CN115966329A - Radioactive waste liquid treatment method and system - Google Patents

Abstract

The embodiment of the application provides a radioactive liquid waste treatment method, which comprises the following steps: driving the radioactive waste liquid to circulate between a heating device and a separating device by a circulating pump, wherein the heating device is used for heating the radioactive waste liquid so as to evaporate the radioactive waste liquid in the separating device, the separating device is used for separating steam generated when the radioactive waste liquid is evaporated so as to concentrate the radioactive waste liquid, and a negative pressure environment is arranged in the separating device; in the circulating process, the vapor separated by the separation device is compressed and heated by the vapor compression device to obtain compressed vapor, and the compressed vapor is introduced into the heating device to be used as a first heat source of the heating device, so that the radioactive waste liquid can be continuously concentrated; after determining that the radioactive waste liquid has been concentrated by the predetermined factor, the radioactive waste liquid is led out of the heating device and the separating device. The embodiment of the application also provides a radioactive liquid waste treatment system.

Description

Radioactive waste liquid treatment method and system

technical field

The present application relates to the technical field of radioactive material processing, in particular to a radioactive waste liquid processing method and system.

Background technique

A large amount of radioactive waste liquid is often produced in process engineering related to nuclear technology, and these radioactive waste liquids need to be concentrated. Evaporation is usually used to complete the concentration of radioactive waste liquid. However, the radioactive waste liquid used in related technologies The process flow of liquid treatment has high energy consumption.

Contents of the invention

In order to solve at least one technical problem in the prior art and other aspects, the present application provides a radioactive waste liquid treatment method and system.

According to the first aspect of the embodiments of the present application, there is provided a radioactive waste liquid treatment method, comprising: using a circulation pump to drive the radioactive waste liquid to circulate between the heating device and the separation device, wherein the heating device is used to treat the radioactive waste liquid Heat treatment to evaporate the radioactive waste liquid in the separation device. The separation device is used to separate the steam generated during the evaporation of the radioactive waste liquid so that the radioactive waste liquid can be concentrated. The separation device is in a negative pressure environment; during the cycle, Use the steam compression device to compress and heat up the steam separated by the separation device to obtain compressed steam, and introduce the compressed steam into the heating device as the first heat source of the heating device, so that the radioactive waste liquid can be continuously concentrated; when it is determined that the radioactive waste liquid has been concentrated by a predetermined multiple Finally, the radioactive waste liquid is led out of the heating device and the separation device.

According to the second aspect of the embodiment of the present application, there is provided a radioactive waste liquid treatment system, including: a heating device, the heating device is formed with a liquid flow channel for the flow of the radioactive waste liquid, and a gas flow channel arranged 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; the separation device is used to separate the vapor in the heated radioactive waste liquid to make the radioactive waste liquid Waste liquid concentration; circulation pipeline, which connects the separation device and the inlet of the liquid flow channel; circulation pump, arranged in the circulation pipeline, and the circulation pump is used to drive the radioactive waste liquid through the circulation pipeline between the heating device and the separation device The vapor compression device is arranged between the separation device and the inlet of the gas flow channel. The vapor compression device is used to compress and heat up the steam separated by the separation device to obtain compressed steam. The compressed steam can be introduced into the gas flow channel to As the first heat source of the heating device; the vacuum pump communicates with the separation device, and the vacuum pump is used to extract the gas in the separation device to build a negative pressure environment in the separation device; the feeding device communicates with the heating device, and the feeding device is used for supplying The radioactive waste liquid is passed into the liquid channel of the heating device; the discharge port is arranged in the circulation pipeline, and the discharge port is used to lead out the concentrated radioactive waste liquid.

The radioactive waste liquid treatment method and system provided in the embodiments of the present application can significantly reduce the energy consumption during the evaporation and concentration treatment of the radioactive waste liquid.

Description of drawings

1 is a schematic diagram of a radioactive waste liquid treatment system according to an embodiment of the present application;

2 is a schematic diagram of a radioactive waste liquid treatment system according to another embodiment of the present application;

3 is a schematic diagram of a radioactive waste liquid treatment system according to another embodiment of the present application;

4 is a schematic diagram of a radioactive waste liquid treatment system according to another embodiment of the present application;

5 is a schematic diagram of a radioactive waste liquid treatment system according to another embodiment of the present application;

6 is a schematic diagram of a radioactive waste liquid treatment system according to another embodiment of the present application;

7 is a schematic diagram of a radioactive waste liquid treatment system according to another embodiment of the present application;

8 is a schematic diagram of a buffer tank according to an embodiment of the present application;

9 is a schematic layout diagram of a radioactive waste liquid treatment system according to an embodiment of the present application;

Fig. 10 is a schematic diagram of a support structure according to an embodiment of the present application.

Detailed ways

In order to make the purpose, technical solutions and advantages of the present application clearer, the present application will be further described in detail below in conjunction with specific embodiments and with reference to the accompanying drawings.

Embodiments of the present application firstly provide a radioactive waste liquid treatment system. Referring to FIG.

