Radioactive waste liquid treatment system

Abstract

The embodiment of the present application provides a radioactive waste liquid treatment system, which comprises a support platform, the support platform is horizontally placed; a heating device, which is fixed on the support platform; a separation device, which is fixed on the support platform; a circulating pipeline, which extends along the surface of the support platform, and which is communicated with the separation device and the inlet of a liquid flow channel; a circulating pump, which is fixed on the support platform and arranged in the circulating pipeline; a steam compression device, which is fixed on the support platform; a feeding device, which is fixed on the support platform; and a discharge outlet, which is arranged in the circulating pipeline.

Description

Technical Field

[0001] This application relates to the field of radioactive material treatment technology, specifically to a radioactive waste liquid treatment system. Background Technology

[0002] Nuclear technology-related processes often generate large amounts of radioactive waste liquid, which needs to be concentrated. Evaporation is usually used to concentrate the radioactive waste liquid. However, the radioactive waste liquid treatment systems used in related technologies typically have a large footprint. Summary of the Invention

[0003] To address at least one technical problem mentioned above and in other aspects in the prior art, this application provides a method and system for treating radioactive waste liquid.

[0004] According to an embodiment of this application, a radioactive waste liquid treatment system is provided, comprising: a support platform, which is horizontally placed; a heating device fixed on the support platform, the heating device forming a liquid flow channel for the flow of radioactive waste liquid and a gas flow channel disposed 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 to heat the radioactive waste liquid; a separation device fixed on the support platform, the separation device being used to separate the vapor in the boiling radioactive waste liquid after heat treatment, thereby concentrating the radioactive waste liquid; and a circulation pipeline extending along the surface of the support platform, the circulation pipeline connecting the separation device and the inlet of the liquid flow channel; A circulation pump, fixed on a support platform and installed in the circulation pipeline, drives the radioactive waste liquid to circulate between the heating device and the separation device via the circulation pipeline. A vapor compression device, fixed on the support platform and installed between the separation device and the inlet of the gas flow channel, compresses and heats the vapor separated by the separation device to obtain compressed vapor, and introduces the compressed vapor into the gas flow channel as the first heat source for the heating device. A feeding device, fixed on the support platform, feeds the radioactive waste liquid into the liquid flow channel of the heating device. An outlet, installed in the circulation pipeline, is used to discharge the concentrated radioactive waste liquid.

[0005] The radioactive waste liquid treatment system provided in this application embodiment has a relatively compact structure and occupies less space in the vertical direction. Attached Figure Description

[0006] Figure 1 This is a schematic diagram of a radioactive waste liquid treatment system according to an embodiment of this application;

[0007] Figure 2 This is a schematic diagram of a radioactive waste liquid treatment system according to another embodiment of this application;

[0008] Figure 3 This is a schematic diagram of a radioactive waste liquid treatment system according to another embodiment of this application;

[0009] Figure 4 This is a schematic diagram of a radioactive waste liquid treatment system according to another embodiment of this application;

[0010] Figure 5 This is a schematic diagram of a radioactive waste liquid treatment system according to another embodiment of this application;

[0011] Figure 6 This is a schematic diagram of a radioactive waste liquid treatment system according to another embodiment of this application;

[0012] Figure 7 This is a schematic diagram of a radioactive waste liquid treatment system according to another embodiment of this application;

[0013] Figure 8 This is a schematic diagram of a buffer tank according to an embodiment of this application;

[0014] Figure 9 This is a schematic diagram of the layout of a radioactive waste liquid treatment system according to an embodiment of this application;

[0015] Figure 10 This is a schematic diagram of the support structure according to an embodiment of this application. Detailed Implementation

[0016] To make the objectives, technical solutions, and advantages of this application clearer, the following detailed description is provided in conjunction with specific embodiments and the accompanying drawings.

[0017] Embodiments of this application provide a radioactive waste liquid treatment system, referring to... Figure 1 The radioactive waste liquid treatment system may include a heating device 1, a separation device 2, a circulation pump 3, a vapor compression device 4, and a feeding device 5.

[0018] Heating device 1 is used to heat radioactive waste liquid to bring it to a boiling temperature. Heating device 1 can be a heat exchanger. For example, heating device 1 can have a liquid flow channel 11 for the flow of radioactive waste liquid and a gas flow channel 12 disposed outside the liquid flow channel 11. During the actual treatment of radioactive waste liquid, the gas flowing in the gas flow channel 12 can exchange heat with the radioactive waste liquid flowing in the liquid flow channel 11, thereby heating the radioactive waste liquid. The specific arrangement of the liquid flow channel 11 and the gas flow channel 12 can be referred to heat exchangers provided in related technologies in the art, and will not be elaborated here.

