CN219891899U - A radioactive waste liquid partitioned heat pump evaporation system - Google Patents

Abstract

The utility model provides a radioactive waste liquid partition type heat pump evaporation system, which is applied to the technical field of radioactive waste liquid treatment and includes a waste liquid evaporation subsystem and a heat exchange subsystem. The waste liquid evaporation subsystem is used to heat and evaporate the radioactive waste liquid. And separate the secondary steam; the heat exchange subsystem includes a heat exchange device using the secondary steam as a heat source, a vapor-liquid separation device and a vapor compression device. The heat exchange device can store clean evaporation working fluid; the evaporation working fluid is heated and evaporated to produce The steam is compressed and raised in temperature and pressure by the vapor compression device and then input into the waste liquid evaporation subsystem and used as the heat source of the waste liquid evaporation subsystem; the secondary steam evaporated by the waste liquid is heated and evaporated and performs wall heat exchange with the evaporation working medium, solving the problem When the radioactive waste liquid containing low-boiling point substances evaporates in the heat pump, the direct compression of the secondary vapor will cause compressor pollution problems and the risks of leakage, explosion, corrosion and other risks in the compression process.

Description

A radioactive waste liquid partitioned heat pump evaporation system

Technical field

The utility model relates to the technical field of radioactive waste liquid treatment, and in particular to a radioactive waste liquid partition type heat pump evaporation system.

Background technique

A large amount of radioactive waste liquid is inevitably produced during the production of nuclear fuel and the promotion and application of nuclear technology. Due to its wide range of sources, complex composition, and certain radioactivity, it brings certain difficulties to post-processing. Among them, low-level and intermediate-level waste liquids are bulky and contain a high total amount of radioactivity, which is the focus and difficulty of waste treatment.

In order to solve the above problems, the evaporation concentration method is effective and widely used in the prior art. Among them, single-effect evaporation is currently the main process method for the evaporation and concentration of radioactive waste liquids. This method requires a large amount of externally generated steam during system operation, and the heat energy utilization rate is low, resulting in high operating energy consumption and waste liquid treatment costs. In order to solve the problem of single-effect evaporation, researchers designed a mechanical vapor recompression (MVR) heat pump evaporation process. Mechanical vapor recompression (MVR) heat pump evaporation can realize the complete recovery and reuse of the latent heat of secondary steam in the waste liquid evaporation process. It can effectively reduce system energy consumption and is currently a prominent and effective energy-saving method.

However, in the mechanical vapor recompression (MVR) heat pump evaporation treatment process, the secondary steam is directly compressed. Although this process has a high energy-saving effect, when the waste liquid contains low-boiling substances, the low-boiling substances in the evaporation process It will enter the compressor with the secondary steam, causing the compressor to be contaminated by radioactive substances, causing the radioactivity level of the compressor itself to increase, which will bring inconvenience to later maintenance. At the same time, direct compression of low-boiling substances also has hidden dangers such as leakage, explosion, and corrosion. .

Utility model content

The utility model provides a wall-type heat pump evaporation system for radioactive waste liquid, which is used to solve the problem that when the existing MVR heat pump evaporation technology handles radioactive waste liquid containing low-boiling point substances, radioactive substances are easy to contaminate the vapor compression equipment and are prone to leakage and explosion. , corrosion defects to achieve efficient, safe and reliable operation of the system.

The utility model provides a wall-type heat pump evaporation system for radioactive waste liquid, which includes a waste liquid evaporation subsystem and a heat exchange subsystem. The waste liquid evaporation subsystem is connected to the radioactive waste liquid and is used to heat, evaporate, and concentrate the radioactive waste liquid. Separate the secondary steam generated by evaporation; the heat exchange subsystem includes a heat exchange device using the secondary steam as a heat source, a vapor-liquid separation device and a vapor compression device. The vapor-liquid separation device is respectively connected with the heat The exchange device and the vapor compression device are connected, and the heat exchange device can store clean evaporation working fluid; wherein the vapor compression device is connected with the waste liquid evaporation subsystem, so that the evaporation working fluid is heated The steam generated after evaporation is compressed by the vapor compression device to raise the temperature and pressure, and then is input into the waste liquid evaporation subsystem and serves as a heat source for the waste liquid evaporation subsystem.