The heating device 1 is used for heating the radioactive waste liquid so that it can reach boiling temperature. The heating device 1 can be a heat exchanger. For example, the heating device 1 can be formed with a liquid flow channel 11 for the flow of radioactive waste liquid, and a gas flow channel 12 arranged outside the liquid flow channel 11. During the process, the gas flowing in the gas flow channel 12 can exchange heat with the radioactive waste liquid flowing in the liquid flow channel 11, so as to perform heat treatment on the radioactive waste liquid. The specific arrangement of the liquid channel 11 and the gas channel 12 can refer to the heat exchanger provided in the related art in this field, and will not be repeated here.

The separation device 2 communicates with the liquid 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 be boiled in the separation device 2, and the vapor formed during boiling is absorbed by the separation device. 2, so that the radioactive waste liquid is concentrated. The separation device 2 can be formed with a cavity, and the top of the cavity can be formed with a gas outlet, and 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 flow out of the cavity. The gas outlet at the top of the chamber leaves the separation device 2, so that the radioactive waste liquid is concentrated, and the concentrated radioactive waste liquid will be deposited at the bottom of the cavity.

The separation device 2 can also communicate with the inlet of the liquid flow channel 11 by means of the circulation pipeline 31, and the circulation pump 3 can be arranged on the circulation pipeline 31. When the radioactive waste liquid is processed, under the drive of the circulation pump 3, the concentrated residual The radioactive waste liquid can return to the liquid 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-mentioned concentration process.

The vapor compression device 4 is arranged between the separation device 2 and the inlet of the gas flow channel 12, which can compress and heat up the steam separated by the separation device 2, and introduce it into the gas flow channel of the heating device 1, thereby serving as a heating device 1 for a heat source.

It can be understood that there is still a large amount of residual heat energy in the steam separated by the separation device 2, but its residual heat energy is not enough to heat the radioactive waste liquid to boiling, and the vapor compression device 4 can decompress the steam separated by the separation device 2. Compression treatment is carried out, so that it has the ability to heat the radioactive waste liquid to boiling again, thus, the residual heat energy in the steam separated by the separation device 2 is fully recovered and utilized, and indirectly reduces the process of radioactive waste liquid treatment. energy consumption.

The heating device 1 can be configured with multiple heat sources, that is, in addition to the compressed steam generated by the vapor compression device 4, it can also be configured with other heat sources, and the other heat sources can be hot steam generated by other devices, or set Some heating components in the heating device 1, etc., and other heat sources can be used as a supplement and substitute to provide the heat required for the evaporation of the radioactive waste liquid together with the compressed steam. If the amount of compressed steam is small or even does not exist, other heat sources can be used to heat the radioactive waste liquid.

The feeding device 5 communicates with the liquid channel 11 of the heating device 1 , so as to feed radioactive waste liquid into the heating device 1 . In some embodiments, the feeding device 5 can communicate with the circulation pipeline 31 , that is, indirectly communicate with the liquid channel 11 via the circulation pipeline 31 . In some other embodiments, the feeding device 5 may also directly communicate with the liquid channel 11 without the circulation pipeline 31 . A feed pump may be arranged on the feed device 5 to provide power for the flow of the radioactive waste liquid.

In the actual process of treating radioactive waste liquid, the radioactive waste liquid in the feeding device 5 can be continuously introduced into the liquid flow channel 11 at a certain rate, or it can also be introduced after a certain amount of radioactive waste liquid After the radioactive waste liquid that has been introduced is concentrated and drawn out, the next batch of radioactive waste liquid is introduced, and there is no limit to this. It can be understood that in the embodiment of continuous feeding, the operation is relatively simple, but it may be difficult to accurately control the concentration ratio of the radioactive waste liquid. Feed in batches can control the concentration ratio of the radioactive waste liquid more accurately, but it requires operators to perform frequent operations.

A discharge port 32 may be provided on the circulation pipeline 31 , and when the radioactive waste liquid has been concentrated by a desired multiple, the concentrated radioactive waste liquid may be drawn out by means of the discharge port 32 .

During the actual process of radioactive waste treatment, sampling can be carried out at the discharge port 32 to determine whether the radioactive waste has been concentrated to the expected multiple, and/or, can be determined according to the actual treatment efficiency of the radioactive waste treatment system Calculate the time required to concentrate to the expected multiple, and determine whether the radioactive waste liquid has been concentrated to the expected multiple according to the time. When the feeding device 5 continuously introduces the radioactive waste liquid, the discharge port 32 can be opened after the radioactive waste liquid has been concentrated by a desired multiple, and the radioactive waste liquid can be continuously drawn out at a certain rate. When the feeding device 5 only introduces a certain amount of radioactive waste liquid, the discharge port 32 can be opened to draw out all the radioactive waste liquid after the radioactive waste liquid has been concentrated by a desired multiple. Those skilled in the art can set according to the actual situation, which will not be repeated here.

