Nuclide separation system and nuclide separation method

Abstract

The embodiment of the invention provides a nuclide separation system and a nuclide separation method. The separation system comprises a gas supply device, a plunger pump, a first piston container, a temperature control device and a data acquisition and control system. The first piston container comprises a first cavity and a first piston located in the first cavity. The first piston divides the first cavity into a first top space and a first bottom space, and the first top space is connected with the gas supply device and used for containing carbon dioxide transmitted by the gas supply device. The temperature control device is used for containing the first piston container and changing the first temperature of the first piston container to the second temperature. The data acquisition and control system is used for calculating the real-time concentration of nuclides according to the initial nuclide concentration of the head space at the first temperature, the gas molar density of the first head space at the second temperature and the molar weight of residual water of the first head space at the second temperature. Based on the salt elimination effect of hydrates, the nuclide separation effect is achieved through multiple times of concentration.

Description

Technical Field

[0001] The present application relates to the technical field of nuclide separation, and in particular to a nuclide separation system and a nuclide separation method. Background Art

[0002] The main sources of radionuclides in nuclear wastewater are generated by the operation of fusion and fission reactors and their associated cooling systems. Current treatment methods typically employ chemical precipitation, ion exchange, adsorption, evaporation and concentration, magnetic-molecular methods, biological treatment, membrane separation, inert chemical methods, and zero-valent iron percolation reaction wall technology to treat radionuclides. However, current radionuclide separation and treatment methods still present many challenges. For example, due to the wide variety of radionuclides, these methods can generally only treat a limited number of them, failing to effectively treat others simultaneously. This requires the combined use of multiple methods, which incurs significant costs. Furthermore, if the concentration of radionuclides in nuclear wastewater is low, for example, only tens to hundreds of becquerels per liter, conventional methods struggle to treat such low concentrations. Summary of the Invention

[0003] In order to solve at least one of the above technical problems, the present invention provides a separation system for removing nuclides from seawater. In addition, the present invention also provides a nuclide separation method using the nuclide separation system.

[0004] In a first aspect, the present application provides a nuclide separation system for separating nuclides in water. The separation system includes an air supply device, a plunger pump, a first piston container, a temperature control device, and a data acquisition and control system. The air supply device is used to provide carbon dioxide. The plunger pump is used to pressurize the carbon dioxide to a first pressure. The first piston container includes a first cavity and a first piston movably disposed in the first cavity. The first piston divides the first cavity into a first top space and a first bottom space. The first top space is connected to the air supply device and is used to accommodate pressurized carbon dioxide. The first top device is also used to accommodate water. The temperature control device is used to change the temperature of the first piston container from a first temperature to a second temperature so that carbon dioxide and water react in the first top space to form hydrates. The data acquisition and control system is used to calculate the real-time concentration of the nuclides based on the initial nuclide concentration in the top space at the first temperature, the molar density of carbon dioxide gas in the first top space, and the molar amount of residual water.

[0005] In some embodiments of the present application, a second piston container is further included, which includes a second cavity and a second piston movably arranged in the second cavity. The second piston divides the second cavity into a second top space and a second bottom space. The second top space is connected to the first top space and is used to accommodate water and carbon dioxide transmitted from the first top space. The data acquisition and control system is also used to calculate the real-time concentration of the nuclide based on the molar density of carbon dioxide gas in the second top space and the molar amount of residual water.

[0006] In some embodiments of the present application, the separation system further includes a first temperature sensor, a first pressure sensor, a second temperature sensor, and a second pressure sensor. The first temperature sensor and the first pressure sensor are respectively configured to measure the temperature and pressure within the first piston container. The second temperature sensor and the second pressure sensor are respectively configured to measure the temperature and pressure within the second piston container. The data acquisition and control system is further configured to calculate the molar density of the gas and the molar amount of residual water in the first headspace and the second headspace based on the acquired temperature and pressure, thereby obtaining the concentration of the nuclide in the first headspace and the second headspace.

[0007] In some embodiments of the present application, the first piston container and the second piston container both include a container body and a piston adjustment mechanism, the piston adjustment mechanism is arranged in the container body, the piston adjustment mechanism includes a piston body and an adjustment member, the piston body is movably arranged in the container body, the adjustment member is arranged in the container body and is used to adjust the relative position of the piston body in the container body to transfer the liquid in the first top space to the second top space.

[0008] In some embodiments of the present application, the piston body is further provided with a liquid extraction port.