[0019] The separation device 2 is connected to the liquid flow channel 11 of the heating device 1, so that the radioactive waste liquid heated by the gas flowing in the gas flow channel 12 can boil in the separation device 2, and the steam formed during boiling is separated by the separation device 2, thereby concentrating the radioactive waste liquid. The separation device 2 can form a cavity, and a gas outlet can be formed at the top of the cavity. The radioactive waste liquid heated by the heating device 1 can enter the cavity from the top of the cavity, and the steam formed by boiling will leave the separation device 2 from the gas outlet at the top of the cavity, thereby concentrating the radioactive waste liquid. The concentrated radioactive waste liquid will be deposited at the bottom of the cavity.

[0020] The separation device 2 can also be connected to the inlet of the liquid flow channel 11 via the circulation pipeline 31. The circulation pump 3 can be installed on the circulation pipeline 31. When radioactive waste liquid is treated, under the drive of the circulation pump 3, the remaining radioactive waste liquid after concentration can return to the liquid flow channel 11 of the heating device 1 and continue to circulate between the heating device 1 and the separation device 2, thereby repeating the above concentration process.

[0021] The vapor compression device 4 is located between the inlet of the separation device 2 and the gas flow channel 12. It can compress and heat the vapor separated by the separation device 2 and introduce it into the gas flow channel of the heating device 1, thereby serving as a heat source for the heating device 1.

[0022] Understandably, the steam separated by the separation device 2 still contains a large amount of residual heat energy, but this residual heat energy is insufficient to heat the radioactive waste liquid to boiling. The steam compression device 4 can compress the steam separated by the separation device 2, enabling it to regain the ability to heat the radioactive waste liquid to boiling. Thus, the residual heat energy in the steam separated by the separation device 2 is fully recovered and utilized, indirectly reducing the energy consumption in the radioactive waste liquid treatment process.

[0023] The heating device 1 can be equipped with multiple heat sources. That is, in addition to the compressed steam generated by the vapor compression device 4, it can also be equipped with other heat sources. These other heat sources can be hot steam generated by other devices, or heating components installed in the heating device 1. These other heat sources can supplement and replace the compressed steam to provide the heat required for the evaporation of radioactive waste liquid. For example, when radioactive waste liquid treatment is initially started, the amount of compressed steam is small or even non-existent. In this case, other heat sources can be used to heat the radioactive waste liquid.

[0024] The feeding device 5 is connected to the liquid flow channel 11 of the heating device 1, thereby introducing radioactive waste liquid into the heating device 1. In some embodiments, the feeding device 5 may be connected to the circulation pipeline 31, that is, indirectly connected to the liquid flow channel 11 via the circulation pipeline 31. In some other embodiments, the feeding device 5 may also be directly connected to the liquid flow channel 11 without using the circulation pipeline 31. A feeding pump may be configured on the feeding device 5 to provide power for the flow of radioactive waste liquid.

[0025] In the actual process of radioactive waste treatment, the radioactive waste liquid in the feeding device 5 can be continuously introduced into the liquid flow channel 11 at a certain rate. Alternatively, it can be stopped after a certain amount of radioactive waste liquid has been introduced, and the next batch of radioactive waste liquid can be introduced only after the currently introduced radioactive waste liquid has been concentrated and withdrawn. There are no restrictions on this. Understandably, in the continuous feeding embodiment, the operation is simpler, but it may be difficult to control the concentration factor of the radioactive waste liquid more precisely. Batch feeding, on the other hand, can control the concentration factor of the radioactive waste liquid more precisely, but it requires frequent operation by the operator.

[0026] A discharge port 32 can be provided on the circulation pipeline 31. After the radioactive waste liquid has been concentrated to the desired multiple, the concentrated radioactive waste liquid can be led out through the discharge port 32.

[0027] In the actual process of radioactive waste liquid treatment, samples can be taken at the discharge port 32 to determine whether the radioactive waste liquid has been concentrated to the desired multiple, and / or, the time required for concentration to the desired multiple can be calculated based on the actual treatment efficiency of the radioactive waste liquid treatment system, and this time can be used to determine whether the radioactive waste liquid has been concentrated to the desired multiple. When the feeding device 5 continuously introduces radioactive waste liquid, the discharge port 32 can be opened after the radioactive waste liquid has been concentrated to the desired multiple, and the radioactive waste liquid can be continuously drawn out at a certain rate. When the feeding device 5 introduces only a certain amount of radioactive waste liquid, the discharge port 32 can be opened after the radioactive waste liquid has been concentrated to the desired multiple, and all the radioactive waste liquid can be drawn out. Those skilled in the art can set it according to the actual situation, which will not be elaborated here.

[0028] In some embodiments, refer to Figure 1 A pressure reducing valve 21 can be installed between the outlet of the liquid flow channel 11 of the heating device 1 and the inlet of the separation device 2. The pressure reducing valve 21 can reduce the pressure of the radioactive waste liquid in the heating device 1 after it enters the separation device 2.