According to the utility model, a wall-type heat pump evaporation system for radioactive waste liquid also includes a raw material storage tank and a feed preheating subsystem. The feed preheating subsystem is connected to the raw material storage tank and the waste liquid respectively. The evaporation subsystem and the heat exchange subsystem are connected to preheat the radioactive waste liquid and input the preheated radioactive waste liquid into the waste liquid evaporation subsystem.

According to a radioactive waste liquid partition type heat pump evaporation system provided by the utility model, the heat exchange device is connected with a second condensed water storage tank, and the second condensed water storage tank is preheated with the feed material through a condensation pump. Subsystems are connected.

According to a radioactive waste liquid dividing wall heat pump evaporation system provided by the utility model, the waste liquid evaporation subsystem includes an evaporator, a first vapor-liquid separator, a second vapor-liquid separator and a first condensed water storage tank. The evaporator is connected to the first vapor-liquid separator, the first condensed water storage tank, and the vapor compression device respectively, and the second vapor-liquid separator is connected to the first vapor-liquid separator, The heat exchange devices are connected.

According to a wall-type heat pump evaporation system for radioactive waste liquid provided by the utility model, the feed preheating subsystem includes a first-level preheater, a second-level preheater, and a third-level preheater that are connected in sequence; the three-level preheater The first-stage preheater is connected to the first vapor-liquid separator, the first condensed water storage tank, and the vapor-liquid separation device respectively, and the second-stage preheater is connected to the second condensed water storage tank. .

According to a radioactive waste liquid partitioned heat pump evaporation system provided by the utility model, the first-level preheater is equipped with a non-condensable gas output pipeline, and the non-condensable gas output pipeline is connected to the evaporator and the The first condensate storage tank is connected.

According to a wall-type heat pump evaporation system for radioactive waste liquid provided by the utility model, the secondary preheater is equipped with a condensate recovery output pipeline for evaporation condensate recovery.

According to a wall-type heat pump evaporation system for radioactive waste liquid provided by the utility model, the vapor-liquid separation device is configured with at least a vapor-liquid two-phase medium inlet, a vapor-phase medium outlet, and a liquid-phase medium for the cyclic flow of the evaporation working medium. Inlet, liquid medium outlet; wherein, the liquid medium inlet is connected to the three-stage preheater, and the liquid medium outlet is connected to the heat exchange device through the second lower circulation pipeline, so that The evaporation working fluid can be circulated into the heat exchange device.

According to a radioactive waste liquid dividing wall heat pump evaporation system provided by the utility model, the first vapor-liquid separator is equipped with at least a waste liquid input port, a waste liquid outlet, a vapor-liquid two-phase inlet, a secondary steam outlet, a liquid Phase reflux port; wherein, the waste liquid outlet and the evaporator are connected through the first lower circulation pipeline, so that the radioactive waste liquid can be cyclically evaporated to achieve concentration.

According to a wall-type heat pump evaporation system for radioactive waste liquid provided by the utility model, a concentrated liquid discharge pipeline for discharging concentrated liquid is arranged on the first lower circulation pipeline.

The beneficial effect of the wall-type heat pump evaporation system for radioactive waste liquid provided by the utility model is that by connecting a heat exchange subsystem at the back end of the secondary steam, the secondary steam produced by evaporating the radioactive waste liquid is evaporated through the heat exchange subsystem. The secondary steam and the clean evaporation working fluid perform partition-type heat exchange, which solves the pollution problems of the compression device caused by the direct compression of the secondary steam when the radioactive waste liquid containing low boiling point substances is evaporated by the heat pump, as well as the leakage, explosion, and corrosion during the compression process. and other risks. At the same time, due to the complete recovery of the latent heat of the secondary steam, the energy utilization rate of the evaporation process is improved and the operating energy consumption is reduced.