In some embodiments, referring to FIG. 1 , a decompression valve 21 can be provided between the outlet of the liquid flow channel 11 of the heating device 1 and the inlet of the separation device 2 , and the decompression valve 21 can make the radioactivity in the heating device 1 After the waste liquid enters the separation device 2, the pressure decreases.

The decompression valve 21 may be any suitable decompression valve provided in the related art, without limitation. The decompression valve 21 can create a pressure difference 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 enters the separation device 2 decreases.

It can be understood that the boiling point of the liquid is related to the pressure. When the pressure drops, the boiling point will also drop. Therefore, the pressure reducing valve 21 can ensure that the radioactive waste liquid entering the separation device 2 boils, and further improve the heating device. 1 of the heat source utilization, thereby indirectly reducing the energy consumption of the radioactive waste liquid treatment system.

In some embodiments, during the actual process of radioactive waste treatment, the opening of the pressure relief valve 21 can be adjusted so that the radioactive waste in the liquid flow channel 11 will not boil, and when it enters the separation device Boiling occurs after 2. It can be understood that if the radioactive waste liquid in the liquid flow channel 11 boils, a part of the steam generated by the boiling will remain in the liquid flow channel 11, and the gas-gas heat exchange is different from the gas-liquid heat exchange. Therefore, 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, but in this embodiment, the opening of the pressure reducing valve 21 can be adjusted to ensure that the liquid channel 11 The radioactive waste liquid in the system will not boil, which improves the utilization rate of the heat source and reduces the energy consumption.

In some embodiments, referring to FIG. 2 , the radioactive waste liquid treatment system may further include a steam generating device 6 , the steam generating device 6 communicates with the inlet of the gas flow channel 12 , so that the steam generated by the steam generating device 6 can enter the gas flow channel 12 , as the second heat source of the heating device 1 . The steam generating device 6 may be any suitable device capable of heating and vaporizing water to generate steam, which is not limited thereto.

In this embodiment, the steam generating device 6 can be used as the second heat source of the heating device 1 to supplement the compressed steam, so that, as described above, it can be used as the heat source of the heating device 1 when the compressed steam has not yet been generated, Or it can be used together with the compressed steam as the heat source of the heating device 1 during the treatment process.

In some embodiments, in addition to the steam generating device 6 , the heating device 1 may also be configured with other heat sources, which will not be repeated here.

It can be understood that in the above embodiment, the heating efficiency of the heating device 1 is actually jointly controlled by the operating parameters of the vapor compression device 4 and the steam generating device 6. In the actual process of radioactive waste liquid treatment, it can be adjusted by Any one of the two is used to adjust the heating efficiency of the heating device 1 .

In some embodiments, it can be understood that the steam in the gas channel 12 will condense to form a liquid after heat exchange with the radioactive waste liquid, and the gas channel 12 can communicate with the inlet of the steam generating device 6, so that the gas The condensate in the flow channel 12 can enter the steam generating device 6 as a water source for the steam generating device 6 . In addition to the condensate, the steam generating device 6 may also have other water sources to ensure that the steam generating device 6 can continuously generate a sufficient amount of steam.

It can be understood that there is still a large amount of residual heat in the condensate, and in this embodiment, the condensate is introduced into the steam generating device 6 as a water source, so that the heat remaining in the condensate can be fully utilized, thereby reducing the generation of steam The energy required for the device 6 to generate steam further reduces the energy consumption of the radioactive waste liquid treatment system.

In some embodiments, the steam generating device 6 can be arranged below the heating device 1 , so that the condensate in the heating device 1 can flow into the steam generating device 6 by gravity.

In some other embodiments, it may be necessary to set the steam generating device 6 and the heating device 1 on the same level to reduce the height of the entire radioactive waste liquid treatment system. At this time, it may be necessary to use the condensate pump 61 to The condensate in the heating device 1 is pumped to the steam generating device 6 .

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 on the bottom of the gas flow channel 12 will be pumped into the steam generating device 6 .

In some embodiments, it can be 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 in an idle state most of the time. Therefore, A liquid level switch can be set at the condensate pump 61, and the liquid level switch can automatically open the condensate pump 61 when sensing that the liquid level of the condensate in the gas flow channel 12 reaches a certain height, and in other cases The condensate pump 61 is turned off in order to avoid idling of the condensate pump 61 .

In some embodiments, the radioactive waste liquid treatment system can also include a preheating device 7, which can be arranged between the feeding device 5 and the heating device 1, and can prevent the liquid from entering the feeding device 5 into the liquid channel. The radioactive waste liquid in 11 is preheated. It can be understood that the radioactive waste liquid stays in the liquid channel 11 for a limited time during a cycle, which may not be enough to raise its temperature to the temperature required for boiling. Therefore, in this embodiment, the radioactive waste liquid is Preheating, thereby improving the efficiency of carrying out radioactive liquid waste. The preheating device 7 may be a heat exchanger, or other devices with heat exchange or heating functions, which is not limited.

