Systems, methods, and applications for microfluidic separation of hydrogen isotopes

Abstract

This invention belongs to the field of hydrogen isotope separation technology, and relates to a system, method, and application for microfluidic separation of hydrogen isotopes. The system includes a gas-liquid separation unit, a liquid storage unit, and two fluid transport units. An internal reaction substrate is provided, with at least one open microchannel. Water in the liquid storage unit is circulated through the two fluid transport units, passing through the microchannel during the circulation process to achieve microfluidic separation of hydrogen isotopes. This invention preferentially transfers deuterium and / or tritium from the liquid phase to the gas phase through the interaction of microfluidic flow at the gas-liquid-solid three-phase interface. The system provided by this invention is simple in design, low in energy consumption, and exhibits excellent stability. It can be modularly scaled up and can be used in scenarios such as treating nuclear wastewater, purifying heavy water, preparing semiconductor ultrapure water, tritium monitoring and recovery, and biomedical isotope labeling. It overcomes the bottlenecks of traditional technologies, such as complex equipment, high energy consumption, and low separation factors, providing a new path for industrial-scale hydrogen isotope separation.

Description

Technical Field

[0001] This invention belongs to the field of hydrogen isotope separation technology, and relates to a system, method and application for separating hydrogen isotopes using microfluidic flow. Background Technology

[0002] The information disclosed in this background section is intended only to enhance understanding of the overall background of the invention and is not necessarily to be construed as an admission or in any way implying that such information constitutes prior art known to those skilled in the art.

[0003] Deuterium (D) and tritium (T), as important hydrogen isotopes, are present in extremely low concentrations in nature. However, in nuclear industry production processes, wastewater contains high concentrations of deuterium and tritium, posing multi-dimensional treatment challenges. Nuclear power plant wastewater discharges must meet stringent tritium emission limits, and the biomedical field requires efficient deuterium recovery and safe tritium removal during the synthesis of deuterium-labeled compounds. Efficient removal of deuterium and tritium from nuclear wastewater is crucial for ensuring nuclear environmental safety. Traditional deuterium-tritium separation or removal technologies include thermal diffusion, gas chromatography, chemical exchange, cryogenic distillation, electrocatalysis, and adsorption using porous materials.

[0004] However, the above methods suffer from common bottlenecks such as complex equipment, low separation factor, high energy consumption, and high cost, making them unsuitable for large-scale engineering applications. Specific shortcomings include: thermal diffusion relies on temperature gradients to achieve isotope separation, but the separation factor is relatively low; gas chromatography utilizes adsorption-diffusion synergy for separation, but its processing capacity is limited, hindering large-scale application; chemical exchange is constrained by the high cost and susceptibility to poisoning of precious metal catalysts; cryogenic distillation requires sophisticated cryogenic equipment, resulting in complex operation and high costs; electrocatalysis methods have high overall operating costs due to continuous energy consumption; and porous material adsorption faces challenges such as stringent preparation conditions for high-performance adsorbents and difficulty in achieving the required separation factor. Summary of the Invention

[0005] To address the shortcomings of existing technologies, the present invention aims to provide a system, method, and application for separating hydrogen isotopes using microfluidics. This invention utilizes microfluidics to preferentially transfer deuterium and / or tritium from the liquid phase to the gas phase at the gas-liquid-solid three-phase interface, achieving separation. Studies have shown that compared to microdroplets, microfluidics offers a higher D / H escape rate ratio and a faster HD exchange rate, while also reducing the cost of constructing the system, thus facilitating industrial applications.

[0006] To achieve the above objectives, the technical solution of the present invention is as follows: In a first aspect, a system for separating hydrogen isotopes using microfluidics includes: A gas-liquid separation unit has an internal reaction substrate with at least one open microchannel, allowing water containing deuterium and / or tritium to flow continuously within the microchannel. During this continuous flow, the water, the reaction substrate, and the gas within the gas-liquid separation unit form a gas-liquid-solid three-phase interface. The width or diameter of the axial cross-section of the microchannel is 0.5–3 mm. During system operation, the humidity within the gas-liquid separation unit is 70–98% RH. A liquid storage unit for storing water containing deuterium and / or tritium; The first fluid delivery unit is used to deliver water containing deuterium and / or tritium in the liquid storage unit to the microchannel inlet of the gas-liquid separation unit; The second fluid delivery unit is used to transport the water processed by the microchannel of the gas-liquid separation unit back to the liquid storage unit, thereby realizing the circulating flow of water containing deuterium and / or tritium. And the piping connecting each unit.