Description of the drawings

In order to explain the technical solutions of the present invention or the prior art more clearly, the drawings needed to be used in the description of the embodiments or the prior art will be briefly introduced below. Obviously, the drawings in the following description are: For some embodiments of the present invention, those of ordinary skill in the art can also obtain other drawings based on these drawings without exerting creative efforts.

Figure 1 is a schematic structural diagram of the radioactive waste liquid partition type heat pump evaporation system provided by the utility model;

Figure 2 is a specific structural diagram of a vapor-liquid separation device provided by an embodiment of the present invention;

Figure 3 is a specific structural diagram of a first vapor-liquid separator provided by an embodiment of the present invention.

Reference signs:

100: Raw material storage tank; 200: Feed preheating subsystem; 201: Raw material pump; 202: First-level preheater; 203: Second-level preheater; 204: Third-level preheater; 300: Waste liquid evaporator System; 301: condensate return pump; 302: first condensate storage tank; 303: evaporator; 304: first lower circulation pipeline; 305: first vapor-liquid separator; 305-1: waste liquid input port; 305-2: Vapor-liquid two-phase inlet; 305-3: Waste liquid outlet; 305-4: Liquid phase reflux port; 305-5: Secondary steam outlet; 306: Second vapor-liquid separator; 307: First upper Circulation pipeline; 400: heat exchange subsystem; 401: condensation pump; 402: second condensate storage tank; 403: second lower circulation pipeline; 404: heat exchange device; 405: vapor-liquid separation device; 405-1 : Vapor-liquid two-phase medium inlet; 405-2: Vapor-phase medium outlet; 405-3: Liquid-phase medium inlet; 405-4: Liquid-phase medium outlet; 406: Vapor compression device; 407: Second upper circulation pipeline; 500: Condensate recovery output pipeline; 600: Non-condensable gas output pipeline; 700: Concentrate discharge pipeline; 800: Concentrate pump.

Detailed ways

In order to make the purpose, technical solutions and advantages of the present utility model clearer, the technical solutions in the present utility model will be clearly and completely described below in conjunction with the drawings of the present utility model. Obviously, the described embodiments are the embodiments of the present utility model. Some, not all, of the new embodiments. Based on the embodiments of the present utility model, all other embodiments obtained by those of ordinary skill in the art without making creative efforts fall within the scope of protection of the present utility model.

In the description of this application, "connected" can be understood as being able to transmit gas or liquid between two devices through one or more pipelines. The transmission process of liquid or gas can be realized by driving device or by pressurizing or depressurizing. Among them, vapor is a form formed by liquid being heated.

The following is a description of a radioactive waste liquid partition type heat pump evaporation system of the present invention in conjunction with Figure 1, which includes a raw material storage tank 100. The raw material storage tank 100 is configured as a barrel-shaped structure, and radioactive waste liquid to be processed is stored in the raw material storage tank 100. , a raw material outlet is configured at the bottom of the storage tank, and the raw material outlet is connected to a pipeline with a valve.

The feed preheating subsystem 200 is connected to the raw material outlet. When connected, a raw material pump 201 is provided. The radioactive raw materials are input into the feed preheating subsystem 200 through the raw material pump 201 for preheating.

The waste liquid evaporation subsystem 300 is used to heat, evaporate and concentrate the radioactive waste liquid and separate the secondary steam generated by evaporation into vapor and liquid. For example, the radioactive waste liquid can be heated by a heating device so that the radioactive waste liquid boils to generate steam, and then the steam is secondary separated and purified through two vapor-liquid separation mechanisms to obtain purer secondary steam. Pipes or components that can provide a heat source for the feed preheating subsystem 200 may be configured in the waste liquid evaporation subsystem 300, and the details may be explained in the following embodiments. Of course, in order to improve the treatment efficiency of radioactive waste liquid, the connected radioactive waste liquid can be preheated in advance.