In some embodiments, the steam generating device 6 can communicate with the preheating device 7 , so that the condensate in the steam generating device 6 can enter the preheating device 7 as a heat source for the preheating device 7 . Specifically, two liquid passages may be formed in the preheating device 7, and the condensate and the radioactive waste liquid may respectively flow in the two liquid passages, so that the condensate and the radioactive waste liquid exchange heat.

As described above, there is also residual heat energy in the condensate, but in this embodiment, the condensate is used as the heat source for preheating, so that the residual heat energy is more fully utilized, thereby reducing the amount of radioactive waste liquid. Energy consumption of the processing system.

In some embodiments, during the actual process of radioactive waste liquid treatment, the flow rate of the condensate introduced into it 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 If the temperature is lower than the desired preheating temperature, the flow rate of the condensate introduced into the preheating device 7 can be increased.

It can be understood that if the flow rate of the condensate introduced into the preheating device 7 is too large, the water level in the steam generating device 6 may be too low, resulting in that the steam generating device 6 may not be able to generate sufficient steam. For this reason, in some embodiments, the water level in the steam generating device 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 generating device 6 is lower than the preset water level, then The temperature after preheating can be increased by reducing the rate of introducing radioactive waste liquid from the feeding device 5 to the preheating device 7 .

In some embodiments, the radioactive waste liquid treatment system further includes a condensate recovery device 62 , and the condensate recovery device 62 can communicate with the preheating device 7 , so as to recover the condensate in the preheating device 7 .

In some embodiments, referring to FIG. 3 , the steam generated by the steam generating device 6 may also be introduced into the inlet of the vapor compression device 4 . It can be understood that the vapor compression device 4 is equipped with a compressor, and when the flow rate of the compressor decreases, or when the pressure difference between the inlet and the outlet is large, surge may occur, which will make the vapor compression device 4 Performance or service life is seriously affected. However, 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 small, ensuring that the vapor compression device 4 Steam flow at the inlet avoids surge conditions.

In some embodiments, a gas supply valve may be provided on the passage between the vapor compression device 4 and the steam generating device 6, and the operating current of the vapor compression device 4 may be monitored during the actual process of radioactive waste liquid treatment. When the variation of the operating current of the compression device 4 is greater than the preset threshold, that is, when abnormal fluctuations occur, the air supplement valve is opened to introduce the steam of the steam generation device 6 into the inlet of the vapor compression device 4 to avoid panting. Vibration occurs. In some other embodiments, it may also be determined by monitoring the pressure at the inlet of the vapor compression device 4 , the gas flow rate, etc. whether it is necessary to open the gas supplement valve for gas supplementation.

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

For example, when the vapor flow rate at the inlet of the vapor compression device 4 decreases, the rotational speed of the vapor compression device 4 may be increased. Alternatively, when the steam flow rate at the inlet of the vapor compression device 4 decreases, the power of the steam generating device 6 can be increased. When the steam flow at the inlet of the vapor compression device 4 increases, the rotational speed of the vapor compression device 4 can be reduced. Or, when the steam flow at the inlet of the steam compression device 4 increases, the power of the steam generating device 6 can be reduced.

In some embodiments, when the steam flow rate at the inlet of the vapor compression device 4 decreases, the gas pressure in the separation device 2 can be detected, and if the gas pressure in the separation device 2 is higher than a preset pressure, the vapor compression device 4 can be increased. If the gas pressure in the separating device 2 is lower than the preset pressure, the power of the steam generating device 6 can be increased. In this embodiment, the gas pressure in the separation device 2 is used to select which device's parameters should be adjusted, thereby improving the effectiveness of the control.

In some embodiments, the condensate in the steam generation device 6 can be further introduced to the outlet of the vapor compression device 4 to perform a certain spray cooling treatment on the compressed steam. It can be understood that the compressed steam may be compressed into superheated steam. Compared with saturated steam, the pressure of superheated steam is lower, but the superheated steam will not significantly improve the working efficiency of the heating device 1. Therefore, this embodiment In this process, the compressed steam is sprayed to prevent it from forming superheated steam, so as not to affect the heating efficiency of the heating device 1, so as to prevent the pressure at the outlet of the vapor compression device 4 from being too low and causing surge .

In some embodiments, the pressure at the outlet of the vapor compression device is monitored, and the steam temperature of the compressed steam after spraying is monitored. If the steam temperature is greater than the saturated steam temperature at the current pressure at the outlet of the vapor compression device, the compressed steam is increased. The amount of condensate sprayed. If the steam temperature is lower than the saturated steam temperature under the current pressure, the amount of condensate to be sprayed is reduced, or not sprayed, so as to avoid excessive spraying treatment from affecting the working efficiency of the heating device 1 .

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 an appropriate liquid level to obtain a better separation effect. For example, the liquid level in the separation device 2 can be adjusted by adjusting the power of the circulating pump 3 , or the liquid level in the separation device 2 can also be adjusted by adjusting the feeding efficiency of the feeding device 5 .