[0029] The pressure reducing valve 21 can be any suitable pressure reducing valve available in the related art, and there is no limitation thereto. The pressure reducing valve 21 can create a pressure difference between the liquid flow channel 11 and the separation device 2, thereby reducing the pressure of the radioactive waste liquid in the liquid flow channel 11 after it enters the separation device 2.

[0030] Understandably, the boiling point of a liquid is related to pressure. When the pressure decreases, the boiling point will also decrease. Therefore, by means of the pressure reducing valve 21, it is possible to ensure that the radioactive waste liquid entering the separation device 2 boils, and further improve the utilization rate of the heat source of the heating device 1, thereby indirectly reducing the energy consumption of the radioactive waste liquid treatment system.

[0031] In some embodiments, during the actual treatment of radioactive waste liquid, the opening of the pressure reducing valve 21 can be adjusted to prevent the radioactive waste liquid in the liquid channel 11 from boiling, and boiling will only occur after entering the separation device 2. Understandably, if the radioactive waste liquid in the liquid channel 11 boils, some of the steam generated by boiling will remain in the liquid channel 11. Since gas-to-gas heat exchange is less efficient than gas-to-liquid heat exchange, the efficiency of heat exchange between the radioactive waste liquid in the liquid channel 11 and the gas in the gas channel 12 is reduced. In this embodiment, adjusting the opening of the pressure reducing valve 21 ensures that the radioactive waste liquid in the liquid channel 11 does not boil, thereby improving the utilization rate of the heat source and reducing energy consumption.

[0032] In some embodiments, refer to Figure 2 The radioactive waste treatment system may also include a steam generator 6, which is connected to the inlet of the gas flow channel 12, allowing the steam generated by the steam generator 6 to enter the gas flow channel 12 as a second heat source for the heating device 1. The steam generator 6 can be any suitable device capable of heating and vaporizing water to generate steam, and there are no limitations on this.

[0033] In this embodiment, the steam generator 6 can serve as a second heat source for the heating device 1 to supplement the compressed steam. Thus, as described above, it can serve as a heat source for the heating device 1 before the compressed steam is generated, or it can serve as a heat source for the heating device 1 together with the compressed steam during the processing.

[0034] In some embodiments, in addition to the steam generator 6, the heating device 1 may also be configured with other heat sources, which will not be described in detail here.

[0035] Understandably, in the above embodiments, the heating efficiency of the heating device 1 is actually controlled by the operating parameters of the steam compression device 4 and the steam generator 6. In the actual process of radioactive waste liquid treatment, the heating efficiency of the heating device 1 can be adjusted by adjusting either of them.

[0036] In some embodiments, it is understood that the steam in the gas channel 12 will condense into liquid after heat exchange with the radioactive waste liquid, and the gas channel 12 can be connected to the inlet of the steam generator 6, so that the condensate in the gas channel 12 can enter the steam generator 6 as a water source for the steam generator 6. In addition to the condensate, the steam generator 6 may also have other water sources to ensure that the steam generator 6 can continuously generate a sufficient amount of steam.

[0037] Understandably, a large amount of residual heat remains in the condensate. In this embodiment, the condensate is introduced into the steam generator 6 as a water source, so that the residual heat in the condensate can be fully utilized, thereby reducing the energy required for the steam generator 6 to generate steam, and thus reducing the energy consumption of the radioactive waste liquid treatment system.

[0038] In some embodiments, the steam generator 6 may be disposed below the heating device 1, so that the condensate in the heating device 1 may flow into the steam generator 6 by gravity.

[0039] In some other embodiments, it may be necessary to place the steam generator 6 and the heating device 1 on the same horizontal plane to reduce the height of the entire radioactive waste treatment system. In this case, it may be necessary to use a condensate pump 61 to pump the condensate in the heating device 1 to the steam generator 6.

[0040] Specifically, the condensate pump 61 can be connected to the bottom of the gas flow channel 12 of the heating device 1, so that the condensate deposited at the bottom of the gas flow channel 12 will be pumped to the steam generator 6.

[0041] In some embodiments, it is understood that the formation of condensate requires a certain heat exchange time. If the condensate pump 61 is always turned on for pumping, the condensate pump 61 may be idling most of the time. Therefore, a level switch can be set at the condensate pump 61. The level switch can automatically turn on the condensate pump 61 when it senses that the condensate level in the gas flow channel 12 has reached a certain height, and turn off the condensate pump 61 in other cases, thereby avoiding the condensate pump 61 from idling.

[0042] In some embodiments, the radioactive waste treatment system may further include a preheating device 7, which may be disposed between the feeding device 5 and the heating device 1, and is capable of preheating the radioactive waste entering the liquid flow channel 11 from the feeding device 5. Understandably, the radioactive waste stays in the liquid flow channel 11 for a limited time during one cycle, which may not be sufficient to raise its temperature to the boiling point. Therefore, in this embodiment, the radioactive waste is preheated to improve the efficiency of radioactive waste treatment. The preheating device 7 may be a heat exchanger or other device with heat exchange or heating functions, and there are no limitations on this.