Heat exchange subsystem 400; the heat exchange subsystem 400 includes a heat exchange device 404 using secondary steam as a heat source, a vapor-liquid separation device 405, and a vapor compression device 406. The vapor-liquid separation device 405 is respectively connected with the heat exchange device 404 and the vapor compression device. 406 is connected, and the heat exchange device 404 can store clean evaporation working fluid, for example, clean water is used as the evaporation working fluid, which is easy to obtain materials and has low cost. The heat exchange device 404 may be a shell and tube heat exchanger or a plate heat exchanger, preferably a shell and tube heat exchanger. The heat exchange subsystem 400 may be configured with pipelines or components that can further provide preheating for the feed preheating subsystem 200 , as will be explained in detail in the following embodiments.

The feed preheating subsystem 200 is connected to the raw material storage tank 100, the waste liquid evaporation subsystem 300, and the heat exchange subsystem 400, respectively, for preheating the radioactive waste liquid and inputting the preheated radioactive waste liquid to the waste liquid evaporation. In the subsystem 300, the vapor compression device 406 is connected to the waste liquid evaporation subsystem 300, so that the vapor of the boiling and vaporized evaporation working medium is raised in temperature and pressure through the vapor compression device 406 and then input into the waste liquid evaporation subsystem 300 and used as the required vapor. The heat source of the waste liquid evaporation subsystem 300.

It can be understood that in the above embodiments, the key point is to provide the heat exchange subsystem 400, through which the heat exchange subsystem 400 exchanges thermal energy with the secondary steam, for example, partition-type heat exchange, so that the evaporation working medium is heated and evaporated and evaporated. The vapor compression device 406 performs compression and temperature rise, and finally enters the waste liquid evaporation subsystem, achieving a clean and safe working environment for the compressor and avoiding safety hazards such as contamination and leakage of radioactive materials.

In one embodiment, the heat exchange device 404 is connected to a second condensate storage tank 402, and the second condensate storage tank 402 is connected to the feed preheating subsystem 200 through a condensation pump 401, thereby realizing heat exchange. Subsystem 400 provides a heat source for feed preheating subsystem 200 . A more specific embodiment is that the feed preheating subsystem 200 includes a first-level preheater 202, a second-level preheater 203, and a third-level preheater 204 connected in sequence; the second-level preheater 203 and the second condensed water The storage tank 402 is connected, so that the condensed water of the heat exchange device 404 is used as the heat source of the secondary preheater 203 to realize the secondary preheating of the radioactive waste liquid, and the secondary preheater is equipped with a condensate for recovery of the evaporated condensate. Liquid recovery output line 500. Specifically, the first-level preheater 202 is a non-condensing steam preheater, the second-level preheater 203 is an evaporative condensate preheater, and the third-level preheater 204 is a clean water preheater. In a further embodiment, the waste liquid evaporation subsystem 300 includes an evaporator 303, a first vapor-liquid separator 305, a second vapor-liquid separator 306, and a first condensed water storage tank 302, wherein the evaporator 303 may be a shell-and-tube type. Heat exchanger or plate heat exchanger, preferably shell and tube heat exchanger. The evaporator 303 is connected to the first vapor-liquid separator 305, the first condensed water storage tank 302, and the vapor compression device 406 respectively, and the second vapor-liquid separator 306 is connected to the first vapor-liquid separator 305 and the heat exchange device 404 respectively. The three-stage preheater 204 is connected to the first vapor-liquid separator 305, the first condensed water storage tank 302, and the vapor-liquid separation device 405 respectively. The first condensed water storage tank 302 is connected to the shell side of the evaporator 303. Connected, so that the condensed water of the evaporator 303 serves as the heat source of the three-stage preheater 204 to realize the preheating of the three-stage preheater 204. In a further embodiment, the first-stage preheater 202 is configured with a non-condensable gas output pipeline 600, which is connected to the evaporator 303 and the first condensed water storage tank 302 respectively, that is, The non-condensable steam in the evaporator 303 and the non-condensable gas in the first condensed water storage tank 302 are collectively input into the primary preheater 202, so that the non-condensable steam can be used as a heat source to perform primary preheating of the radioactive waste liquid. .