[0009] In some embodiments of the present application, the second piston container is further connected to a liquid storage tank, which is used to collect waste liquid in the second piston container.

[0010] In some embodiments of the present application, a buffer device is further connected between the gas supply device and the first piston container, and the buffer device is used to buffer the carbon dioxide transmitted from the gas supply device.

[0011] In some embodiments of the present application, the separation system further includes a delivery pipeline, which includes a first delivery pipeline, a second delivery pipeline, and a third delivery pipeline. The first delivery pipeline includes a first branch, a second branch, and a third branch. The first branch connects the air supply device and the buffer device, the second branch connects the plunger pump and the first branch, and the third branch connects the buffer device and the first headspace. The second delivery pipeline includes a fourth branch and a fifth branch. The fourth branch connects the first headspace and the second headspace, and the fifth branch connects the fourth branch and the outside world. The third delivery pipeline connects the second headspace and the liquid storage tank.

[0012] In some embodiments of the present application, the separation system further includes a camera device and a visualization window, the visualization window being disposed on the first piston container and the second piston container, and the camera device being used to capture images of hydrates generated in the first piston container and the second piston container respectively through the visualization window.

[0013] A second aspect of the present application provides a nuclide separation method for separating nuclides in water. The separation method is implemented using the aforementioned nuclide separation system, and the measurement method includes turning on a gas supply device to output carbon dioxide. A first pressure is applied to the output carbon dioxide by a plunger pump, so that the pressurized carbon dioxide is injected into a first headspace. The first piston container is changed from a first temperature to a second temperature by a temperature control device, so that carbon dioxide and water react in the first headspace to form hydrates. The real-time concentration of the nuclides is calculated based on the initial nuclide concentration in the headspace at the first temperature, the gas molar density in the first headspace at the second temperature, and the molar amount of residual water in the first headspace at the second temperature.

[0014] Compared to existing technologies, the radionuclide separation system provided in the embodiments of this application leverages the salt-removal effect of hydrates and the principle of ion separation at the molecular level. Through multiple concentration steps, radionuclide enrichment is achieved, collecting wastewater containing radionuclides for subsequent treatment. Hydrate decomposition produces clean water, effectively removing the radionuclides. This system offers significant advantages, including safety, high concentration ratios, high efficiency, sustainable production, and low cost. BRIEF DESCRIPTION OF THE DRAWINGS

[0015] Figure 1 Schematic diagram of a nuclide separation system according to one embodiment of the present application.

[0016] Figure 2 yes Figure 1 A schematic three-dimensional diagram of the first piston container or the second piston container is shown.

[0017] Description of main component symbols: Separation system 10, gas supply device 100, plunger pump 200, first piston container 300, second piston container 400, temperature control device 500, data acquisition and control system 600, first cavity 301, first piston 302, first top space 303, first bottom space 304, second cavity 401, second piston 402, second top space 403, second bottom space 404, first temperature sensor 700, first pressure sensor 800, second temperature sensor 800, first pressure sensor 900, second pressure sensor 100, first ... Sensor 701, second pressure sensor 801, container body 310, piston adjustment mechanism 320, adjustment member 330, liquid intake port 900, liquid storage tank 910, stirring device 311, stirring paddle 3110, motor 3111, first delivery pipe 11, second delivery pipe 12, third delivery pipe 13, first branch 111, second branch 112, third branch 113, fourth branch 121, fifth branch 122, camera device 601, visualization window 340. DETAILED DESCRIPTION

[0018] The following will clearly and completely describe the technical solutions in the embodiments of the present application in combination with the drawings in the embodiments of the present application. Obviously, the described embodiments are only part of the embodiments of the present application, not all of the embodiments.

[0019] It should be noted that when an element is considered to be “connected” to another element, it may be directly connected to the other element or there may be a centrally disposed element. When an element is considered to be “disposed on” another element, it may be directly disposed on the other element or there may be a centrally disposed element.

[0020] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by one skilled in the art to which this invention pertains. The terms used in this specification of the present invention are for the purpose of describing specific embodiments only and are not intended to limit the present invention. The term "and / or" as used herein includes any and all combinations of one or more of the associated listed items.

