CN116153551B - Radioactive waste liquid treatment method and system - Google Patents
Radioactive waste liquid treatment method and system Download PDFInfo
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- CN116153551B CN116153551B CN202310007667.3A CN202310007667A CN116153551B CN 116153551 B CN116153551 B CN 116153551B CN 202310007667 A CN202310007667 A CN 202310007667A CN 116153551 B CN116153551 B CN 116153551B
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- 239000002901 radioactive waste Substances 0.000 title claims abstract description 201
- 239000007788 liquid Substances 0.000 title claims abstract description 193
- 238000000034 method Methods 0.000 title abstract description 28
- 238000010438 heat treatment Methods 0.000 claims abstract description 126
- 238000000926 separation method Methods 0.000 claims abstract description 87
- 238000007906 compression Methods 0.000 claims abstract description 47
- 230000006835 compression Effects 0.000 claims abstract description 46
- 239000007789 gas Substances 0.000 claims description 83
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 20
- 238000004891 communication Methods 0.000 claims description 14
- 238000000746 purification Methods 0.000 claims description 13
- 238000001816 cooling Methods 0.000 claims description 10
- 238000011084 recovery Methods 0.000 claims description 9
- 238000005192 partition Methods 0.000 claims description 8
- 239000012141 concentrate Substances 0.000 claims description 4
- 238000005086 pumping Methods 0.000 claims description 4
- 238000007599 discharging Methods 0.000 claims description 3
- 239000007921 spray Substances 0.000 description 16
- 238000009835 boiling Methods 0.000 description 10
- 238000005265 energy consumption Methods 0.000 description 10
- 238000000605 extraction Methods 0.000 description 9
- 239000000941 radioactive substance Substances 0.000 description 6
- 238000005507 spraying Methods 0.000 description 6
- 230000002285 radioactive effect Effects 0.000 description 5
- 239000002699 waste material Substances 0.000 description 5
- 238000004140 cleaning Methods 0.000 description 4
- 230000007423 decrease Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 238000001704 evaporation Methods 0.000 description 4
- 230000008020 evaporation Effects 0.000 description 4
- 238000012546 transfer Methods 0.000 description 4
- 238000001914 filtration Methods 0.000 description 3
- 238000012544 monitoring process Methods 0.000 description 3
- 229920006395 saturated elastomer Polymers 0.000 description 3
- 230000000694 effects Effects 0.000 description 2
- 238000010992 reflux Methods 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000000945 filler Substances 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 238000011086 high cleaning Methods 0.000 description 1
- 238000010327 methods by industry Methods 0.000 description 1
- 238000005025 nuclear technology Methods 0.000 description 1
- 238000012856 packing Methods 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 239000013589 supplement Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/08—Processing by evaporation; by distillation
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Abstract
The embodiment of the application provides a radioactive waste liquid treatment method, which comprises the following steps: driving the radioactive waste liquid to circulate between the heating device and the separating device by means of a circulating pump, wherein a pressure reducing valve is arranged between the heating device and the separating device, and the pressure reducing valve reduces the pressure of the radioactive waste liquid in the heating device after the radioactive waste liquid enters the separating device; in the circulation process, the vapor separated by the separation device is compressed and heated by the vapor compression device to obtain compressed vapor, the compressed vapor is introduced into the heating device, so that the compressed vapor exchanges heat with the radioactive waste liquid to be used as a first heat source of the heating device, and the radioactive waste liquid can be continuously concentrated; after it is determined that the radioactive waste has been concentrated by a predetermined multiple, the concentrated radioactive waste is directed out of the heating device and the separating device. The embodiment of the application also provides a radioactive waste liquid treatment system.
Description
Technical Field
The application relates to the technical field of radioactive substance treatment, in particular to a radioactive waste liquid treatment method and system.
Background
In the process engineering related to the nuclear technology, a large amount of radioactive waste liquid is often generated, the radioactive waste liquid needs to be concentrated, and the concentration of the radioactive waste liquid is usually completed by adopting an evaporation mode, however, the process flow for treating the radioactive waste liquid adopted in the related technology has higher energy consumption.
Disclosure of Invention
To solve at least one of the technical problems described and other aspects of the prior art, the present application provides a radioactive waste liquid treatment method and system.
According to a first aspect of an embodiment of the present application, there is provided a radioactive waste liquid treatment method including: driving the radioactive waste liquid to circulate between a heating device and a separating device by means of a circulating pump, wherein the heating device is used for heating the radioactive waste liquid so as to enable the radioactive waste liquid to boil in the separating device, the separating device is used for separating steam generated when the radioactive waste liquid boils so as to concentrate the radioactive waste liquid, a pressure reducing valve is arranged between the heating device and the separating device, and the pressure of the radioactive waste liquid in the heating device is reduced after the radioactive waste liquid enters the separating device by the pressure reducing valve; in the circulation process, the vapor separated by the separation device is compressed and heated by the vapor compression device to obtain compressed vapor, the compressed vapor is introduced into the heating device, so that the compressed vapor exchanges heat with the radioactive waste liquid to be used as a first heat source of the heating device, and the radioactive waste liquid can be continuously concentrated; after it is determined that the radioactive waste has been concentrated by a predetermined multiple, the concentrated radioactive waste is directed out of the heating device and the separating device.
According to a second aspect of embodiments of the present application, there is provided a radioactive waste treatment system comprising: a heating device which is provided with a liquid flow channel for the radioactive waste liquid to flow and a gas flow channel arranged outside the liquid flow channel, wherein the gas flowing in the gas flow channel can exchange heat with the radioactive waste liquid in the liquid flow channel so as to heat the radioactive waste liquid; a separation device for separating steam from the boiled radioactive waste liquid after the heat treatment to concentrate the radioactive waste liquid; the pressure reducing valve is arranged between the outlet of the liquid flow channel and the inlet of the separation device and is used for reducing the pressure of the radioactive waste liquid in the heating device after the radioactive waste liquid enters the separation device; the circulating pipeline is used for communicating the separating device with the inlet of the liquid flow channel; the circulating pump is arranged in the circulating pipeline and used for driving the radioactive waste liquid to circularly flow between the heating device and the separating device through the circulating pipeline; the vapor compression device is arranged between the separation device and an inlet of the gas flow passage and is used for compressing and heating vapor separated by the separation device to obtain compressed vapor and introducing the compressed vapor into the gas flow passage to serve as a first heat source of the heating device; the feeding device is used for introducing radioactive waste liquid into the liquid flow channel of the heating device; the discharge port is arranged in the circulating pipeline and is used for leading out the concentrated radioactive waste liquid.