In some embodiments, the rate at which exothermic waste liquid is introduced from the supply device 5 into the heating device 1 may be reduced as the liquid level in the separation device 2 increases. When the liquid level in the separation device 2 decreases, the rate at which radioactive waste liquid is introduced from the feeding device 5 into said heating device 1 can be increased.

In some embodiments, referring to FIG. 4 , the feeding device 5 can be provided with a first pipeline 51 communicating with the heating device 1 , the first pipeline 51 is used to introduce radioactive waste liquid into the heating device 1 , the first pipe A second pipeline 52 communicating with the feeding device 5 is arranged on the road 51. The second pipeline 52 is used to return part of the radioactive waste liquid in the first pipeline 51 to the feeding device 5. In this embodiment, it can By adjusting the rate at which the radioactive waste liquid in the first pipeline 51 flows back to the feeding device 5 , the rate at which the radioactive waste liquid is introduced into the heating device 1 is adjusted. As an example, a valve may be provided on the second pipeline 52 , and the rate at which the radioactive waste liquid flows back to the feeding device 5 can 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 by 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.

In some embodiments, referring to FIG. 5 , the radioactive waste liquid treatment system may further include a purification device 8, which is arranged between the separation device 2 and the vapor compression device 4, and the purification device 8 is used to enter the vapor separated in the separation device 2 into the steam Compression device 4 is cleaned before it. As described above, the main component of the steam separated by the separation device 2 is water, and these steams will later become condensate and be recovered, and some radioactive substances may be entrained in these steams, therefore, this embodiment A purification device 8 is set in the steam to purify the steam, so as to remove the radioactive substances entrained in the steam and prevent the radioactive content of the condensate from exceeding the standard.

Those skilled in the art can specifically set the purification mode of the purification device 8 according to actual needs. For example, a spray head can be arranged in the purification device 8, which can spray the steam entering the purification device 8 to remove all the impurities in the purification device 8. Entrained radioactive material. Alternatively, the purification device 8 may be provided with structures with filtering functions such as screens and fillers, which can filter and absorb radioactive substances entrained in the steam.

In some embodiments, the top of the separation device 2 can also be provided with a structure with a filtering function such as a screen, packing, etc., which can perform a certain pre-purification on the steam before it enters the purification device 8, further improving the purification effect .

In some embodiments, as described above, a spray head 81 may be provided in the purification device 8 , and the spray head 81 may spray the steam entering the purification device 8 . It can be understood that the temperature of the liquid used in the spray treatment cannot be too low, so as to avoid the waste of heat caused by the condensation of a large amount of steam. For this reason, in some embodiments, the condensed water in the steam generating device 6 can be introduced into the purification device 8 as spray water, as described above, the condensed water has residual heat, which can Also avoid condensation of large quantities of steam.

The residual spray water after spray treatment may contain more radioactive substances. Therefore, in some embodiments, the spray water after spray treatment can be introduced into the feeding device 5 to avoid radioactive leakage. .

In some embodiments, referring to FIG. 6 , after the spray treatment, the spray water dripped at the bottom of the purification device 8 can be reintroduced into the shower head 81 for spraying, thereby avoiding introducing too much condensed water into the shower head 81 for further cleaning. Spray treatment, thereby reducing the waste of heat.

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. Further, after the liquid at the bottom of the purification device 8 is introduced into the feeding device, the condensed liquid in the steam generating device 6 can be introduced into the spray head 81 to supplement the liquid used for the spraying treatment.

It can be understood that during the circulation of the spray liquid, some steam may condense and cause the height of the spray liquid to rise, thereby affecting the purification efficiency. Therefore, in some embodiments, the inlet and outlet of the purification device 8 can also 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.

In some embodiments, referring to FIG. 7 , the radioactive waste liquid treatment system may further include a vacuum pump 9, which communicates with the separation device 2, and is used to extract the gas in the separation device 2 to create a negative pressure environment in the separation device 2. . It can be understood that constructing a negative pressure environment in the separation device 2 helps to further improve the boiling efficiency of the radioactive waste liquid in the separation device 2 .

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

In some embodiments, constructing the negative pressure environment may be performed before introducing the radioactive waste liquid. In some embodiments, the gas pressure in the separation device 2 can also be monitored during the radioactive waste treatment process. If the gas pressure is higher than the expected negative pressure, a certain amount of gas can be extracted from the above-mentioned gas extraction port to maintain Negative pressure environment.

In some embodiments, the vacuum pump 9 can also be used to extract the non-condensable gas in the heating device 1 . As described above, the gas entering the heating device 1 will condense into condensed water after heat exchange, however, some non-condensable gas may be mixed in the heating device 1, that is, non-condensable gas, when the heating device 1 When more non-condensable gas is accumulated, the overall temperature of the gas in the heating device 1 will be reduced, thereby affecting the heating efficiency of the heating device 1. For this reason, the non-condensable gas in the heating device 1 can be extracted by means of a vacuum pump 9, Thereby avoiding the accumulation of non-condensable gas. Specifically, the non-condensable gas may be extracted from the above-mentioned second air extraction port 92 .