[0021] The sources of radioactive nuclides in nuclear wastewater mainly include those generated by the operation of fusion reactors and fission reactors and their supporting cooling systems. There are about 30 main radioactive nuclides, including radioactive 3 H. 79 Se, 90 S. 137 CS, 54 Mn, 55 Fe, 60 Co、 63 Ni, 125Corrosion products and activation products such as Sb. Existing technologies typically use chemical precipitation, ion exchange, adsorption, evaporation and concentration, Mag-Molecule methods, biological treatment, membrane separation, inert chemical methods, and zero-valent iron percolation reaction wall (PRB) technology to treat radionuclides. For example, ion exchange methods using cation exchange resins, phenolic cation resins, and macroporous cation resins can remove radioactive strontium and cesium. They can also remove colloidal zirconium, niobium, and cobalt, as well as ruthenium complexes, through adsorption. Adsorption methods using adsorbents such as activated carbon, zeolite, kaolin, bentonite, clay, activated carbon, chitosan, and modified sepiolite can effectively remove heavy metal ions.

[0022] However, these treatment methods generally only target certain radionuclides and are unable to effectively treat others simultaneously. When multiple radionuclides need to be treated, a combination of methods is required, which is very costly. Furthermore, the concentration of radionuclides in nuclear wastewater is low, only tens to hundreds of becquerels per liter (ppm), making it difficult for conventional methods to treat such low concentrations.

[0023] In view of this, the inventors discovered that based on the "salt-removal effect" of hydrates and the principle of ion separation at the molecular level, radionuclides in nuclear wastewater can be effectively separated and can be reused multiple times.

[0024] See also Figure 1 and Figure 2 An embodiment of the present application provides a nuclide separation system 10 for separating nuclides in water (such as seawater). The separation system 10 includes an air supply device 100, a plunger pump 200, a first piston container 300, a temperature control device 500 and a data acquisition and control system 600.

[0025] The gas supply device 100 is used to provide carbon dioxide. The plunger pump 200 is used to pressurize the carbon dioxide output by the gas supply device 100 to a first pressure. The first piston container 300 includes a first cavity 301 and a first piston 302 located in the first cavity 301. The first piston 302 separates the first cavity 301 into a first top space 303 and a first bottom space 304, and the first top space 303 is used to accommodate water to be treated. The first top space 303 is connected to the gas supply device 100 and is used to further accommodate the carbon dioxide transmitted from the gas supply device 100. The temperature control device 500 is used to accommodate the first piston container 300 and maintain the first piston container 300 at a first temperature so that the carbon dioxide and water form a hydrate. The pressurization of the plunger pump 200 allows the carbon dioxide to enter the first headspace 303 at a constant pressure. The temperature control device 500, which houses the first piston container 300, maintains a constant temperature. By cooling or heating the first piston container 300, the carbon dioxide can combine with water in the nuclear wastewater to form hydrates, or the hydrates can decompose to produce pure water and carbon dioxide. This achieves multi-stage concentration of radionuclides. Once the target concentration is reached, the radionuclide-rich wastewater can be collected for subsequent treatment. Optionally, the temperature control device 500 can be an air bath or a water bath. Hydration promoters can also be added to the nuclear wastewater to accelerate hydrate formation.

[0026] The data acquisition and control system 600 is used to calculate the real-time concentration of the nuclide based on the molar density of the carbon dioxide gas in the first top space 303 and the molar amount of residual water. The calculation method will be described in detail below. Specifically, the first piston container 300 has a fully visible sapphire glass. More preferably, the fully visible piston container can also be an invisible piston container. Specifically, a stirring device 311 is also provided on the first piston container 300, and the stirring device includes a stirring paddle 3110 and a motor 3111 for driving the stirring paddle. The stirring paddle 3110 is located in the first piston container 300, and the motor 3111 is provided at the end of the stirring paddle 3110 away from the first piston container 300, for driving the stirring paddle 3110. The data acquisition and control system 600 may include a processor, which may be a central processing unit (CPU), other general-purpose processors, digital signal processors (DSP), application-specific integrated circuits (ASIC), field-programmable gate arrays (FPGA), or other programmable logic devices, discrete gate or transistor logic devices, discrete hardware components, etc. The general-purpose processor may be a microprocessor or any conventional processor.

[0027] In one embodiment of the present application, the separation system 10 further includes a second piston container 400, which includes a second cavity 401 and a second piston 402 located in the second cavity 401. The second piston 402 separates the second cavity 401 into a second top space 403 and a second bottom space 404. The second top space 403 is connected to the first top space 303 and is used to accommodate water transmitted from the first top space 303. The data acquisition and control system 600 is also used to calculate the real-time concentration of nuclides based on the gas molar density of the second top space 403 and the molar amount of residual water. By providing the second piston container 400, receiving the water transmitted from the first piston container 300, and adjusting the second piston 402, the water and carbon dioxide in the second top space 403 can form hydrates, thereby achieving multi-stage synchronous concentration and improving the efficiency of hydrate formation.