The radioactive waste liquid treatment method and the radioactive waste liquid treatment system provided by the embodiment of the application can obviously reduce the energy consumption during the evaporation and concentration treatment of the radioactive waste liquid.
Drawings
FIG. 1 is a schematic diagram of a radioactive waste treatment system according to one embodiment of the present application;
FIG. 2 is a schematic diagram of a radioactive waste treatment system according to another embodiment of the present application;
FIG. 3 is a schematic view of a radioactive waste treatment system according to yet another embodiment of the present application;
FIG. 4 is a schematic view of a radioactive waste treatment system according to yet another embodiment of the present application;
FIG. 5 is a schematic view of a radioactive waste treatment system according to yet another embodiment of the present application;
FIG. 6 is a schematic diagram of a radioactive waste treatment system according to yet another embodiment of the present application;
FIG. 7 is a schematic view of a radioactive waste treatment system according to yet another embodiment of the present application;
FIG. 8 is a schematic diagram of a surge tank according to an embodiment of the present application;
FIG. 9 is a schematic layout of a radioactive waste treatment system according to an embodiment of the present application;
fig. 10 is a schematic view of a support structure according to an embodiment of the present application.
Detailed Description
The present application will be further described in detail below with reference to specific embodiments and with reference to the accompanying drawings, in order to make the objects, technical solutions and advantages of the present application more apparent.
An embodiment of the present application first provides a radioactive waste treatment system, referring to fig. 1, which may include a heating device 1, a separating device 2, a circulation pump 3, a vapor compression device 4, and a feeding device 5.
The heating device 1 is used for heating the radioactive waste liquid so that it can reach the boiling temperature. The heating device 1 may be a heat exchanger, and for example, the heating device 1 may be formed with a liquid flow channel 11 for flowing radioactive waste liquid, and a gas flow channel 12 provided outside the liquid flow channel 11, and in the course of actually performing radioactive waste liquid treatment, the gas flowing in the gas flow channel 12 may exchange heat with the radioactive waste liquid flowing in the liquid flow channel 11, thereby performing heat treatment on the radioactive waste liquid. The specific arrangement of the liquid flow channel 11 and the gas flow channel 12 can refer to a heat exchanger provided in the related art, and will not be described herein.
The separation device 2 communicates with the liquid flow passage 11 of the heating device 1, so that the radioactive waste liquid heated by the gas flowing in the gas flow passage 12 can be boiled in the separation device 2, and the vapor formed at the time of boiling is separated by the separation device 2, so that the radioactive waste liquid is concentrated. The separation device 2 may be formed with a cavity, the top of the cavity may be formed with a gas outlet, the radioactive waste liquid heated by the heating device 1 can enter the cavity from the top of the cavity, and steam formed by boiling of the radioactive waste liquid leaves the separation device 2 from the gas outlet at the top of the cavity, so that the radioactive waste liquid is concentrated, and the concentrated radioactive waste liquid is deposited at the bottom of the cavity.
The separation device 2 may be further connected to the inlet of the liquid flow channel 11 by means of a circulation pipe 31, the circulation pump 3 may be disposed on the circulation pipe 31, and when the radioactive waste liquid is treated, the radioactive waste liquid remaining after concentration may return to the liquid flow channel 11 of the heating device 1 under the driving of the circulation pump 3, and continue to circulate between the heating device 1 and the separation device 2, so as to repeat the above concentration process.
The vapor compression device 4 is provided between the separation device 2 and the inlet of the gas flow passage 12, and is capable of performing a compression temperature increasing process on the vapor separated by the separation device 2 and introducing it into the gas flow passage of the heating device 1, thereby serving as a heat source of the heating device 1.
It will be appreciated that there is still a significant amount of residual heat energy in the steam separated by the separation device 2, but the residual heat energy is insufficient to heat the radioactive waste liquid to boiling, and the vapour compression device 4 is capable of compressing the steam separated by the separation device 2 to provide the ability to heat the radioactive waste liquid to boiling again, so that the residual heat energy in the steam separated by the separation device 2 is fully recycled, thereby indirectly reducing the energy consumption in the radioactive waste liquid treatment process.
The heating device 1 may be provided with a plurality of heat sources, i.e. it may be provided with other heat sources in addition to the compressed steam generated by the vapour compression device 4, the other heat sources may be the hot steam generated by other devices, or some heating elements provided in the heating device 1, etc., the other heat sources may be used in addition to or instead of the compressed steam to provide the heat required for the evaporation of the radioactive waste liquid, e.g. at the beginning of the radioactive waste liquid treatment, the amount of compressed steam is small or even no compressed steam is present, at which time other heat sources may be used for heating the radioactive waste liquid.
The feeding device 5 communicates with the liquid flow path 11 of the heating device 1, and thereby the radioactive waste liquid is introduced into the heating device 1. In some embodiments, the feeding device 5 may be in communication with the circulation line 31, i.e. indirectly with the liquid flow channel 11 by means of the circulation line 31. In some other embodiments, the feeding means 5 may also be in direct communication with the liquid flow channel 11 without the aid of the circulation line 31. The feeding device 5 may be provided with a feeding pump to provide the power for the flow of radioactive waste.
In the actual radioactive waste liquid treatment process, the radioactive waste liquid in the feeding device 5 may be continuously introduced into the liquid flow channel 11 at a certain rate, or may be stopped after a certain amount of radioactive waste liquid is introduced, and the radioactive waste liquid of the next batch may be introduced after the concentration and extraction of the radioactive waste liquid which has been introduced at present are completed, which is not limited. It will be appreciated that in the continuous feed embodiment, the operation is simpler, but it may be difficult to control the multiple by which the radioactive waste is concentrated more accurately. The batch feeding can accurately control the concentration multiple of the radioactive waste liquid, but the operation is needed to be frequently performed by operators.