In some embodiments, the non-condensable gas can be extracted at predetermined intervals, or the temperature of the feed liquid in the separation device 2 can be monitored. If the temperature of the feed 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 .

It can be understood that no matter when constructing a negative pressure environment or when extracting non-condensable gas, the extracted gas contains a large amount of steam, and the extracted steam may condense in the vacuum pump 9, thus affecting the working efficiency of the vacuum pump 9 and service life, for this reason, in some embodiments, the radioactive waste liquid treatment system can also include a cooling device 93, which is arranged on the passage between the vacuum pump 9 and the separation device 2, and the cooling device 93 is used for the gas pumped by the vacuum pump 9 A cooling process is performed to recover the vapor in the gas extracted by the vacuum pump 9 as condensate.

In some embodiments, it can be understood that when the power of the vacuum pump 9 is relatively large, part of the condensate in the cooling device 93 may also be sucked away. For this reason, referring to FIG. There is a buffer tank 94 which is used to store the condensate and prevent the condensate from being 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 communicates with the vacuum pump 9 and the cooling device 93, and the second buffer tank 942 is set Below the first buffer tank 941 , a first valve 943 is provided at the junction of the first buffer tank 941 and the second buffer tank 942 , and a second valve 944 is provided to communicate the second buffer tank 942 with the atmosphere.

Understandably, in the process of pumping air, if the buffer tank is completely sealed, the vacuum pump 9 may not be able to continuously extract gas due to air pressure problems, and if the buffer tank is connected to the atmosphere, it may cause the separation device 2, The gas channel 12 of the heating device 1 is directly connected to the atmosphere, which may cause the risk of radioactive leakage. Therefore, two buffer tank structures are provided in this embodiment.

Specifically, when the vacuum pump 9 is turned on and the height of the condensate in the first buffer tank 941 is lower than a preset value, the first valve 943 can be closed. And when the height of the condensate 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 moment, the second valve 944 can be closed and the first valve 943 can 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 all the condensate in the first buffer tank 941 enters the second buffer tank 942, the first valve 943 can be closed, and the second valve 944 can be opened to balance the pressure of the second buffer tank 942, so that when the next When more condensate has accumulated in the first buffer tank 941 , the second valve 944 can still be closed and the first valve 943 can be opened to release the pressure in the first buffer tank 941 .

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 pump gas, and ensuring that the separation device 2 and the gas channel 12 are not directly connected to the atmosphere.

In some embodiments, the second buffer tank 942 may communicate with the condensate recovery device 62 , and a third valve 945 is provided at the communication 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 remove the condensate in the second buffer tank 942. The liquid is introduced into the condensate recovery device 62.

In some embodiments, the vacuum pump 9 can be connected with a filter device 95, and the filter device 95 can be connected with an exhaust pipe 96, and the filter device 95 can be used to filter radioactive substances in the gas extracted by the vacuum pump 9, and the exhaust pipe 96 Can be used to vent filtered gas.

In some embodiments, the exhaust pipe 96 can be arranged in a segmented structure, and the segments can be disassembled from each other, or can be slid relative to each other, so that the exhaust pipe 96 can be removed without radioactive waste treatment. The sections of air tube 96 are disassembled or folded over each other to avoid their high height and restricted movement.

In some embodiments, referring to FIG. 9 and FIG. 10 , the radioactive waste liquid treatment system further includes a support platform 100 that can be placed horizontally, and the above-mentioned devices can be fixed on the support platform 100 . In this embodiment, the above-mentioned devices are fixed on the same horizontal plane, thereby reducing the height of the radioactive waste liquid treatment system in the vertical plane, making the overall structure of the radioactive waste liquid treatment system more compact, and convenient for installation in a relatively narrow space. Arrange in.

In some embodiments, the supporting platform 100 can be fixed on a movable platform, so that the entire radioactive waste liquid treatment system is movable, and its application scene does not have to be limited to a factory building. The movable platform can be a car and is equipped with a compartment, and the support platform 100 and the above-mentioned devices can be fixed in the compartment. As described above, each device in the radioactive waste liquid treatment system in this embodiment is fixed on the same horizontal plane, so that the whole radioactive waste liquid treatment system in this embodiment can meet the height limit requirements when the vehicle is running, thus, It can freely drive on the road to the required location for radioactive waste liquid treatment.

In some embodiments, the liquid channel 11 and the gas 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, so as to ensure that the liquid channel 11 and the gas channel 12 are long enough to meet the height requirements.

In some embodiments, the feeding device 5 , the heating device 1 , the separating device 2 and the vapor compression device 4 may be sequentially arranged 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 can be understood that, compared with the feeding device 5, the heating device 1, and the separation device 2, the radioactive content in the vapor compression device 4 and the steam generation device 6 is lower, therefore, the vapor compression device 4 and the steam generation device 6 Arranged side by side and 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 is convenient for ensuring the safety of operators.