[0028] In one embodiment of the present application, the separation system 10 further includes a first temperature sensor 700, a first pressure sensor 800, a second temperature sensor 701, and a second pressure sensor 801. The first temperature sensor 700 and the first pressure sensor 800 are respectively used to measure the temperature and pressure within the first piston container 300. The second temperature sensor 701 and the second pressure sensor 801 are respectively used to measure the temperature and pressure within the second piston container 400. The data acquisition and control system 600 is further used to calculate the molar density of the gas and the molar amount of residual water in the first headspace 303 and the second headspace 403 based on the acquired temperature and pressure, thereby obtaining the concentration of the nucleus in the first headspace 303 and the second headspace 403.

[0029] like Figure 2 As shown, in one embodiment of the present application, the first piston container 300 and the second piston container 400 both include a container body 310 and a piston adjustment mechanism 320. The piston adjustment mechanism 320 is arranged in the container body 310. The piston adjustment mechanism 320 includes a piston body and an adjustment member 330. The piston body is movably arranged in the container body 310. The adjustment member 330 is arranged in the container body 310 and is used to adjust the relative position of the piston body in the container body 310 to transfer the liquid in the first top space 303 to the second top space 403.

[0030] In one embodiment of the present application, the piston body is further provided with a liquid taking port 900. By providing the liquid taking port 900, real-time sampling can be achieved.

[0031] In one embodiment of the present application, the second piston container 400 is further connected to a liquid storage tank 910 , which is used to collect waste liquid in the second piston container 400 .

[0032] In one embodiment of the present application, a buffer device is further connected between the gas supply device 100 and the first piston container 300 , and the buffer device is used to buffer the carbon dioxide transmitted from the gas supply device 100 .

[0033] In one embodiment of the present application, the separation system 10 further includes a delivery pipeline, comprising a first delivery pipeline 11, a second delivery pipeline 12, and a third delivery pipeline 13. The first delivery pipeline 11 includes a first branch 111, a second branch 112, and a third branch 113. The first branch 111 connects the gas supply device 100 with the buffer device, the second branch 112 connects the plunger pump 200 with the first branch 111, and the third branch 113 connects the buffer device with the first headspace 303. The second delivery pipeline 12 includes a fourth branch 121 and a fifth branch 122. The fourth branch 121 connects the first headspace 303 with the second headspace 403, while the fifth branch 122 connects the fourth branch 121 with the outside world. The fourth branch 121 enables the transfer of concentrated nuclear wastewater from the first piston container 300 to the second piston container 400. The fifth branch 122 enables real-time sampling. The third delivery pipeline 13 connects the second headspace 403 with the liquid storage tank 910.

[0034] In one embodiment of the present application, the separation system 10 also includes a camera device 601 and a visualization window 340. The visualization window 340 is arranged on the first piston container 300 and the second piston container 400. The camera device 601 is used to capture images of hydrates generated in the first piston container 300 and the second piston container 400 through the visualization window 340.

[0035] Compared to existing technologies, the nuclide separation system 10 provided in the embodiments of the present application has the following advantages: Leveraging the "salt-removal effect" of hydrates and the principle of ion separation at the molecular level, multiple concentrations are performed to achieve nuclide enrichment, collecting wastewater containing radionuclides for subsequent treatment. Using only temperature and pressure data, the residual water content within the first piston container 300 can be calculated in real time, providing a real-time representation of the nuclide concentration within the first piston container 300. This method, which measures the real-time evolution of the nuclide concentration within the first piston container 300 by calculating the residual water content within the first piston container 300, requires only initial calibration; the nuclide concentration within the first piston container 300 can then be calculated based on the temperature and pressure values, eliminating the need for multiple measurements.

[0036] The second aspect of the present application further provides a nuclide separation method for separating nuclides in water, the separation method being implemented using the aforementioned nuclide separation system 10. Depending on different requirements, the order of certain steps or sub-steps of the measurement method may be changed, and certain steps or sub-steps may be omitted or combined. The measurement method includes: Step 1: Open the gas supply device 100 to inject carbon dioxide into the first piston container 300.

[0037] Step 2: Apply a first pressure to the carbon dioxide output from the gas supply device 100 through the plunger pump 200 and inject it into the first head space 303 .