The circulation line 31 may be provided with a discharge port 32, and after the radioactive waste has been concentrated by a desired factor, the radioactive waste, which has been concentrated, may be led out by means of the discharge port 32.
During actual radioactive waste treatment, a sample may be taken at the discharge port 32 to determine whether the radioactive waste has been concentrated to a desired multiple and/or the time required for concentration to the desired multiple may be calculated based on the actual treatment efficiency of the radioactive waste treatment system, from which it is determined whether the radioactive waste has been concentrated to the desired multiple. When the feeding device 5 continuously introduces the radioactive waste, the discharge opening 32 may be opened after the radioactive waste has been concentrated by a desired factor and the radioactive waste may be continuously withdrawn at a certain rate. When the feeding device 5 only introduces a certain amount of radioactive waste, the discharge opening 32 may be opened to completely discharge the radioactive waste after it has been concentrated by a desired factor. Those skilled in the art may perform the setting according to the actual situation, and will not be described herein.
In some embodiments, referring to fig. 1, a pressure reducing valve 21 may be provided between the outlet of the liquid flow channel 11 of the heating device 1 and the inlet of the separation device 2, which pressure reducing valve 21 may allow the radioactive waste liquid in the heating device 1 to enter the separation device 2 to be reduced in pressure.
The pressure reducing valve 21 may be any suitable pressure reducing valve provided in the related art, and is not limited thereto. The pressure reducing valve 21 enables a pressure difference to be created between the liquid flow channel 11 and the separation device 2, so that the pressure of the radioactive waste liquid in the liquid flow channel 11 is reduced after it has entered the separation device 2.
It will be appreciated that the boiling point of the liquid is dependent on the pressure and will drop as the pressure drops, whereby the pressure reducing valve 21 ensures that the radioactive waste entering the separation device 2 boils and further increases the utilization of the heat source of the heating device 1, thereby indirectly reducing the energy consumption of the radioactive waste treatment system.
In some embodiments, during the actual radioactive waste treatment, the opening of the pressure reducing valve 21 may be adjusted so that the radioactive waste in the liquid flow channel 11 does not boil, but only after entering the separation device 2. It can be understood that if the radioactive waste liquid in the liquid flow channel 11 boils, a part of steam generated by boiling will remain in the liquid flow channel 11 at this time, and the efficiency of gas-gas heat exchange is lower than that of gas-liquid heat exchange, so that the efficiency of heat exchange between the radioactive waste liquid in the liquid flow channel 11 and the gas in the gas flow channel 12 is reduced, and in this embodiment, the opening of the pressure reducing valve 21 is adjusted to ensure that the radioactive waste liquid in the liquid flow channel 11 will not boil, thereby improving the utilization rate of the heat source and reducing the energy consumption.
In some embodiments, referring to fig. 2, the radioactive waste treatment system may further include a steam generating device 6, where the steam generating device 6 is in communication with the inlet of the gas flow channel 12, so that steam generated by the steam generating device 6 can enter the gas flow channel 12 to serve as the second heat source of the heating device 1. The steam generating device 6 may be any suitable device capable of generating steam by heating and gasifying water, and is not limited thereto.
In this embodiment, the steam generating device 6 may be used as a second heat source of the heating device 1 as a supplement to the compressed steam, thereby enabling the compressed steam to be used as a heat source of the heating device 1 when it has not been generated, or to be used as a heat source of the heating device 1 together with the compressed steam during the treatment, as described above.
In some embodiments, the heating device 1 may be configured with other heat sources besides the steam generating device 6, which will not be described here.
It will be appreciated that in the above embodiments, the heating efficiency of the heating device 1 is actually controlled by the operating parameters of the vapor compression device 4 and the vapor generation device 6, and that in the process of actually performing radioactive waste liquid treatment, the heating efficiency of the heating device 1 can be adjusted by adjusting either one of them.
In some embodiments, it will be appreciated that the steam in the gas flow path 12 will condense to form a liquid upon heat exchange with the radioactive waste liquid, and the gas flow path 12 may be in communication with the inlet of the steam generator 6, such that condensate in the gas flow path 12 may enter the steam generator 6 as a water source for the steam generator 6. In addition to condensate, the steam generator 6 may also have other sources of water to ensure that the steam generator 6 is able to continue to generate sufficient amounts of steam.
It will be appreciated that there is still a significant amount of heat remaining in the condensate, but in this embodiment the condensate is introduced into the steam generator 6as a water source so that the heat remaining in the condensate can be fully utilized, thereby reducing the energy required by the steam generator 6 to generate steam and thus reducing the energy consumption of the radioactive waste disposal system.
In some embodiments, the steam generating device 6 may be arranged below the heating device 1, so that condensate in the heating device 1 may flow into the steam generating device 6 by means of gravity.
In some other embodiments, it may be desirable to provide the steam generating device 6 at the same level as the heating device 1 to reduce the overall radioactive waste disposal system height, at which point it may be desirable to pump condensate from the heating device 1 to the steam generating device 6 by means of the condensate pump 61.
In particular, the condensate pump 61 may be connected to the bottom of the gas flow channel 12 of the heating device 1, whereby condensate deposited on the bottom of the gas flow channel 12 will be pumped into the steam generating device 6.
In some embodiments, it will be appreciated that the formation of condensate requires a certain heat exchange time, and if the condensate pump 61 is always on for pumping, the condensate pump 61 may be in idle mode most of the time, for which purpose a level switch may be provided at the condensate pump 61, which level switch is capable of automatically switching on the condensate pump 61 when it is sensed that the level of condensate in the gas flow channel 12 reaches a certain level, and switching off the condensate pump 61 in other cases, thereby avoiding idle operation of the condensate pump 61.