In some embodiments, the radioactive waste liquid treatment system may include a partition, which may extend along the second direction, and the steam generating device 4 and the vapor compression device 6 are arranged on the side of the partition facing away from the separation device 2 . In this embodiment, the low-radiation devices such as the steam generating device 4 and the vapor compression device 6 are further separated from the high-radiation devices by means of a partition, so as to ensure safety. As described above, the support platform 100 and the above-mentioned devices can be arranged in the compartment, and the partition can be sealed and connected with the compartment, so that low-radiation devices such as the steam generating device 4 and the vapor compression device 6 are in contact with high-radiation devices. In two relatively sealed partitions.

In some embodiments, the condensate recovery device 62 may be arranged on the side of the vapor compression device 4 facing away from the separation device 2 , that is, it is also arranged in the subregion where the low-radioactive device is located.

In some embodiments, the circulation pump 3 and the purification device 8 can 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 can be arranged between the feeding device 5 and the purifying device 8 .

In some embodiments, some do not have control equipment and electrical equipment, such as electrical cabinets that provide power for the above-mentioned various devices, and controllers for controlling the startup and operation of the above-mentioned various devices, and monitoring the operating parameters of the above-mentioned devices. Can be arranged on the above-mentioned support platform 100, because these equipments are not radioactive, so they can be arranged on the side away from the separation device 2 of devices such as the steam generation device 4, the vapor compression device 6, and the condensate recovery device 62, and can also be It is isolated from the above-mentioned devices by means of partitions, so that the entire radioactive waste liquid treatment system is divided into three areas: high radiation area, low radiation area and no radiation area.

As described above, there are multiple pipelines between the above-mentioned multiple 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, these are used to transfer condensate The pipeline for liquid can be arranged along the surface of the support platform 100, and the pipeline for gas extraction and transfer can be arranged along the top surface of each of the above-mentioned devices.

In some embodiments, referring to FIG. 10 , the 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 with the support plate 110 . In this embodiment, each of the above-mentioned devices can be connected to the support frame 120. It is understandable that liquid leakage may occur during the operation of the above-mentioned devices, and since there is a gap formed between the support frame 120 and the support plate 110, Leakage can thus be collected in this gap, preventing it from flowing around.

In some embodiments, a side of the support plate 110 facing the support frame 120 is formed with an inclination angle. Therefore, the liquid leaked into the gap will flow to a corner of the support plate 110 along the inclination angle, so as to facilitate the collection of the leaked liquid.

Specifically, the inclination angle of the support plate 110 can be a very small angle, and at the same time, the support surface of the support frame 120 can be horizontal, so as to ensure the stability of supporting the above-mentioned various devices.

Embodiments of the present application also provide a radioactive waste liquid treatment method, which can be applied to the radioactive waste liquid treatment system described in one or more embodiments above.

Specifically, radioactive waste treatment methods include:

S1: The circulating pump is used to drive the radioactive waste liquid to circulate between the heating device and the separation device. The heating device is used to heat the radioactive waste liquid to evaporate the radioactive waste liquid in the separation device. The steam generated when the liquid evaporates is separated, so that the radioactive waste liquid is concentrated, and the separation device is in a negative pressure environment.

S2: In the process of circulation, use the steam compression device to compress and heat up the steam separated by the separation device to obtain compressed steam, and introduce the compressed steam into the heating device as the first heat source of the heating device, so that the radioactive waste liquid can be continuously concentrated;

S3: After it is determined that the radioactive waste liquid has been concentrated by a predetermined multiple, lead the radioactive waste liquid out of the heating device and the separation device.

In some embodiments, a negative pressure environment can be established in the separation device by means of a vacuum pump in communication with the separation device.

In some embodiments, before starting to process the radioactive waste liquid, the gas in the separation device can be extracted by means of a vacuum pump, so as to build a negative pressure environment in the separation device.

In some embodiments, the pressure in the separation device can also be monitored during the cycle, and if the pressure in the separation device is higher than the desired negative pressure, the vacuum pump is turned on to extract the gas in the separation device to maintain the negative pressure in the separation device environment.

In some embodiments, the non-condensable gas in the heating device can also be extracted by means of the above-mentioned vacuum pump.

In some embodiments, the outlet of the separation device is provided with a first air extraction port, and the heating device is provided with a second air extraction port, and the separation device can be extracted from one of the first air extraction port and the second air extraction port when creating a negative pressure environment. The gas; when extracting the non-condensable gas in the heating device, it can be extracted from the second extraction port.

In some embodiments, the temperature of the feed liquid in the separation device can be monitored, and if the temperature of the feed liquid in the separation device is lower than the evaporation temperature, the vacuum pump is turned on to extract the non-condensable gas in the heating device.

In some embodiments, during the process of constructing a negative pressure environment in the separation device and extracting non-condensable gas in the heating device by means of a vacuum pump, the gas extracted by the vacuum pump can be cooled by means of a cooling device, so as to extract the gas extracted by the vacuum pump. The vapor is recovered as condensate.

In some embodiments, the condensate recovered from the cooling unit may be introduced into the radioactive waste liquid.