[0038] Step 3: Using the temperature control device 500, the first piston container 300 is changed from the first temperature to the second temperature to generate hydrates.

[0039] In some embodiments, hydrate formation is induced by cooling the temperature of the first piston container 300 to 1° C. The following is the formula for the formation of carbon dioxide hydrate from carbon dioxide: , where N H is the hydration number (taken as 6.0).

[0040] Step 4: Based on the initial nuclide concentration C in the top space at the first temperature xi,0 , the gas molar density of the first head space 303 at the second temperature and the molar amount of residual water in the first head space 303 at the second temperature, according to the formula Calculate real-time concentration of nuclides C xi,t .in V L,t is the volume of the residual water in the first piston container 300, which can be determined by the residual water content n W,t Calculated.

[0041] The following is a detailed description of the calculation process of the nuclide concentration in the nuclide separation system: (Formula 1); (Formula 2); (Formula 3); (Formula 4); in, nL is the amount of CO2 dissolved in the liquid phase, nG t is the molar amount of residual gas in the gas phase, nH is the amount captured in the hydrate phase.

[0042] (Formula 5); (Formula 6); The solubility of CO2 can be calculated by formula (Formula 5) and (Formula 6). Therefore, the residual water content n at any time W,t Obtained by the volume conservation method: (Formula 7); (Formula 8); (Formula 9); Real-time evolution calculation of nuclide concentration: due to the initial X The initial concentration C xi and the initial liquid volume in the first piston container 300 V L0 It has been measured that the residual water content in the first piston container 300 at any time n W,t The above method can be used to calculate the amount of matter: Any nuclide X The initial concentration is: in V L,t is the volume of the residual water in the first piston container 300, which can be determined by the content of the residual water n W,t Calculated.

[0043] See also Figure 1 The nuclide separation system provided in the embodiment of the present application specifically includes the following steps: In step S1, carbon dioxide gas of a set first pressure P and a first temperature T is injected into the first piston container 300 through the gas supply device 100. The initial gas injection volume n0 can be calculated based on the effective dissolution Vcell and the compression factor Z0 under the thermodynamic conditions.

[0044] Step S2: Take out the test solution from the liquid taking port 900 and measure the initial concentration Cxi,0 of various nuclides by ICP-OES.

[0045] Step S3, control the temperature control system to cool down from the first temperature to the second temperature to generate hydrates. At this time, by conserving the amount of CO2 gas added (n0) and the effective volume (Vcell) of the first piston container 300, the Peng-Robinson gas state equation is solved to obtain the molar density of the gas at this time. The molar density of the solution and the molar density of the hydrate are known. Therefore, the macroscopic dynamic data considering the volume expansion of hydrate formation can be calculated, and the distribution ratio and evolution law of the gas in the three phases of gas, liquid and hydrate in real time can be obtained. The molar amount of residual water in the first piston container 300, n, is thus obtained. W,t .

[0046] Step S4, calculate the concentration C of various nuclides in the first piston container 300 at this time xi,t, and ICP-OES tests were performed to verify the calculated results.

[0047] In step S5, the piston adjustment mechanism 320 is adjusted to move the piston upward, squeezing the concentrated liquid (residual liquid that has not formed hydrates) in the first piston container 300 into the second piston container 400, and repeating the generation and measurement process. This multiple concentration process achieves radionuclide enrichment, while the hydrates decompose to produce clean water, effectively removing radionuclides.

[0048] As can be seen, the radionuclide separation system 10 and method provided in this application utilize the "salt-removal effect" of hydrates and the principle of ion separation at the molecular level to achieve radionuclide enrichment through multiple concentrations, collecting wastewater containing radionuclides for subsequent treatment. Using only temperature and pressure data, the residual water content in the reactor can be calculated in real time, allowing for real-time characterization of the radionuclide concentration within the reactor. By calculating the residual water content in the reactor in real time, the method for calculating the real-time evolution of the radionuclide concentration within the reactor requires only initial calibration. The radionuclide concentration within the reactor can then be calculated based on the temperature and pressure values, eliminating the need for multiple measurements.

[0049] At the same time, the nuclide separation method provided in this application can also be used in the following aspects: juice concentration, sewage treatment, hydrate-based CO2 storage, oil-water separation and pharmaceutical concentration.

[0050] It will be understood that the above embodiments are merely exemplary embodiments for illustrating the principles of the present invention, and the present invention is not limited thereto. Those skilled in the art will appreciate that various modifications and improvements can be made without departing from the spirit and substance of the present invention, and such modifications and improvements are also considered to be within the scope of protection of the present invention.