[0007] This invention provides a reaction substrate with an open microchannel, which allows water containing deuterium and / or tritium to flow through the microchannel and form a gas-liquid-solid three-phase interface with the reaction substrate and the surrounding gas. Under the action of the gas-liquid-solid three-phase interface, deuterium and / or tritium preferentially transfer from the liquid phase to the gas phase, thus achieving separation.

[0008] In a second aspect, a method for separating hydrogen isotopes using microfluidic flow involves circulating water containing deuterium and / or tritium in a microchannel using the system described in the first aspect of this invention. Under the action of the gas-liquid-solid three-phase interface, deuterium and / or tritium are transferred from the liquid phase to the gas phase, thereby achieving separation.

[0009] Thirdly, the application of the system described in the first aspect of the present invention or the method described in the second aspect of the present invention in the removal of deuterium and tritium from nuclear wastewater, purification of heavy water, preparation of semiconductor ultrapure water, synthesis of biomedical deuterium-labeled compounds, or monitoring and recovery of tritium.

[0010] The beneficial effects of this invention are as follows: (1) This invention applies microfluidic technology to hydrogen isotope separation. By constructing microchannels on the reaction substrate, the D / H escape rate ratio is significantly improved and the HD exchange rate is accelerated under the synergistic effect of the gas-liquid-solid three-phase interface, enabling a highly efficient and low-energy separation process. This system does not require external electric fields, magnetic fields, or high-temperature and high-pressure conditions. It relies solely on microscale fluid behavior and interface effects to drive the preferential migration of deuterium / tritium from the liquid phase to the gas phase, effectively avoiding the problems of high energy consumption, complex equipment, and secondary pollution that exist in traditional distillation, electrolysis, or chemical exchange methods.

[0011] (2) The present invention has a wide range of material selection for the reaction substrate for constructing microchannels, and can be adapted to a variety of materials including metals, alloys, polymers, and inorganic non-metals. It does not require special customization of expensive special separation materials, and the overall cost is extremely low.

[0012] (3) The separation factor of the system and method provided by the present invention can be flexibly adjusted in the range of 10 to 50,000, which can adapt to the different purity requirements of hydrogen isotope products in different application scenarios.

[0013] (4) The system and method provided by the present invention can operate stably at room temperature and pressure without the need for special reaction conditions such as high temperature and high pressure. The overall energy consumption is extremely low, and the energy consumption per unit of deuterium removal can be as low as 0.024 GJ / kg.

[0014] (5) The system provided by the present invention has a simple structure and can be modularly scaled up, making it suitable for industrial continuous production. Attached Figure Description

[0015] The accompanying drawings, which form part of this invention, are used to provide a further understanding of the invention. The illustrative embodiments of the invention and their descriptions are used to explain the invention and do not constitute an improper limitation of the invention.

[0016] Figure 1 This is a schematic diagram of the microfluidic system constructed in Embodiment 1 of the present invention, wherein 1 is the reaction substrate, 2 is the reaction chamber, 3 is the liquid distributor, 4 is the liquid collector, 5 is the liquid storage bottle, 6 is the first peristaltic pump, and 7 is the second peristaltic pump. Figure 2 The graphs show the changes in deuterium concentration over time for different inlet and outlet flow rates in Examples 1-3 of the present invention. Figure 3 This is a bar chart comparing the D2O mass transfer flux of different inlet and outlet flow rates in Examples 1-3 of the present invention. Figure 4 This is a bar chart comparing the D / H escape rate ratios for different inlet and outlet flow rates in Examples 1-3 of the present invention. Figure 5 The graphs show the changes in deuterium concentration over time for different substrates in Examples 1, 4-5 of the present invention. Figure 6 The above are bar charts comparing the D2O mass transfer flux of different substrates in Examples 1, 4-5 of this invention. Figure 7 This is a bar chart comparing the D / H escape rate ratios of different substrates in Examples 1, 4-5 of the present invention; Figure 8 The graphs show the changes in deuterium concentration over time for different initial D2O concentrations in Examples 1, 7-9 of the present invention. Figure 9The bar charts show the comparison of D2O mass transfer flux with different initial D2O concentrations in Examples 1, 7-9 of the present invention. Figure 10 This is a bar chart comparing the D / H escape rate ratios for different initial D2O concentrations in Examples 1, 7-9 of the present invention. Figure 11 This is a bar chart comparing the separation factors for different initial D2O concentrations in Examples 1, 7-9 of the present invention. Figure 12 This is a time-dependent decay diagram of the tritium-containing radioactive solution in Example 10 of the present invention. Detailed Implementation