In some embodiments, the radioactive waste treatment system may further comprise a preheating device 7, the preheating device 7 may be arranged between the feeding device 5 and the heating device 1, which is capable of preheating the radioactive waste from the feeding device 5 into the liquid flow channel 11. It will be appreciated that the time that the radioactive waste remains in the liquid flow channel 11 during a cycle is limited and may not be sufficient to raise its temperature to the temperature required for boiling, for which reason the radioactive waste is preheated in this embodiment, thereby increasing the efficiency of carrying out the radioactive waste. The preheating device 7 may be a heat exchanger or other devices having heat exchange or heating functions, and is not limited thereto.
In some embodiments, the steam generator 6 may be in communication with the preheater 7, allowing condensate in the steam generator 6 to enter the preheater 7 as a heat source for the preheater 7. Specifically, two liquid flow passages may be formed in the preheating device 7, and the condensate and the radioactive waste liquid may flow in the two liquid flow passages, respectively, so that the condensate exchanges heat with the radioactive waste liquid.
As described above, there is also residual heat energy in the condensate, and the condensate is used as a heat source for preheating in this embodiment, so that the residual heat energy therein is more fully utilized, thereby reducing the energy consumption of the radioactive waste liquid treatment system.
In some embodiments, during actual radioactive waste treatment, the flow rate of the condensate introduced into the preheating device 7 may be determined by monitoring the radioactive waste temperature at the outlet of the preheating device 7, for example, if the radioactive waste temperature is less than the desired preheating temperature, the flow rate of the condensate introduced into the preheating device 7 may be increased.
It will be appreciated that if the flow rate of the condensate introduced into the preheating means 7 is too great, this may result in an excessively low water level in the steam generating means 6 and thus in a sufficient amount of steam may not be generated in the steam generating means 6. To this end, in some embodiments, the water level in the steam generator 6 may be further monitored, and if the temperature of the radioactive waste liquid is less than the desired preheating temperature and the water level in the steam generator 6 is less than a preset water level, the preheated temperature may be increased by reducing the rate of introduction of radioactive waste liquid from the feeding device 5 to the preheating device 7.
In some embodiments, the radioactive waste treatment system further includes a condensate recovery apparatus 62, the condensate recovery apparatus 62 may be in communication with the preheating apparatus 7, thereby recovering condensate in the preheating apparatus 7.
In some embodiments, referring to fig. 3, steam generated by the steam generating device 6 may also be introduced at the inlet of the vapor compression device 4. It will be appreciated that when the compressor is arranged in the vapour compression device 4 and the flow rate of the compressor is reduced, or when the pressure difference between the inlet and the outlet is large, surging may occur, which may have a serious effect on the performance or the service life of the vapour compression device 4. In this embodiment, the steam generated by the steam generating device 6 is also introduced into the inlet of the vapor compression device 4, so that the steam can be supplemented when the flow rate of the steam separated by the separation device 2 is smaller, the flow rate of the steam at the inlet of the vapor compression device 4 is ensured, and the occurrence of surge condition is avoided.
In some embodiments, a gas compensating valve may be disposed in a path between the vapor compression device 4 and the vapor generation device 6, and during actual radioactive waste liquid treatment, the working current of the vapor compression device 4 may be monitored, and when the variation of the working current of the vapor compression device 4 is greater than a preset threshold, i.e. abnormal fluctuation occurs, the gas compensating valve is opened to introduce the vapor of the vapor generation device 6 to the inlet of the vapor compression device 4, so as to avoid occurrence of surge. In some other embodiments, it may also be determined whether the make-up valve needs to be opened for make-up by monitoring the pressure, gas flow, etc. at the inlet of the vapor compression device 4.
Further, when the steam flow at the inlet of the vapor compression device 4 is reduced, this means that the working efficiency of the heating device 1 is lower, resulting in a lower steam flow separated by the separation device 2. At this time, as described above, the efficiency with which the radioactive waste is concentrated may be controlled by adjusting the operation parameters of the vapor compression device 4 and/or the vapor generation device 6, thereby adjusting the vapor flow rate.
For example, the rotational speed of the vapor compression device 4 may be increased when the flow of vapor at the inlet of the vapor compression device 4 decreases. Or the power of the steam generating means 6 may be increased when the steam flow at the inlet of the steam compressing means 4 decreases. As the flow of steam at the inlet of the vapor compression device 4 increases, the rotational speed of the vapor compression device 4 may be reduced. Or the power of the steam generating means 6 may be reduced when the steam flow at the inlet of the steam compressing means 4 increases.
In some embodiments, when the flow of steam at the inlet of the vapour compression device 4 decreases, the gas pressure in the separation device 2 may be detected, if the gas pressure in the separation device 2 is higher than a preset pressure, the rotational speed of the vapour compression device 4 may be increased, and if the gas pressure in the separation device 2 is lower than the preset pressure, the power of the vapour generation device 6 may be increased. In this embodiment, the gas pressure in the separation device 2 is used to select which device is specifically to be controlled by adjusting the parameters thereof, thereby improving the effectiveness of the control.
In some embodiments, the condensate in the steam generating device 6 may be further introduced to the outlet of the steam compressing device 4 to perform a certain spray cooling treatment on the compressed steam. It will be appreciated that the compressed steam may be compressed into superheated steam at a lower pressure than saturated steam, but the superheated steam does not significantly improve the working efficiency of the heating device 1, and for this purpose, in this embodiment, the compressed steam is subjected to a certain spraying treatment so as not to form superheated steam, thereby avoiding occurrence of surge due to too low pressure at the outlet of the vapor compression device 4 without affecting the heating efficiency of the heating device 1.
In some embodiments, the pressure at the outlet of the vapor compression device is monitored, and the vapor temperature of the compressed vapor after spraying is monitored, and if the vapor temperature is greater than the saturated vapor temperature at the current pressure at the outlet of the vapor compression device, the amount of condensate that sprays the compressed vapor is increased. If the steam temperature is less than the saturated steam temperature at the current pressure, the amount of condensate to be sprayed is reduced or no spraying is performed, so that the working efficiency of the heating device 1 is prevented from being affected by excessive spraying treatment.