In the above embodiment, the evaporator 303 and the first condensate storage tank 302 in the waste liquid evaporation subsystem are connected to the third-stage preheater 204 and the first-stage preheater 202 through designed pipelines. The third-stage preheater 204 The pipeline connected to the first condensate storage tank 302 uses the condensate return pump 301 to input the condensate as the heat source of the third-stage preheater 204. The pipeline connected to the first-stage preheater 202 uses the input of non-condensable steam as the heat source. Heat source; the heat exchange device 404 in the heat exchange subsystem 400 and the second condensation storage tank are connected through the designed pipeline, and the connecting pipeline of the secondary preheater 203 inputs the condensate in the heat exchange device 404 through the condensation pump 401 as a heat source. It can be understood that the condensate flowing through the condensate return pump 301 in the system is the condensed evaporation working fluid; the heat source of each stage of the preheater is to utilize the subsequent waste liquid evaporation subsystem 300 and the heat exchange subsystem 400 The heat energy in the whole system can be fully utilized to achieve high efficiency and energy saving.

As shown in Figure 2, in a specific embodiment, the vapor-liquid separation device 405 is configured with at least a vapor-liquid two-phase medium inlet 405-1, a vapor-phase medium outlet 405-2, and a liquid medium for circulating flow of the evaporation working medium. Phase medium inlet 405-3, liquid phase medium outlet 405-4; among them, vapor-liquid two-phase medium inlet 405-1 and vapor phase medium outlet 405-2 are used for the circulation of clean evaporation working medium for vaporization, that is, clean water vapor Circulation, specifically, the vaporized evaporation working fluid enters the vapor-liquid separation device 405 from the heat exchange device 404 through the vapor-liquid two-phase medium inlet 405-1, and the liquid phase is separated by the vapor-liquid separation device 405. The vaporized evaporation working fluid It enters the vapor compression device 406 from the vapor-liquid separation device 405; the liquid medium inlet 405-3 is connected to the three-stage preheater 204, and the liquid medium outlet 405-4 is connected to the heat exchange device through the second lower circulation pipeline 403. 404 is connected to enable the evaporation working fluid to circulate into the heat exchange device 404 . As shown in Figure 3, in a further embodiment, the first vapor-liquid separator 305 is equipped with at least a waste liquid input port 305-1, a waste liquid outlet 305-3, a vapor-liquid two-phase inlet 305-2, and a secondary steam The outlet 305-5 and the liquid phase reflux port 305-4; the waste liquid outlet 305-3 is connected to the evaporator 303 through the first lower circulation pipeline 304 so that the waste liquid circulates and evaporates to achieve concentration; the waste liquid input port 305-1 is connected into the three-stage preheater 204, so that the preheated radioactive waste liquid enters the first vapor-liquid separator 305. In another specific embodiment, a concentrated liquid discharge pipe 700 for discharging concentrated liquid is disposed on the first circulation pipe, and a concentrated liquid pump 800 is provided on the concentrated liquid discharge pipe 700, so that when concentrated to a predetermined concentration The concentrated liquid can then be discharged through the concentrated liquid discharge pipe 700.

In combination with the above embodiment, the vapor compression device 406 is connected to the evaporator 303, and uses the compressed and heated vaporized evaporation working fluid as the heat source of the evaporator 303, and the condensed evaporation working fluid passes through the connected first condensed water storage tank. 302 enters the three-stage preheater 204 and further serves as the heat source of the three-stage preheater 204. After preheating the waste liquid, the evaporated working fluid is evaporated through the connecting pipeline between the liquid medium inlet 405-3 and the three-stage preheater 204. It is input into the vapor-liquid separation device 405, thereby realizing the circulation of the evaporated working fluid in the system.

In the embodiment of the present application, the first vapor-liquid separator 305 and the vapor-liquid separation device 405 are both used to separate the vapor-liquid mixture obtained during the evaporation process. Gravity separation can be used. Specifically, the vapor-liquid separation device can be used in the separator. The phase part is equipped with a swirl plate or mesh filler to remove entrained droplets and improve the purification effect. The second vapor-liquid separator 306 is used to further separate the vapor and liquid of the secondary steam obtained during the evaporation process to further improve the purification effect. Purification methods such as packing filtration and spray washing can be used. The raw material pump 201, the condensate return pump 301, the concentrate pump 800 and the condensate pump 401 are used for fluid transmission in the system; preferably, the feed pump, condensate pump, condensate pump, concentrate pump, etc. use variable frequency pumps, or alternatively Power frequency pump.

