid nuclear waste is used as reuse water to treat the next batch of solid nuclear waste, and if the radioactive concentration is more than or equal to 37Bq/L, the solid nuclear waste is discharged to an existing waste liquid treatment system of a power plant. Further, a multiplex water pump 55 may be provided to pump the solution reaching the detection standard into the dissolution tank 10, so as to improve the treatment efficiency. Further, a drive pump 41 may be provided between the gas-liquid separator 40 and the monitoring drain tank 50, and the liquid phase separated by the gas-liquid separator 40 may be flowed to the monitoring drain tank 50 by the drive pump 41 to increase the processing speed. Wherein, after the gas-liquid separator 40 separates the gas-liquid phase mixture, the gas phase product is discharged to the existing waste gas treatment system of the nuclear power plant, and the liquid phase product is discharged to the monitoring discharge tank 50.
Referring to fig. 1, a temporary storage tank 80 is disposed between the filter unit 20 and the supercritical oxidation reactor 30 for storing the solution processed by the filter unit 20 so as to be fed into the supercritical oxidation reactor 30 in batch control. That is, the solution filtered by the filtering unit 20 is temporarily stored in the temporary storage tank 80, and the solution in the temporary storage tank 80 is pumped into the supercritical oxidation reactor 30 in batches by controlling the water outlet switch of the temporary storage tank 80, so as to improve the processing efficiency and quality.
The working principle of the solid nuclear waste disposal apparatus 100 of the present application will be explained in detail with reference to fig. 1:
the solid nuclear waste enters the dissolving kettle 10 through the feed inlet 12, the solvent (ionized water and reuse water) and the oxidant flow into the dissolving kettle 10 from the water inlet 11, the catalyst is placed in the catalyst box 60 to heat the dissolving kettle 10 for dissolving and degrading, and the ultraviolet generator 70 is started to provide ultraviolet light to photolyze the solid nuclear waste in the dissolving kettle 10. After the solid nuclear waste is dissolved, degraded and photolyzed by the dissolving kettle 10, the solution flows into a Y-shaped filter 21, a discharge pump 22, a primary filter 23 and a fine filter 25 in sequence, and radioactive particles and ionic nuclides in the solution are effectively removed. The filtered solution flows into the temporary storage tank 80 for temporary storage, and the solution in the temporary storage tank 80 is pumped into the supercritical oxidation kettle 30 in batches by controlling the water outlet switch of the temporary storage tank 80. The solution is mineralized in the supercritical oxidation kettle 30 and then flows into the gas-liquid separator 40. After the gas-liquid separator 40 separates the gas-liquid phase mixture, the gas phase product is discharged to the existing waste gas treatment system of the nuclear power plant, and the liquid phase product is discharged to the monitoring discharge tank 50. The radioactivity concentration of the liquid product is detected by the radioactivity monitor 51, the pH of the liquid product is detected by the pH direct-reading monitor 53, and when the liquid product reaches the standard after detection, the liquid product is discharged or the solution reaching the standard is extracted by the multiplexing water pump 55 to flow into the dissolving kettle 10.
Compared with the prior art, the solid nuclear waste processing apparatus 100 of this application, solid nuclear waste gets into in the dissolving kettle 10 through feed inlet 12, the solvent can flow into dissolving kettle 10 in from water inlet 11, the solvent can dissolve the solid nuclear waste in dissolving kettle 10, can splendid attire catalyst medicine in catalyst box 60 degrades the solid nuclear waste in dissolving kettle 10 with the cooperation oxidant, ultraviolet generator 70 can provide the ultraviolet ray and carry out the photolysis to the solid nuclear waste in dissolving kettle 10, and introduce the oxidizing power that the ultraviolet ray can promote the oxidant. Therefore, the solid nuclear waste can be dissolved, degraded and photolyzed in the same dissolving kettle 10, so that the device is simplified, and the cost of the device is greatly reduced. The radioactive particles in the solution can be effectively removed by the filter unit 20. Supercritical oxidation is performed using the supercritical oxidation reactor 30 to mineralize the organic solution to completely convert into carbon dioxide, water and inorganic salts. Utilize vapour and liquid separator 40 to separate the gas-liquid phase mixture, the gas phase result is discharged to the existing exhaust treatment system of nuclear power plant, and liquid phase flow is to monitoring discharge tank 50, discharges after monitoring discharge tank 50 detects up to standard, and the gas after the processing is discharged to the existing gas treatment system of power plant, and the liquid after the processing is arranged to the existing waste liquid collecting system of power plant, need not increase extra gas, liquid treatment system. Therefore, the solid nuclear waste treatment device 100 has a simple structure, occupies a small area, reduces processes, can realize efficient degradation of the solid nuclear waste, and finally converts the solid nuclear waste into carbon dioxide and water, thereby realizing effective volume reduction of the solid nuclear waste.