In some embodiments, it may be desirable to control the liquid level in the separation device 2 so that the radioactive waste boils at the proper liquid level for better separation. For example, the level of the liquid in the separation device 2 may be adjusted by adjusting the power of the circulation pump 3, or the level of the liquid in the separation device 2 may also be adjusted by adjusting the feed efficiency of the feed device 5.
In some embodiments, the rate of introduction of the exothermic waste liquid from the feeding device 5 into the heating device 1 may be reduced when the liquid level in the separation device 2 increases. As the liquid level in the separation device 2 decreases, the rate of introduction of radioactive waste liquid from the feeding device 5 into the heating device 1 may be increased.
In some embodiments, referring to fig. 4, the feeding device 5 may be provided with a first line 51 communicating with the heating device 1, the first line 51 being used for introducing radioactive waste liquid into the heating device 1, a second line 52 communicating with the feeding device 5 being provided on the first line 51, the second line 52 being used for refluxing a portion of the radioactive waste liquid in the first line 51 to the feeding device 5, in which embodiment the rate of introducing radioactive waste liquid into the heating device 1 may be adjusted by adjusting the rate of refluxing the radioactive waste liquid in the first line 51 to the feeding device 5. As an example, a valve may be provided in the second line 52, and the rate of return of the radioactive waste liquid to the feeding means 5 may be adjusted by adjusting the opening of the valve.
Compared with directly adjusting the flow rate in the first pipeline 51, the adjustment method provided in this embodiment can avoid abrupt changes in the flow rate, pressure, temperature, etc. of the radioactive waste liquid entering the radioactive waste liquid treatment system.
In some embodiments, referring to fig. 5, the radioactive waste treatment system may further comprise a purifying device 8 disposed between the separating device 2 and the vapor compression device 4, the purifying device 8 being configured to purify the vapor separated by the separating device 2 before it enters the vapor compression device 4. As described above, the main component of the steam separated by the separation device 2 is water, which will be subsequently turned into condensate and recovered, and which may be entrained with some radioactive substances, so that the purification device 8 is provided in this embodiment to purify the steam to remove the radioactive substances entrained in the steam, so as to avoid exceeding the radioactive content of the condensate.
The purification mode of the purification device 8 can be specifically set by a person skilled in the art according to actual requirements, for example, a spray head can be arranged in the purification device 8, and the steam entering the purification device 8 can be subjected to spray treatment so as to remove radioactive substances entrained therein. Or the purifying device 8 may be provided with a structure having a filtering function such as a wire mesh, a packing, or the like, which is capable of filtering and adsorbing radioactive substances entrained in the vapor.
In some embodiments, a structure with filtering function such as a silk screen, a filler, etc. may be arranged on the top of the separation device 2, which can perform a certain pre-purification on the steam before entering the purification device 8, so as to further improve the purification effect.
In some embodiments, as described above, a spray head 81 may be provided in the purifying device 8, and the spray head 81 may spray the steam entering the purifying device 8. It will be appreciated that the temperature of the liquid used in the spraying process should not be too low to avoid condensing a significant amount of steam and resulting in waste of heat. For this purpose, in some embodiments, condensed water in the steam generating device 6 may be introduced into the purification device 8 as spray water, which, as described above, has a heat residual, which is capable of avoiding condensing a large amount of steam while spraying.
The shower water remaining after the shower treatment may be entrained with a lot of radioactive substances, for which reason, in some embodiments, the shower water after the shower treatment may be introduced into the feeding device 5 to avoid the occurrence of radioactive leakage.
In some embodiments, referring to fig. 6, spray water dropped on the bottom of the purifying device 8 after the spray treatment may be reintroduced into the spray head 81 to spray, thereby avoiding introducing excessive condensed water into the spray head 81 to spray the treatment and reducing waste of heat.
In this embodiment, shower water at the bottom of the purifying device 8 may be introduced into the feeding device 5 at predetermined intervals. Further, after introducing the liquid at the bottom of the purifying device 8 to the feeding device, the condensate in the steam generating device 6 may be introduced into the shower head 81 to replenish the liquid for the shower treatment.
It will be appreciated that during circulation of the spray liquid, there may be a part of the vapour condensing which causes the height of the spray liquid to rise and thus affects the cleaning efficiency, for which purpose in some embodiments it is also possible to monitor the pressure difference between the inlet and the outlet of the cleaning device 8, and when this pressure difference is greater than a preset pressure difference, a part of the condensate at the bottom of the cleaning device 8 may be introduced into the feeding device 5, thereby ensuring that the cleaning device 8 always has a high cleaning efficiency.
In some embodiments, referring to fig. 7, the radioactive waste treatment system may further comprise a vacuum pump 9, the vacuum pump 9 being in communication with the separation device 2 for drawing gas from the separation device 2 to create a negative pressure environment in the separation device 2. It will be appreciated that the creation of a negative pressure environment in the separation device 2 helps to further increase the efficiency of the radioactive waste boiling in the separation device 2.
In some embodiments, the outlet of the separation device 2 may be provided with a first air extraction opening 91, the air flow channel 12 of the heating device 1 may be provided with a second air extraction opening 92, and the vacuum pump 9 may extract air from the first air extraction opening 91 and/or the second air extraction opening 92 to construct a negative pressure environment. The first suction port 91 and the second suction port 92 provided in the present embodiment contribute to improvement of efficiency in constructing a negative pressure environment.
In some embodiments, the construction of the negative pressure environment may be performed prior to the introduction of the radioactive waste. In some embodiments, the gas pressure in the separation device 2 may also be monitored during radioactive waste treatment, and if the gas pressure is higher than the desired negative pressure, a certain amount of gas may be extracted from the extraction port to maintain the negative pressure environment.
In some embodiments, the vacuum pump 9 may also be used to pump non-condensable gases in the heating device 1. As described above, the gas entering the heating device 1 condenses into condensed water after heat exchange, however, some uncondensable gas, i.e., uncondensed gas, may be mixed into the heating device 1, and when more uncondensed gas is accumulated in the heating device 1, the overall temperature of the gas in the heating device 1 will be reduced, thereby affecting the heating efficiency of the heating device 1, and for this reason, the uncondensed gas in the heating device 1 may be extracted by the vacuum pump 9, thereby avoiding accumulation of uncondensed gas. Specifically, the noncondensable gas may be extracted from the above-described second extraction opening 92.