The specific work flow of the radioactive waste liquid partitioned heat pump evaporation system of the present invention is described below. The work flow described below and the radioactive waste liquid divided wall heat pump evaporation system described above can be mutually referenced.

Referring to Figure 1, the radioactive waste liquid is discharged from the raw material outlet of the raw material storage tank 100, and is driven into the cold flow inlet of the primary preheater 202 through the raw material pump 201 for preliminary preheating; then, the material enters the secondary preheater 203 After continuing to preheat, it is discharged from the cold outflow outlet on the second-level preheater 203; further, the material enters the third-level preheater 204 and continues to be preheated. After completing the preheating, it is discharged through the cold outflow outlet on the third-level preheater 204. discharge. The preheated radioactive waste liquid enters the first vapor-liquid separator 305 through the material inlet of the first vapor-liquid separator 305, and then the radioactive waste liquid enters from the lower part of the evaporator 303 along with the fluid in the first lower circulation pipe 304. On the tube side of the evaporator 303, the radioactive waste liquid in the tube side boils and evaporates into a vapor-liquid mixture after exchanging heat with the steam of the evaporation working medium on the shell side, and then enters the first vapor-liquid separator 305 through the first upper circulation pipe 307. Vapor-liquid separation is performed in The lower circulation pipeline 304 continues to participate in circulation and evaporation. After the secondary steam further removes entrained droplets in the second vapor-liquid separator 306, the secondary steam in the vapor phase enters the shell side of the heat exchange device 404 as a heat source to heat the clean water in the tube side, and the secondary steam in the liquid phase refluxes to the first vapor-liquid separator 305. The secondary steam exchanges heat with the clean water in the heat exchange device 404 and becomes condensate, which enters the second condensate storage tank 402; further, the high-temperature condensate in the second condensate storage tank 402 is pumped into the secondary stage by the condensation pump 401. The heat flow inlet of the preheater 203 is used as a heat source to preheat the feed and then discharge it into the system for subsequent processing; the clear water in the tube side of the heat exchange device 404 boils and evaporates after being heated, and the generated vapor-liquid mixture enters the vapor-liquid separation through the second upper circulation pipe 407 In device 405, the separated secondary clean water vapor is discharged from the top and then enters the vapor compression device 406. The remaining clean water liquid enters the second lower circulation pipe 403 to continue to participate in cyclic evaporation. The steam is compressed by the vapor compression device 406 to increase the temperature and pressure, and then enters the shell side of the evaporator 303 as a heat source to heat the waste liquid in the tube side. After heat exchange, the high-temperature steam becomes condensed water and enters the first condensed water storage tank 302. The high-temperature The condensate water is pumped into the heat flow inlet of the three-stage preheater 204 by the condensate water reflux pump. It is used as a heat source to preheat the radioactive waste liquid and is then discharged from the outlet and returned to the vapor-liquid separation device 405. The first lower circulation line 304 is provided with a concentrated liquid discharge port. When the waste liquid in the system is concentrated to a set concentration, the concentrated liquid pump 800 will pump the concentrated liquid out of the system for subsequent processing. Considering that there may be a small amount of non-condensable gas inside the system during operation, non-condensable gas outlets are provided on the shell side of the evaporator 303 and the top of the first condensate storage tank 302, and are connected through pipelines and then connected to the first-level preheater. 202's heat flow inlet, preheating the feed and then the discharge system is connected to the non-condensable steam treatment device.

Through the above description of the embodiments, those skilled in the art can clearly understand that each embodiment can fully utilize the thermal energy of the system, and the entire system has a reasonable design, a simple structure, and a high thermal energy utilization rate.