[0043] In some embodiments, the steam generator 6 can be connected to the preheating device 7, allowing the condensate in the steam generator 6 to enter the preheating device 7 as a heat source. Specifically, the preheating device 7 can have two liquid channels, through which the condensate and the radioactive waste liquid can flow, respectively, allowing the condensate and the radioactive waste liquid to exchange heat.

[0044] As described above, there is also residual heat energy in the condensate. In this embodiment, the condensate is used as a heat source for preheating, thereby making fuller use of the residual heat energy and reducing the energy consumption of the radioactive waste liquid treatment system.

[0045] In some embodiments, during the actual treatment of radioactive waste liquid, the flow rate of condensate introduced into the preheating device 7 can be determined by monitoring the temperature of the radioactive waste liquid at the outlet of the preheating device 7. For example, if the temperature of the radioactive waste liquid is lower than the desired preheating temperature, the flow rate of the condensate introduced into the preheating device 7 can be increased.

[0046] Understandably, if the flow rate of condensate introduced into the preheating device 7 is too high, the water level in the steam generator 6 may be too low, potentially resulting in insufficient steam generation in the steam generator 6. Therefore, in some embodiments, the water level in the steam generator 6 can be further monitored. If the temperature of the radioactive waste liquid is lower than the desired preheating temperature, and the water level in the steam generator 6 is lower than a preset water level, the preheated temperature can be increased by reducing the rate at which the radioactive waste liquid is introduced from the feeding device 5 into the preheating device 7.

[0047] In some embodiments, the radioactive waste treatment system further includes a condensate recovery device 62, which can be connected to the preheating device 7 to recover the condensate in the preheating device 7.

[0048] In some embodiments, refer to Figure 3The steam generated by the steam generator 6 can also be introduced into the inlet of the steam compressor 4. Understandably, the steam compressor 4 is equipped with a compressor, and when the compressor flow rate decreases, or when the pressure difference between the inlet and outlet is large, surge may occur, which will severely affect the performance or service life of the steam compressor 4. In this embodiment, the steam generated by the steam generator 6 is also introduced into the inlet of the steam compressor 4, thereby supplementing the steam flow when the steam flow rate separated by the separator 2 is low, ensuring the steam flow rate at the inlet of the steam compressor 4, and avoiding surge.

[0049] In some embodiments, a make-up air valve may be installed in the passage between the vapor compressor 4 and the steam generator 6. During the actual treatment of radioactive waste, the operating current of the vapor compressor 4 can be monitored. When the change in the operating current of the vapor compressor 4 exceeds a preset threshold, i.e., when abnormal fluctuations occur, the make-up air valve is opened to introduce steam from the steam generator 6 into the inlet of the vapor compressor 4 to prevent surge. In some other embodiments, the need to open the make-up air valve for make-up air can also be determined by monitoring the pressure and gas flow rate at the inlet of the vapor compressor 4.

[0050] Furthermore, when the steam flow rate at the inlet of the vapor compressor 4 decreases, it means that the heating device 1 is less efficient, resulting in a lower steam flow rate separated by the separation device 2. At this time, as described above, the efficiency of radioactive waste liquid concentration can be controlled by adjusting the operating parameters of the vapor compressor 4 and / or the steam generator 6, thereby adjusting the steam flow rate.

[0051] For example, when the steam flow rate at the inlet of the steam compressor 4 decreases, the rotational speed of the steam compressor 4 can be increased. Alternatively, when the steam flow rate at the inlet of the steam compressor 4 decreases, the power of the steam generator 6 can be increased. When the steam flow rate at the inlet of the steam compressor 4 increases, the rotational speed of the steam compressor 4 can be decreased. Alternatively, when the steam flow rate at the inlet of the steam compressor 4 increases, the power of the steam generator 6 can be decreased.

[0052] In some embodiments, when the steam flow rate at the inlet of the steam compressor 4 decreases, the gas pressure in the separator 2 can be detected. If the gas pressure in the separator 2 is higher than a preset pressure, the rotational speed of the steam compressor 4 can be increased; if the gas pressure in the separator 2 is lower than the preset pressure, the power of the steam generator 6 can be increased. In this embodiment, the gas pressure in the separator 2 is used to select which device's parameters to adjust, thereby improving the effectiveness of control.

[0053] In some embodiments, the condensate in the steam generator 6 can be further introduced to the outlet of the steam compressor 4 to perform a certain spray cooling treatment on the compressed steam. Understandably, the compressed steam may be compressed into superheated steam. Compared to saturated steam, superheated steam has a lower pressure, but superheated steam does not significantly improve the working efficiency of the heating device 1. Therefore, in this embodiment, the compressed steam is subjected to a certain spray treatment to prevent the formation of superheated steam, thereby avoiding excessively low pressure at the outlet of the steam compressor 4 and the occurrence of surge without affecting the heating efficiency of the heating device 1.