In some embodiments, the non-condensable gas may be extracted at predetermined intervals, or the temperature of the feed liquid in the separation device 2 may be monitored, and if the temperature of the feed liquid in the separation device 2 is lower than the evaporation temperature, this means that the heating efficiency is reduced, and at this time, the vacuum pump 9 may be turned on to extract the non-condensable gas in the heating device 1.
It will be appreciated that the extracted gas, both when a negative pressure environment is built up and when non-condensable gases are extracted, contains a significant amount of vapour which may condense in the vacuum pump 9, affecting the working efficiency and lifetime of the vacuum pump 9, and for this purpose, in some embodiments, the radioactive waste disposal system may further comprise cooling means 93 arranged in the path between the vacuum pump 9 and the separation means 2, the cooling means 93 being adapted to cool the gas extracted by the vacuum pump 9 to recover vapour in the gas extracted by the vacuum pump 9 as condensate.
In some embodiments, it is understood that when the power of the vacuum pump 9 is high, it is possible to pump away part of the condensate from the cooling device 93, for which purpose, with reference to fig. 8, a buffer tank 94 may be provided between the vacuum pump 9 and the cooling device 93, which buffer tank 94 serves to store condensate, avoiding that condensate is pumped into the vacuum pump 9.
Specifically, the buffer tank 94 may include a first buffer tank 941, a second buffer tank 942, a first valve 943, and a second valve 944, the first buffer tank 941 being in communication with the vacuum pump 9 and the cooling device 93, the second buffer tank 942 being disposed below the first buffer tank 941, the first valve 943 being disposed at a junction of the first buffer tank 941 and the second buffer tank 942, the second valve 944 being disposed to communicate the second buffer tank 942 with the atmosphere.
It will be appreciated that if the buffer tank is completely sealed during pumping, the vacuum pump 9 may not be able to continuously pump gas due to the air pressure problem, whereas if the buffer tank is in communication with the atmosphere, the separating device 2, the gas flow passage 12 of the heating device 1, etc. may be directly in communication with the atmosphere, which may present a risk of radioactive leakage, for which reason, in the present embodiment, two buffer tank structures are provided.
Specifically, when the vacuum pump 9 is turned on and the condensate level in the first buffer tank 941 is lower than a preset value, the first valve 943 may be closed. When the condensate level in the first buffer tank 941 is higher than the preset value, this means that the pressure in the first buffer tank 941 is already high, and at this time, the second valve 944 may be closed and the first valve 943 may be opened, so that the condensate in the first buffer tank 941 enters the second buffer tank 942, thereby releasing the pressure in the first buffer tank 941.
After the condensate in the first buffer tank 941 has fully entered the second buffer tank 942, the first valve 943 may be closed and the second valve 944 may be opened to equalize the pressure in the second buffer tank 942, so that when more condensate is accumulated in the first buffer tank 941 next time, the second valve 944 may still be closed and the first valve 943 may be opened to release the pressure in the first buffer tank 941.
In this embodiment, the first valve 943 and the second valve 944 are not opened at the same time, so that it is ensured that the vacuum pump 9 can continuously pump gas, and that the separation device 2, the gas flow channel 12, and the like are not directly connected to the atmosphere.
In some embodiments, the second buffer tank 942 may be in communication with the condensate recovery apparatus 62, and a third valve 945 is provided at the communication of the second buffer tank 942 with the condensate recovery apparatus 62. In this embodiment, after the condensate in the first buffer tank 941 enters the second buffer tank 9421, the first valve 943 may be closed and the second valve 944 and the third valve 945 may be opened to introduce the condensate in the second buffer tank 942 to the condensate recovery apparatus 62.
In some embodiments, the vacuum pump 9 may be connected to a filter device 95, the filter device 95 may be connected to an exhaust 96, the filter device 95 may be used to filter radioactive materials in the gas pumped by the vacuum pump 9, and the exhaust 96 may be used to exhaust the filtered gas.
In some embodiments, the exhaust tube 96 may be provided in a segmented configuration with the segments being removable from each other or slidable relative to each other so that the segments of the exhaust tube 96 may be removed from each other or folded over each other without radioactive waste treatment to avoid limited movement due to the high height.
In some embodiments, referring to fig. 9 and 10, the radioactive waste treatment system further includes a support platform 100, the support platform 100 may be horizontally disposed, and the apparatus may be fixed to the support platform 100. In this embodiment, above-mentioned device is fixed on same horizontal plane to, reduced the height of radioactivity waste liquid treatment system in vertical plane, make the overall structure of radioactivity waste liquid treatment system compacter, conveniently arrange in comparatively narrow and small space.
In some embodiments, the support platform 100 may be fixed to a movable platform, so that the entire radioactive waste treatment system is movable, and the application scenario is not necessarily limited to a factory building. The movable platform may be an automobile and is provided with a compartment in which the support platform 100 and the above-described devices may be fixed. As described above, the devices in the radioactive waste treatment system in the present embodiment are fixed on the same horizontal plane, so that the radioactive waste treatment system of the present embodiment as a whole can meet the height limit requirement when the vehicle is traveling, and thus, can freely travel to a desired position on a road for radioactive waste treatment.
In some embodiments, the liquid flow channels 11 and the gas flow channels 12 of the heating device 1 described above are arranged in parallel with the support platform 100. That is, the heating device 1 is designed in a horizontal type, thereby ensuring that the liquid flow passage 11 and the gas flow passage 12 are long enough to satisfy the height requirement.
In some embodiments, the feeding means 5, the heating means 1, the separating means 2 and the vapour compression means 4 may be arranged in sequence along the first direction of the support platform 100.
Further, in some embodiments, the steam generating device 6 and the steam compressing device 4 may be arranged side by side along the second direction of the support platform 100.
It will be appreciated that the radioactive content in the vapour compression device 4 and the vapour generation device 6 is lower than in the feeding device 5, the heating device 1, the separation device 2, and therefore the vapour compression device 4 and the vapour generation device 6 are arranged side by side and on one side of the three devices, so that the whole radioactive waste liquid treatment system is divided into areas of high and low radioactivity, which is convenient for ensuring the safety of the operators.