Finally, it should be noted that the above embodiments are only used to illustrate the technical solution of the present invention, but not to limit it; although the present utility model has been described in detail with reference to the foregoing embodiments, those of ordinary skill in the art should understand that: The technical solutions described in the foregoing embodiments can still be modified, or some of the technical features can be equivalently replaced; and these modifications or substitutions do not deviate from the essence of the corresponding technical solutions from the spirit of the technical solutions of the various embodiments of the present invention. and scope.

Claims (10)

1. A radioactive waste liquid dividing wall type heat pump evaporation system, comprising:

the waste liquid evaporation subsystem is used for heating, evaporating and concentrating the radioactive waste liquid and performing vapor-liquid separation on secondary steam generated by evaporation;

the heat exchange subsystem comprises a heat exchange device taking the secondary steam as a heat source, a vapor-liquid separation device and a vapor compression device, wherein the vapor-liquid separation device is respectively communicated with the heat exchange device and the vapor compression device, and the heat exchange device can store clean evaporating working media;

the vapor compression device is communicated with the waste liquid evaporation subsystem, so that vapor generated after the evaporation working medium is heated and evaporated is compressed by the vapor compression device to raise the temperature and the pressure, and then is input into the waste liquid evaporation subsystem and used as a heat source of the waste liquid evaporation subsystem.

2. The radioactive waste dividing wall heat pump evaporation system according to claim 1, further comprising:

a raw material storage tank;

and the feeding preheating subsystem is respectively connected with the raw material storage tank, the waste liquid evaporation subsystem and the heat exchange subsystem and is used for preheating radioactive waste liquid and inputting the preheated radioactive waste liquid into the waste liquid evaporation subsystem.

3. The radioactive waste dividing wall heat pump evaporation system according to claim 2, wherein a second condensate storage tank is communicated with the heat exchange device, and the second condensate storage tank is communicated with the feed preheating subsystem through a condensate pump.

4. The radioactive waste dividing wall heat pump evaporation system according to claim 3, wherein said waste evaporation subsystem comprises an evaporator, a first vapor-liquid separator, a second vapor-liquid separator and a first condensate storage tank, said evaporator is respectively communicated with said first vapor-liquid separator, said first condensate storage tank and said vapor compression device, and said second vapor-liquid separator is respectively communicated with said first vapor-liquid separator and said heat exchange device.

5. The radioactive waste dividing wall heat pump evaporation system according to claim 4, wherein said feed preheating subsystem comprises a primary preheater, a secondary preheater, a tertiary preheater, which are sequentially connected; the third-stage preheater is respectively communicated with the first vapor-liquid separator, the first condensate water storage tank and the vapor-liquid separation device, and the second-stage preheater is communicated with the second condensate water storage tank.

6. The radioactive waste dividing wall heat pump evaporation system according to claim 5, wherein said primary preheater is provided with a non-condensable gas output pipe, said non-condensable gas output pipe being respectively communicated with said evaporator and said first condensate storage tank.

7. The radioactive waste dividing wall type heat pump evaporation system according to claim 5 or 6, wherein a condensate recovery output pipeline for evaporating condensate recovery is arranged on the secondary preheater.

8. The radioactive waste liquid dividing wall type heat pump evaporation system according to claim 5, wherein said vapor-liquid separation device is provided with at least a vapor-liquid two-phase medium inlet, a vapor-phase medium outlet, a liquid-phase medium inlet, a liquid-phase medium outlet for circulating said evaporation medium; the liquid medium inlet is communicated with the three-stage preheater, and the liquid medium outlet is communicated with the heat exchange device through a second lower circulation pipeline, so that the evaporating material can be circulated into the heat exchange device.

9. The radioactive waste liquid dividing wall type heat pump evaporation system according to claim 4 or 5, wherein the first vapor-liquid separator is provided with at least a waste liquid input port, a waste liquid output port, a vapor-liquid two-phase input port, a secondary vapor output port and a liquid phase return port; the waste liquid outlet is communicated with the evaporator through a first lower circulation pipeline, so that the radioactive waste liquid is concentrated by circulation evaporation.

10. The radioactive waste dividing wall heat pump evaporation system according to claim 9, wherein said first lower circulation line is provided with a concentrate discharge line for discharging the concentrate.