[0054] In some embodiments, the pressure at the outlet of the steam compressor and the steam temperature of the compressed steam after spraying are monitored. If the steam temperature is greater than the saturated steam temperature at the current pressure at the outlet of the steam compressor, the amount of condensate sprayed onto the compressed steam is increased. If the steam temperature is less than the saturated steam temperature at the current pressure, the amount of condensate sprayed is reduced, or spraying is not performed, thereby avoiding excessive spraying that could affect the working efficiency of the heating device 1.

[0055] In some embodiments, it may be necessary to control the liquid level in the separation device 2 so that the radioactive waste liquid boils at a suitable liquid level to achieve better separation. For example, the liquid level in the separation device 2 can be adjusted by adjusting the power of the circulating pump 3, or by adjusting the feeding efficiency of the feeding device 5.

[0056] In some embodiments, when the liquid level in the separation device 2 rises, the rate at which exothermic waste liquid is introduced from the feeding device 5 into the heating device 1 can be reduced. When the liquid level in the separation device 2 falls, the rate at which radioactive waste liquid is introduced from the feeding device 5 into the heating device 1 can be increased.

[0057] In some embodiments, refer to Figure 4 The feeding device 5 may be equipped with a first pipe 51 connected to the heating device 1. This first pipe 51 is used to introduce radioactive waste liquid into the heating device 1. A second pipe 52 connected to the feeding device 5 is provided on the first pipe 51. The second pipe 52 is used to allow a portion of the radioactive waste liquid in the first pipe 51 to flow back into the feeding device 5. In this embodiment, the rate at which the radioactive waste liquid is introduced into the heating device 1 can be adjusted by regulating the rate at which the radioactive waste liquid flows back into the feeding device 5 from the first pipe 51. As an example, a valve may be provided on the second pipe 52, and the rate at which the radioactive waste liquid flows back into the feeding device 5 can be adjusted by regulating the opening degree of this valve.

[0058] Compared to directly adjusting the flow rate in the first pipeline 51, the adjustment method provided in this embodiment can avoid sudden changes in the flow rate, pressure, temperature, etc. of the radioactive waste liquid entering the radioactive waste liquid treatment system.

[0059] In some embodiments, refer to Figure 5 The radioactive waste treatment system may also include a purification device 8, which is disposed between the separation device 2 and the vapor compression device 4. The purification device 8 is used to purify the steam separated by the separation 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. This steam will subsequently become condensate and be recovered. However, this steam may contain some radioactive materials. Therefore, in this embodiment, a purification device 8 is provided to purify this steam to remove the radioactive materials entrained in the steam and prevent the radioactivity content of the condensate from exceeding the standard.

[0060] Those skilled in the art can specifically configure the purification method of the purification device 8 according to actual needs. For example, the purification device 8 may be equipped with nozzles that can spray the steam entering the purification device 8 to remove radioactive substances entrained therein. Alternatively, the purification device 8 may be equipped with structures with filtration functions such as wire mesh and packing material, which can filter and adsorb radioactive substances entrained in the steam.

[0061] In some embodiments, a structure with filtration function, such as a wire mesh or packing, may also be provided on the top of the separation device 2, which can pre-purify the steam before it enters the purification device 8, thereby further improving the purification effect.

[0062] In some embodiments, as described above, the purification device 8 may be equipped with a nozzle 81, which can spray the steam entering the purification device 8. Understandably, the liquid temperature used for spraying should not be too low to avoid condensation of a large amount of steam and resulting in heat waste. Therefore, in some embodiments, condensate from the steam generator 6 can be introduced into the purification device 8 as spray water. As described above, this condensate has residual heat, which can prevent condensation of a large amount of steam during spraying.

[0063] The residual spray water after the spraying treatment may contain a large amount of radioactive material. Therefore, in some embodiments, the spray water after the spraying treatment can be introduced into the feeding device 5 to avoid radioactive leakage.

[0064] In some embodiments, refer to Figure 6After spraying, the water that drips to the bottom of the purification device 8 can be reintroduced into the nozzle 81 for spraying, thereby avoiding the introduction of too much condensate into the nozzle 81 for spraying and reducing heat waste.

[0065] In this embodiment, the spray water at the bottom of the purification device 8 can be introduced into the feeding device 5 at predetermined intervals. Furthermore, after the liquid at the bottom of the purification device 8 is introduced into the feeding device, the condensate in the steam generator 6 can be introduced into the nozzle 81 to replenish the liquid used for the spray treatment.

[0066] Understandably, during the circulation of the spray liquid, some steam may condense, causing the height of the spray liquid to rise, which in turn affects the purification efficiency. Therefore, in some embodiments, the pressure difference between the inlet and outlet of the purification device 8 can be monitored. When the pressure difference is greater than the preset pressure difference, part of the condensate at the bottom of the purification device 8 can be introduced into the feeding device 5, thereby ensuring that the purification device 8 always has a high purification efficiency.