In some embodiments, the radioactive waste treatment system may include a partition that may extend in the second direction, with the vapor-generating device 4 and vapor-compression device 6 disposed on sides of the partition facing away from the separation device 2. In this embodiment, the low-emissivity devices such as the steam generator 4 and the steam compressor 6 are further isolated from the high-emissivity devices by a partition plate, so that safety is ensured. As described hereinabove, the support platform 100 and the above-described devices may be disposed in the cabin, and the partition may be hermetically connected to the cabin, so that the low-emissivity devices such as the steam generator 4, the steam compressor 6, and the like are located in two relatively sealed partitions with the high-emissivity devices.
In some embodiments, the condensate recovery means 62 may be arranged on the side of the vapour compression means 4 facing away from the separation means 2, i.e. it is also arranged in the zone where the low-emissivity means are located.
In some embodiments, the circulation pump 3 and the purification device 8 may be disposed at both sides of the heating device 1 in the second direction of the support platform 100. In some embodiments, the preheating means 7 may be arranged between the feeding means 5 and the purifying means 8.
In some embodiments, some electrical cabinets without control equipment and electrical equipment, such as electrical cabinets for providing electrical power to the various devices, and controls for controlling the start-up, operation, monitoring of the operating parameters of the devices, etc. may also be provided on the support platform 100, as these equipment are not radioactive, they may be provided on the side of the steam generating means 4, the steam compression means 6, the condensate recovery means 62, etc. facing away from the separation means 2, and may likewise be isolated from the devices by means of a partition, whereby the whole radioactive waste treatment system is divided into three areas, high-emission, low-emission and no-emission.
As described above, there are multiple lines between the devices, some for transfer of condensate, some for extraction and transfer of gas, and in some embodiments, these lines for transfer of condensate may be located along the surface of the support platform 100, while lines for extraction and transfer of gas may be located along the top surface of each device.
In some embodiments, referring to fig. 10, the support platform 100 includes a support plate 110 and a support bracket 120. The support bracket 120 is disposed above the support plate 110 and forms a gap with the support plate 110. In this embodiment, each device may be connected to the support 120, and it will be understood that, in the operation process of each device, a leakage may occur, and because a gap is formed between the support 120 and the support 110, the leakage may be collected in the gap, so as to avoid flowing around.
In some embodiments, the side of the support plate 110 facing the support frame 120 is formed with an inclination angle. Thus, the liquid leaked into the gap flows to a corner of the support plate 110 along the inclined angle, thereby facilitating the collection of the leaked liquid.
Specifically, the inclination angle of the support plate 110 may be a very small angle, and at the same time, the support surface of the support frame 120 may be horizontal to ensure the stability of the support for each of the above-mentioned devices.
Embodiments of the present application also provide a radioactive waste treatment method that may be applied to the radioactive waste treatment system described in one or more of the embodiments above.
Specifically, the radioactive waste liquid treatment method comprises the following steps:
S1: the radioactive waste liquid is driven to circulate between the heating device and the separating device by means of the circulating pump, wherein the heating device is used for heating the radioactive waste liquid so as to enable the radioactive waste liquid to boil in the separating device, the separating device is used for separating steam generated when the radioactive waste liquid boils so as to concentrate the radioactive waste liquid, a pressure reducing valve is arranged between the heating device and the separating device, and the pressure of the radioactive waste liquid in the heating device is reduced after the radioactive waste liquid enters the separating device by the pressure reducing valve.
S2: in the circulation process, the vapor separated by the separation device is compressed and heated by the vapor compression device to obtain compressed vapor, the compressed vapor is introduced into the heating device, so that the compressed vapor exchanges heat with the radioactive waste liquid to be used as a first heat source of the heating device, and the radioactive waste liquid can be continuously concentrated;
S3: after it is determined that the radioactive waste has been concentrated by a predetermined multiple, the concentrated radioactive waste is directed out of the heating device and the separating device.
As described above, in the method provided by the present embodiment, the pressure of the radioactive waste liquid is reduced by the pressure reducing valve after the radioactive waste liquid enters the separation device, thereby ensuring that the radioactive waste liquid entering the separation device boils, and further improving the utilization rate of the heat source of the heating device, thereby indirectly reducing the energy consumption in the radioactive waste liquid treatment.
In some embodiments, the method further comprises: the opening of the pressure reducing valve is adjusted so that the radioactive waste liquid does not evaporate in the heating device but evaporates after entering the separating device. According to the embodiment, the radioactive waste liquid in the liquid flow channel can be prevented from boiling by adjusting the opening of the pressure reducing valve, so that the utilization rate of a heat source is improved, and the energy consumption is reduced.
In some embodiments, the steam generated by the steam generating means may be introduced into the heating means as a second heat source of the heating means.
In some embodiments, condensate in the heating device may be introduced into the steam generating device as a water source for the steam generating device, the condensate being generated after heat exchange between compressed steam in the heating device and the radioactive waste liquid. It will be appreciated that a large amount of residual heat still exists in the condensate, but in this embodiment, the condensate is introduced into the steam generating device as a water source, so that the heat remaining in the condensate can be fully utilized, thereby reducing the energy required by the steam generating device when generating steam, and further reducing the energy consumption during radioactive waste liquid treatment.
In some embodiments, a discharge port is disposed on the circulation pipeline between the heating device and the separation device, and the method for leading the concentrated radioactive waste liquid out of the separation device and the heating device can include: after it is determined that the radioactive waste has been concentrated to a predetermined multiple, the discharge port is opened to continuously lead the radioactive waste out of the separation device and the heating device.
In some embodiments, a discharge port is disposed on the circulation pipeline between the heating device and the separation device, and the method for leading the concentrated radioactive waste liquid out of the separation device and the heating device can include: after the radioactive waste liquid is determined to be concentrated to a preset multiple, the discharging hole is opened to lead the radioactive waste liquid out of the separating device and the heating device, and then the discharging hole is closed.