Claims

1. A nuclide separation system for separating nuclides in water, characterized in that: The separation system comprises: a gas supply device for providing carbon dioxide; a plunger pump, configured to pressurize the carbon dioxide to a first pressure; a first piston container comprising a first cavity and a first piston movably disposed in the first cavity, wherein the first piston divides the first cavity into a first top space and a first bottom space, wherein the first top space is connected to the gas supply device and is used to accommodate the pressurized carbon dioxide, and the first top device is also used to accommodate the water; a temperature control device for changing the temperature of the first piston container from a first temperature to a second temperature so that the carbon dioxide reacts with the water in the first head space to form a hydrate; and The data acquisition and control system is used to calculate the real-time concentration of the nuclide based on the initial nuclide concentration in the head space at the first temperature, the molar density of carbon dioxide gas in the first head space, and the molar amount of residual water.

2. The nuclide separation system according to claim 1, characterized in that: It also includes a second piston container, which includes a second cavity and a second piston movably arranged in the second cavity. The second piston divides the second cavity into a second top space and a second bottom space. The second top space is connected to the first top space and is used to accommodate water and carbon dioxide transmitted from the first top space. The data acquisition and control system is also used to calculate the real-time concentration of the nuclide based on the molar density of carbon dioxide gas in the second top space and the molar amount of residual water.

3. The nuclide separation system according to claim 2, characterized in that: The separation system further comprises: a first temperature sensor and a first pressure sensor, for measuring the temperature and pressure in the first piston container, respectively; a second temperature sensor and a second pressure sensor, for measuring the temperature and pressure in the second piston container, respectively; The data acquisition and control system is further configured to calculate the gas molar density and the molar amount of residual water in the first head space and the second head space according to the acquired temperature and pressure, and obtain the concentration of the nucleobase in the first head space and the second head space.

4. The nuclide separation system according to claim 2, characterized in that: The first piston container and the second piston container both include a container body and a piston adjustment mechanism. The piston adjustment mechanism is arranged in the container body. The piston adjustment mechanism includes a piston body and an adjustment member. The piston body is movably arranged in the container body. The adjustment member is arranged in the container body and is used to adjust the relative position of the piston body in the container body to transfer the liquid in the first top space to the second top space.

5. The nuclide separation system according to claim 4, characterized in that: The piston body is also provided with a liquid taking port.

6. The nuclide separation system according to claim 2, characterized in that: The second piston container is also connected to a liquid storage tank, which is used to collect waste liquid in the second piston container.

7. The nuclide separation system according to claim 6, characterized in that: A buffer device is further connected between the gas supply device and the first piston container, and the buffer device is used to buffer the carbon dioxide transmitted from the gas supply device.

8. The nuclide separation system according to claim 7, characterized in that: The apparatus further includes a delivery pipeline, the delivery pipeline including a first delivery pipeline, a second delivery pipeline, and a third delivery pipeline, the first delivery pipeline including a first branch pipe, a second branch pipe, and a third branch pipe, the first branch pipe connecting the air supply device and the buffer device, the second branch pipe connecting the plunger pump and the first branch pipe, and the third branch pipe connecting the buffer device and the first head space; The second delivery pipeline includes a fourth branch pipe and a fifth branch pipe, the fourth branch pipe is used to connect the first top space and the second top space, and the fifth branch pipe connects the fourth branch pipe and the outside; The third delivery pipe is used to connect the second head space and the liquid storage tank.

9. The nuclide separation system according to claim 2, characterized in that: The separation system further includes a camera device and a visualization window, wherein the visualization window is provided on the first piston container and the second piston container, and the camera device is used to capture images generated by hydrates in the first piston container and the second piston container respectively through the visualization window.

10. A method for separating nuclides in water, characterized in that: The separation method is implemented using the nuclide separation system according to any one of claims 1 to 9, and the measurement method includes: turning on the gas supply device to output carbon dioxide; applying a first pressure to the outputted carbon dioxide by the plunger pump so that the pressurized carbon dioxide is injected into the first head space; changing the first piston container from the first temperature to the second temperature by the temperature control device, so that the carbon dioxide and the water react in the first head space to form a hydrate; The real-time concentration of the nuclide is calculated according to the initial nuclide concentration in the head space at the first temperature, the gas molar density in the first head space at the second temperature, and the molar amount of residual water in the first head space at the second temperature.

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