[0067] In some embodiments, refer to Figure 7 The radioactive waste treatment system may also include a vacuum pump 9, which is connected to the separation device 2 and is used to extract gas from the separation device 2 to create a negative pressure environment within the separation device 2. Understandably, creating a negative pressure environment within the separation device 2 helps to further improve the boiling efficiency of the radioactive waste within the separation device 2.

[0068] In some embodiments, a first suction port 91 may be provided at the outlet of the separation device 2, and a second suction port 92 may be provided on the gas flow channel 12 of the heating device 1. The vacuum pump 9 can extract gas from the first suction port 91 and / or the second suction port 92 to create a negative pressure environment. The first suction port 91 and the second suction port 92 provided in this embodiment help to improve the efficiency of creating a negative pressure environment.

[0069] In some embodiments, the negative pressure environment can be established before the introduction of radioactive waste liquid. In some embodiments, the gas pressure in the separation device 2 can also be monitored during the treatment of radioactive waste liquid. If the gas pressure is higher than the desired negative pressure, a certain amount of gas can be extracted from the above-mentioned extraction port to maintain the negative pressure environment.

[0070] In some embodiments, the vacuum pump 9 can also be used to extract non-condensable gases from the heating device 1. As described above, the gas entering the heating device 1 condenses into condensate after heat exchange. However, some non-condensable gases may be mixed into the heating device 1. When a large amount of non-condensable gases accumulate in the heating device 1, the overall temperature of the gas in the heating device 1 will decrease, thereby affecting the heating efficiency of the heating device 1. Therefore, the vacuum pump 9 can be used to extract the non-condensable gases from the heating device 1 to avoid their accumulation. Specifically, the non-condensable gases can be extracted from the second extraction port 92 described above.

[0071] In some embodiments, non-condensable gas can be extracted once at predetermined intervals, or the temperature of the liquid in the separation device 2 can be monitored. If the temperature of the liquid in the separation device 2 is lower than the evaporation temperature, it means that the heating efficiency is reduced. At this time, the vacuum pump 9 can be turned on to extract the non-condensable gas in the heating device 1.

[0072] Understandably, whether constructing a negative pressure environment or extracting non-condensable gases, the extracted gas contains a large amount of vapor, which may condense in the vacuum pump 9, thus affecting the working efficiency and lifespan of the vacuum pump 9. Therefore, in some embodiments, the radioactive waste liquid treatment system may also include a cooling device 93, which is disposed in the passage between the vacuum pump 9 and the separation device 2. The cooling device 93 is used to cool the gas extracted by the vacuum pump 9 to recover the vapor in the gas extracted by the vacuum pump 9 as condensate.

[0073] In some embodiments, it is understood that when the power of the vacuum pump 9 is high, it may also remove some of the condensate in the cooling device 93. Therefore, refer to... Figure 8 A buffer tank 94 can be provided between the vacuum pump 9 and the cooling device 93. The buffer tank 94 is used to store condensate and prevent condensate from being drawn into the vacuum pump 9.

[0074] 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 is connected to the vacuum pump 9 and the cooling device 93. The second buffer tank 942 is located below the first buffer tank 941. The first valve 943 is located at the connection between the first buffer tank 941 and the second buffer tank 942. The second valve 944 is configured to connect the second buffer tank 942 to the atmosphere.

[0075] Understandably, during the evacuation process, if the buffer tank is completely sealed, the vacuum pump 9 may be unable to continuously extract gas due to air pressure issues. If the buffer tank is connected to the atmosphere, the gas flow channel 12 of the separation device 2 and the heating device 1 may be directly connected to the atmosphere, which may pose a risk of radioactive leakage. Therefore, this embodiment is provided with two buffer tank structures.

[0076] 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 can be closed. When the condensate level in the first buffer tank 941 is higher than the preset value, it means that the pressure in the first buffer tank 941 is already high. At this time, the second valve 944 can be closed and the first valve 943 can be opened, allowing the condensate in the first buffer tank 941 to enter the second buffer tank 942, thereby releasing the pressure in the first buffer tank 941.

[0077] Once all the condensate in the first buffer tank 941 has entered the second buffer tank 942, the first valve 943 can be closed and the second valve 944 opened to balance the pressure in the second buffer tank 942. Thus, when a large amount of condensate accumulates in the first buffer tank 941 next time, the second valve 944 can still be closed and the first valve 943 opened to release the pressure in the first buffer tank 941.

[0078] In this embodiment, the first valve 943 and the second valve 944 will not be opened at the same time, thereby ensuring that the vacuum pump 9 can continuously extract gas and that the separation device 2, gas flow channel 12, etc. will not be directly connected to the atmospheric environment.

[0079] In some embodiments, the second buffer tank 942 may be connected to the condensate recovery device 62, and a third valve 945 is provided at the connection point between the second buffer tank 942 and the condensate recovery device 62. In this embodiment, after the condensate in the first buffer tank 941 enters the second buffer tank 9421, the first valve 943 can be closed and the second valve 944 and the third valve 945 can be opened to introduce the condensate in the second buffer tank 942 into the condensate recovery device 62.