For some specific technical details of the radioactive waste liquid treatment method described above, reference may be made to the description of relevant parts of the radioactive waste liquid treatment system above, and details will not be repeated here.

The present invention has been described in detail above in conjunction with the accompanying drawings and embodiments, but the present invention is not limited to the above-mentioned embodiments, and can also be made without departing from the gist of the present invention within the scope of knowledge possessed by those of ordinary skill in the art. kind of change. The content that is not described in detail in the present invention can adopt the prior art.

Claims (16)

1. A radioactive waste liquid treatment method comprises the following steps:

driving the radioactive waste liquid to circulate between a heating device and a separation device by means of a circulating pump, wherein the heating device is used for heating the radioactive waste liquid so as to evaporate the radioactive waste liquid in the separation device, the separation device is used for separating steam generated when the radioactive waste liquid is evaporated so as to concentrate the radioactive waste liquid, and a negative pressure environment is arranged in the separation device;

during the circulation, compressing and heating the steam separated by the separation device by means of a steam compression device to obtain compressed steam, introducing the compressed steam into the heating device as a first heat source of the heating device, and enabling the radioactive waste liquid to be continuously concentrated;

after determining that the radioactive waste has been concentrated by a predetermined factor, directing the radioactive waste to the heating device and the separation device.

2. The method of claim 1, further comprising:

establishing a negative pressure environment in the separation device by means of a vacuum pump in communication with the separation device.

3. The method of claim 2, wherein constructing a negative pressure environment comprises:

before the radioactive waste liquid is treated, gas in the separation device is pumped by a vacuum pump to establish a negative pressure environment in the separation device.

4. The method of claim 3, wherein constructing a negative pressure environment further comprises:

and monitoring the pressure in the separation device during the circulation process, and if the pressure in the separation device is higher than the expected negative pressure, starting the vacuum pump to pump gas in the separation device so as to maintain the negative pressure environment in the separation device.

5. The method of claim 4, further comprising:

and pumping out the non-condensable gas in the heating device by means of the vacuum pump.

6. The method according to claim 5, wherein the outlet of the separation device is provided with a first suction port and the heating device is provided with a second suction port, and the establishing of the negative pressure environment in the separation device by means of the vacuum pump comprises:

extracting gas in the separation device from one of the first pumping port and the second pumping port;

the extracting the non-condensable gasses in the heating device comprises:

and extracting the non-condensable gas in the heating device from the second air extraction port.

7. The method of claim 5 or 6, further comprising:

and monitoring the temperature of the material liquid in the separation device, and if the temperature of the material liquid in the separation device is lower than the evaporation temperature, starting the vacuum pump to extract the non-condensable gas in the heating device.

8. The method of claim 5, further comprising:

in the process of establishing a negative pressure environment in the separation device by means of the vacuum pump and extracting the non-condensable gas in the heating device, cooling the gas extracted by the vacuum pump by means of a cooling device so as to recover steam in the gas extracted by the vacuum pump as condensed liquid.

9. The method of claim 8, further comprising:

introducing the condensate recovered by the cooling device into the radioactive spent liquor.

10. A radioactive liquid waste treatment system comprising:

a heating device, wherein a liquid flow channel for flowing the radioactive waste liquid and a gas flow channel arranged outside the liquid flow channel are formed on the heating device, and 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 radioactive waste liquid after the heat treatment to concentrate the radioactive waste liquid;

a circulation line communicating the separation device with an inlet of the liquid flow channel;

a circulation pump provided in the circulation line for driving the radioactive liquid waste to circulate between the heating device and the separation device via the circulation line;

a vapor compression device arranged between the separation device and the inlet of the gas flow passage, wherein the vapor compression device is used for compressing and heating the vapor separated by the separation device to obtain compressed vapor, and the compressed vapor can be introduced into the gas flow passage to serve as a first heat source of the heating device;

a vacuum pump in communication with the separation device, the vacuum pump for drawing gas from the separation device to create a negative pressure environment in the separation device;

the feeding device is communicated with the heating device and is used for introducing the radioactive waste liquid into the liquid flow channel of the heating device;

and the discharge port is arranged in the circulating pipeline and used for leading out the concentrated radioactive waste liquid.

11. The system of claim 10, wherein the vacuum pump is further configured to extract non-condensable gasses in the heating device.

12. The system of claim 11, wherein a first pumping port is provided at an outlet of the separation device, a second pumping port is provided in the gas flow passage of the heating device, and the vacuum pump is in communication with the separation device via the first pumping port and the second pumping port.

13. The system of claim 11, 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 extracted by the vacuum pump so as to recover steam in the gas extracted by the vacuum pump into condensate.

14. The system of claim 11, further comprising:

and the filtering device is communicated with an outlet of the vacuum pump and is used for filtering radioactive substances in the gas extracted by the vacuum pump.

15. The system of claim 14, further comprising:

and the exhaust pipe is detachably arranged at the outlet of the filtering device and is used for exhausting the gas in the filtering device.

16. The system of claim 15, wherein the exhaust pipe is provided in a segmented configuration.

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