In some embodiments, the radioactive waste in the feeding device may be continuously introduced into the heating device during the circulation.
In some embodiments, the rate of introduction of radioactive waste liquid from the supply device into the heating device may be adjusted based on the liquid level in the separation device to maintain the liquid level in the separation device at the operating liquid level.
In some embodiments, introducing radioactive waste from the supply device to the heating device may include: the radioactive waste liquid is introduced into a preheating device from a feeding device for preheating treatment, and the radioactive waste liquid in the preheating device is introduced into a heating device.
In some embodiments, introducing radioactive waste from the supply device to the preheating device for preheating treatment may include: the radioactive waste liquid is introduced into the preheating device from the feeding device, and condensate in the steam generating device is introduced into the preheating device to exchange heat with the radioactive waste liquid so as to perform preheating treatment on the radioactive waste liquid.
In some embodiments, the condensate in the preheating device may be introduced into the condensate recovery device.
In some embodiments, the vapor separated by the separation device may be subjected to a purification treatment by the purification device prior to being introduced into the vapor compression device.
In some embodiments, a negative pressure environment may be built up in the separation device by means of a vacuum pump.
In some embodiments, building a negative pressure environment in the separation device with the aid of a vacuum pump may comprise: before the radioactive waste liquid starts to be treated, the gas in the separation device is pumped by a vacuum pump to build a negative pressure environment in the separation device.
In some embodiments, building up a negative pressure environment in the separation device with the aid of the vacuum pump may further comprise: during the circulation, the pressure in the separation device is monitored, and if the pressure in the separation device is higher than the desired negative pressure, the gas in the separation device is pumped by means of a vacuum pump to maintain a negative pressure environment in the separation device.
In some embodiments, the non-condensable gases in the heating device may be pumped by the vacuum pump described above.
In some embodiments, the gas pumped by the vacuum pump may be subjected to a cooling process by the cooling device during the process of pumping the non-condensable gas in the heating device and the negative pressure environment in the separating device by the vacuum pump, so as to recover the vapor in the gas pumped by the vacuum pump as condensate.
Specific technical details of the radioactive waste treatment method described above may be referred to the description of the relevant parts of the radioactive waste treatment system above, and will not be repeated here.
The present invention has been described in detail with reference to the drawings and the embodiments, but the present invention is not limited to the embodiments described above, and various changes can be made within the knowledge of those skilled in the art without departing from the spirit of the present invention. The invention may be practiced otherwise than as specifically described.
Claims (9)
1. A radioactive waste treatment system comprising:
A heating device formed with a liquid flow passage for flowing radioactive waste liquid, and a gas flow passage provided outside the liquid flow passage, the gas flowing in the gas flow passage being capable of exchanging heat with the radioactive waste liquid in the liquid flow passage to heat-treat the radioactive waste liquid;
a separation device in communication with the liquid flow channel for separating vapor from the boiled radioactive waste after the heat treatment to concentrate the radioactive waste;
A pressure reducing valve arranged between an outlet of the liquid flow channel and an inlet of the separation device, wherein the pressure reducing valve is used for reducing the pressure of the radioactive waste liquid in the heating device after the radioactive waste liquid enters the separation device;
A circulation line that communicates the separator with an inlet of the liquid flow passage;
a circulation pump provided in the circulation line, the circulation pump being for driving the radioactive waste liquid to circulate between the heating device and the separation device via the circulation line;
a vapor compression device arranged between the separation device and an inlet of the gas flow passage, wherein the vapor compression device is used for compressing and heating vapor separated by the separation device to obtain compressed vapor and introducing the compressed vapor into the gas flow passage to serve as a first heat source of the heating device;
the feeding device is used for introducing the radioactive waste liquid into the liquid flow channel of the heating device;
The discharging port is arranged in the circulating pipeline and is used for leading out the concentrated radioactive waste liquid;
The steam generation device is communicated with the inlet of the gas flow passage, so that steam generated by the steam generation device can enter the gas flow passage to serve as a second heat source of the heating device;
The radioactive waste liquid treatment system further comprises a support platform, wherein the support platform is arranged to be horizontally placed, and the radioactive waste liquid treatment system of the device is fixed on the support platform;
The liquid flow channel and the gas flow channel of the heating device are arranged in parallel with the supporting platform;
the feeding device, the heating device, the separating device and the vapor compression device are arranged in sequence along a first direction of the supporting platform;
the steam generating device and the steam compression device are arranged side by side along the second direction of the supporting platform;
the steam generating device and the steam compressing device are arranged on one side of the feeding device, the heating device and the separating device;
The radioactive waste liquid treatment system includes a partition plate disposed to extend in a second direction, the vapor generating device and the vapor compression device being disposed on a side of the partition plate facing away from the separation device.
2. The system of claim 1, wherein the gas flow passage communicates with an inlet of the steam generation device to enable condensate in the gas flow passage to be used as a water source for the steam generation device, the condensate being generated after heat exchange of gas in the heating device with the radioactive waste liquid.
3. The system of claim 2, further comprising:
and the preheating device is arranged between the feeding device and the heating device and is used for preheating the radioactive waste liquid which is introduced into the liquid flow channel from the feeding device.
4. A system according to claim 3, wherein the steam generator is in communication with the pre-heater, such that condensate in the steam generator can enter the pre-heater as a heat source for the pre-heater.
5. The system of claim 4, further comprising:
and the condensate recovery device is communicated with the preheating device and is used for recovering the condensate in the preheating device.
6. The system of claim 1, further comprising:
And the purification device is arranged between the separation device and the vapor compression device and is used for purifying the vapor separated by the separation device before the vapor enters the vapor compression device.
7. The system of claim 1, further comprising:
and the vacuum pump is communicated with the separation device and is used for pumping gas in the separation device so as to build a negative pressure environment in the separation device.
8. The system of claim 7, wherein the vacuum pump is further configured to pump non-condensable gases in the heating device.
9. The system of claim 8, further comprising:
And the cooling device is arranged on a passage between the vacuum pump and the separation device and is used for cooling the gas pumped by the vacuum pump so as to recover steam in the gas pumped by the vacuum pump as condensate.
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