[0080] In some embodiments, the vacuum pump 9 may be connected to a filter device 95, which may be connected to an exhaust pipe 96. The filter device 95 may be used to filter radioactive substances in the gas drawn by the vacuum pump 9, while the exhaust pipe 96 may be used to discharge the filtered gas.

[0081] In some embodiments, the exhaust pipe 96 may be configured as a segmented structure, wherein the segments are detachable from each other or can slide relative to each other, so that the segments of the exhaust pipe 96 can be detached or folded together without radioactive waste treatment, so as to avoid its height restricting its movement.

[0082] In some embodiments, refer to Figure 9 and Figure 10 The radioactive waste treatment system also includes a support platform 100, which can be placed horizontally, and the aforementioned devices can be fixed on the support platform 100. In this embodiment, the aforementioned devices are fixed on the same horizontal plane, thereby reducing the height of the radioactive waste treatment system in the vertical plane, making the overall structure of the radioactive waste treatment system more compact and convenient for arrangement in relatively small spaces.

[0083] In some embodiments, the support platform 100 can be fixed to a movable platform, thereby making the entire radioactive waste treatment system mobile and allowing its application scenarios to extend beyond a factory building. The movable platform can be a vehicle equipped with a cargo compartment, in which the support platform 100 and the aforementioned devices can be fixed. As described above, the devices in the radioactive waste treatment system of this embodiment are fixed on the same horizontal plane, ensuring that the overall radioactive waste treatment system of this embodiment meets the height restrictions for vehicle travel, thus enabling it to freely travel on roads to the required locations for radioactive waste treatment.

[0084] In some embodiments, the liquid flow channel 11 and gas flow channel 12 of the heating device 1 described above are arranged parallel to the support platform 100. That is, the heating device 1 adopts a horizontal design, thereby ensuring that the liquid flow channel 11 and gas flow channel 12 are long enough to meet the height requirements.

[0085] In some embodiments, the feeding device 5, heating device 1, separating device 2 and steam compression device 4 may be arranged sequentially along the first direction of the support platform 100.

[0086] Furthermore, in some embodiments, the steam generator 6 and the steam compressor 4 may be arranged side by side along the second direction of the support platform 100.

[0087] Understandably, compared to the feeding device 5, heating device 1, and separation device 2, the radioactivity content in the steam compression device 4 and steam generator 6 is lower. Therefore, by placing the steam compression device 4 and steam generator 6 side by side on one side of the above three devices, the entire radioactive waste liquid treatment system is divided into high-radioactivity and low-radioactivity areas, which helps to ensure the safety of operators.

[0088] In some embodiments, the radioactive waste treatment system may include a partition extending in a second direction, with the steam generator 4 and the steam compressor 6 disposed on the side of the partition away from the separation device 2. In this embodiment, the partition further isolates low-radioactive devices such as the steam generator 4 and the steam compressor 6 from high-radioactive devices, thereby ensuring safety. As described above, the support platform 100 and the aforementioned devices can be housed within a vehicle compartment, and the partition can be sealed to the compartment, thus placing the low-radioactive devices such as the steam generator 4 and the steam compressor 6 in two relatively sealed partitions from the high-radioactive devices.

[0089] In some embodiments, the condensate recovery device 62 may be located on the side of the vapor compression device 4 away from the separation device 2, that is, it is also located in the partition where the low radioactivity device is located.

[0090] In some embodiments, the circulating pump 3 and the purification device 8 may be arranged on both sides of the heating device 1 along the second direction of the support platform 100. In some embodiments, the preheating device 7 may be arranged between the feeding device 5 and the purification device 8.

[0091] In some embodiments, some devices that do not have control equipment and electrical equipment, such as electrical cabinets that provide power to the above-mentioned devices, and controllers that control the start-up and operation of the above-mentioned devices and monitor the operating parameters of the above-mentioned devices, may also be installed on the support platform 100. Since these devices are not radioactive, they can be installed on the side away from the separation device 2 of the steam generator 4, steam compressor 6, condensate recovery device 62, etc., and can also be isolated from the above-mentioned devices by means of partitions. Thus, the entire radioactive waste liquid treatment system is divided into three areas: a high-radioactivity zone, a low-radioactivity zone, and a non-radioactivity zone.

[0092] As described above, there are multiple pipelines between the above-mentioned devices. Some pipelines are used for the transfer of condensate, and some pipelines are used for the extraction and transfer of gas. In some embodiments, the pipelines for transferring condensate can be arranged along the surface of the support platform 100, while the pipelines for extracting and transferring gas can be arranged along the top surface of each of the above-mentioned devices.