The above disclosure is only a preferred embodiment of the present application and should not be taken as limiting the scope of the present application, so that the claims of the present application are covered by the appended claims.
Claims (10)
1. The utility model provides a solid nuclear waste processing apparatus, its characterized in that discharges the jar including dissolving cauldron, filter house, supercritical oxidation cauldron, vapour and liquid separator and monitoring, dissolving cauldron has water inlet and feed inlet, be equipped with catalyst box and ultraviolet generator in the dissolving cauldron, the catalyst box is used for splendid attire catalyst medicine, ultraviolet generator is used for providing the ultraviolet ray, and solid nuclear waste warp flow direction after dissolving cauldron and handling the filter house, the warp flow direction after the filter house carries out filtration treatment supercritical oxidation cauldron, the warp the supercritical oxidation cauldron carries out mineralization and obtains the gas-liquid phase mixture after handling, the gas-liquid phase mixture flow direction vapour and liquid separator separates the back, and the liquid phase flows to the monitoring discharges the jar, the warp the monitoring discharges the jar and detects discharge after up to standard.
2. The solid nuclear waste disposal apparatus of claim 1 wherein said dissolving tank is externally connected to an external circulation pump and heat exchanger.
3. The solid nuclear waste disposal apparatus of claim 1, wherein said filtering part comprises a Y-type filter, a primary filter and a fine filter, and the solution flowing out of said dissolving tank is sequentially treated by said Y-type filter, said primary filter and said fine filter.
4. The solid nuclear waste disposal apparatus of claim 3, wherein said Y-type filter has a filter pore size of 10 to 40 μm, said primary filter has a filter pore size of 5 μm, and said fine filter has a filter pore size of 0.25 μm.
5. The solid nuclear waste disposal apparatus of claim 1 wherein said catalyst cartridge is removably mounted within said dissolving tank.
6. The solid nuclear waste disposal apparatus of claim 1, wherein said ultraviolet generator is removably installed in said dissolving tank.
7. The solid nuclear waste disposal apparatus of claim 1, wherein a COD detector is provided in the supercritical oxidation reactor.
8. The solid nuclear waste disposal apparatus of claim 1, wherein the monitoring discharge tank is provided with a radioactivity monitor and a pH direct reading monitor.
9. The solid nuclear waste disposal apparatus of claim 1, wherein a water outlet of said monitor discharge tank is in communication with said water inlet of said dissolving tank.
10. The solid nuclear waste disposal apparatus of claim 1, wherein a temporary storage tank is provided between the filtering part and the supercritical oxidation reactor, for storing the solution processed by the filtering part, so as to control the solution to enter the supercritical oxidation reactor in batches.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201922334789.5U CN211628716U (en) | 2019-12-23 | 2019-12-23 | Solid nuclear waste treatment device |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201922334789.5U CN211628716U (en) | 2019-12-23 | 2019-12-23 | Solid nuclear waste treatment device |
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| CN211628716U true CN211628716U (en) | 2020-10-02 |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114005569A (en) * | 2021-10-29 | 2022-02-01 | 华能核能技术研究院有限公司 | Low-radioactivity organic waste liquid treatment system |
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- 2019-12-23 CN CN201922334789.5U patent/CN211628716U/en active Active
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114005569A (en) * | 2021-10-29 | 2022-02-01 | 华能核能技术研究院有限公司 | Low-radioactivity organic waste liquid treatment system |
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