[0093] In some embodiments, refer to Figure 10The support platform 100 includes a support plate 110 and a support frame 120. The support frame 120 is disposed above the support plate 110 and forms a gap between the support frame 120 and the support plate 110. In this embodiment, the aforementioned devices can be connected to the support frame 120. It is understood that leakage may occur during the operation of the aforementioned devices. Since there is a gap between the support frame 120 and the support plate 110, the leaked liquid can be collected in the gap, preventing it from flowing around.

[0094] In some embodiments, the side of the support plate 110 facing the support frame 120 is angled. Thus, liquid leaking into the aforementioned gap will flow along this angle to a corner of the support plate 110, facilitating the collection of the leaked liquid.

[0095] Specifically, the tilt angle of the support plate 110 can be a very small angle, while the support surface of the support frame 120 can be horizontal to ensure the stability of the support for the above-mentioned devices.

[0096] The present invention has been described in detail above with reference to the accompanying drawings and embodiments. However, the present invention is not limited to the above embodiments, and various changes can be made within the scope of knowledge possessed by those skilled in the art without departing from the spirit of the present invention. All contents not described in detail in the present invention can be derived from existing technologies.

Claims

1. A radioactive waste liquid treatment system, comprising: The support platform is placed horizontally. A heating device is fixed on the support platform. The heating device has a liquid flow channel for the flow of radioactive waste liquid and a gas flow channel outside the liquid flow channel. The gas flowing in the gas flow channel can exchange heat with the radioactive waste liquid in the liquid flow channel to heat the radioactive waste liquid. A separation device is fixed on the support platform. The separation device is used to separate the vapor from the radioactive waste liquid that has been boiled after heat treatment, so as to concentrate the radioactive waste liquid. A circulation pipeline extends along the surface of the support platform, connecting the separation device and the inlet of the liquid flow channel; A circulation pump is fixed on the support platform and installed in the circulation pipeline. The circulation pump is used to drive the radioactive waste liquid to circulate between the heating device and the separation device through the circulation pipeline. A vapor compression device is fixed on the support platform and disposed between the separation device and the inlet of the gas flow channel. The vapor compression device is used to compress and heat the vapor separated by the separation device to obtain compressed vapor and introduce the compressed vapor into the gas flow channel as the first heat source of the heating device. A feeding device is fixed on the support platform, and the feeding device is used to introduce the radioactive waste liquid into the liquid channel of the heating device; The discharge port is located in the circulation pipeline and is used to draw out the concentrated radioactive waste liquid. A vacuum pump, connected to the separation device, is used to extract gas from the separation device to create a negative pressure environment in the separation device; A cooling device is installed in the passage between the vacuum pump and the separation device to cool the gas drawn by the vacuum pump, so as to recover the vapor in the gas drawn by the vacuum pump as condensate. A buffer tank is disposed between the vacuum pump and the cooling device to store the condensate and prevent the condensate from being drawn into the vacuum pump.

2. The system of claim 1, wherein, The liquid flow channel and the gas flow channel are arranged parallel to the support platform.

3. The system of claim 1, wherein, The feeding device, the heating device, the separating device, and the steam compression device are arranged sequentially along the first direction of the support platform.

4. The system according to claim 3, further comprising: A steam generator is connected to the inlet of the gas flow channel, so that the steam generated by the steam generator can enter the gas flow channel to serve as a second heat source for the heating device.

5. The system of claim 4, wherein, The steam generator and the steam compressor are arranged side by side along the second direction of the support platform.

6. The system according to claim 5, further comprising: A partition extending along the second direction, wherein the steam generating device and the steam compressing device are disposed on the side of the partition away from the separation device.

7. The system of claim 4, wherein, The gas flow channel is connected to the inlet of the steam generator so that the condensate in the gas flow channel can serve as the water source for the steam generator. The condensate is generated after the gas in the heating device exchanges heat with the radioactive waste liquid.

8. The system according to claim 7, further comprising: A preheating device is provided between the feeding device and the heating device for preheating the radioactive waste liquid that enters the liquid channel from the feeding device; a steam generator is connected to the preheating device so that the condensate in the steam generator can enter the preheating device as a heat source for the preheating device.

9. The system according to claim 8, further comprising: A condensate recovery device is connected to the preheating device, and the condensate recovery device is used to recover the condensate in the preheating device.

10. The system of claim 9, wherein, The condensate recovery device is located on the side of the vapor compression device away from the separation device.

11. The system according to claim 3, further comprising: A purification device is installed on the support platform, and the purification device is used to purify the steam separated by the separation device before it enters the steam compression device.

12. The system of claim 11, wherein, The circulating pump and the purification device are arranged on both sides of the heating device along the second direction of the support platform.

13. The system according to claim 1, further comprising: A mobile platform, wherein the support platform is mounted on the mobile platform.

14. The system of claim 1 or 13, wherein, The support platform includes: A support frame and a support plate, wherein the support frame is disposed above the support plate and forms a gap between the support frame and the support plate.

15. The system of claim 14, wherein, The side of the support plate facing the support frame is inclined.

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