[0017] It should be noted that the following detailed descriptions are exemplary and intended to provide further illustration of the invention. Unless otherwise specified, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention pertains.

[0018] It should be noted that the terminology used herein is for the purpose of describing particular embodiments only and is not intended to limit the scope of exemplary embodiments according to the invention. As used herein, the singular form is intended to include the plural form as well, unless the context clearly indicates otherwise. Furthermore, it should be understood that when the terms "comprising" and / or "including" are used in this specification, they indicate the presence of features, steps, operations, devices, components, and / or combinations thereof.

[0019] Traditional techniques for separating hydrogen isotopes suffer from problems such as complex equipment, high energy consumption, and low separation factor. This invention proposes a system, method, and application for separating hydrogen isotopes using microfluidic flow.

[0020] A typical embodiment of the present invention provides a system for separating hydrogen isotopes using microfluidic flow, comprising: A gas-liquid separation unit has an internal reaction substrate with at least one open microchannel, allowing water containing deuterium and / or tritium to flow continuously within the microchannel. During this continuous flow, the water, the reaction substrate, and the gas within the gas-liquid separation unit form a gas-liquid-solid three-phase interface. The width or diameter of the axial cross-section of the microchannel is 0.5–3 mm. During system operation, the humidity within the gas-liquid separation unit is 70–98% RH. A liquid storage unit for storing water containing deuterium and / or tritium; The first fluid delivery unit is used to deliver water containing deuterium and / or tritium in the liquid storage unit to the microchannel inlet of the gas-liquid separation unit; The second fluid delivery unit is used to transport the water processed by the microchannel of the gas-liquid separation unit back to the liquid storage unit, thereby realizing the circulating flow of water containing deuterium and / or tritium. And the piping connecting each unit.

[0021] The first fluid delivery unit and the second fluid delivery unit of the present invention can be pumps, such as peristaltic pumps.

[0022] When the system described in this invention is running, the humidity inside the gas-liquid separation unit can be 70% RH, 71% RH, 72% RH, 73% RH, 74% RH, 75% RH, 76% RH, 77% RH, 78% RH, 79% RH, 80% RH, 81% RH, 82% RH, 83% RH, 84% RH, 85% RH, 86% RH, 87% RH, 88% RH, 89% RH, 90% RH, 91% RH, 92% RH, 93% RH, 94% RH, 95% RH, 96% RH, 97% RH, 98% RH, or any two values ​​between them.

[0023] The width or diameter of the axial cross section of the microchannel described in this invention can be 0.5~2 mm, 0.5~1.5 mm, 0.8~1.2 mm, etc.

[0024] In some embodiments, the reaction substrate is made of a metal, a polymer, or an inorganic non-metal. Specifically, the metal includes, but is not limited to, nickel, copper, aluminum, iron, titanium, gold, silver, platinum, stainless steel, and their alloys. Specifically, the polymer includes, but is not limited to, polytetrafluoroethylene, polyvinyl chloride, polydimethylsiloxane, polypropylene, polyethylene, and polyetheretherketone. Specifically, the inorganic non-metal includes, but is not limited to, quartz, glass, ceramics, silicon, silicon carbide, and alumina.

[0025] In some embodiments, the methods for creating microchannels include computer numerical control (CNC) engraving technology, laser etching, chemical etching, injection molding, 3D printing, etc.

[0026] In some embodiments, the number of microchannels opened is 1 to 100. It can be 1 to 90, 1 to 80, 1 to 70, 1 to 60, 1 to 50, 1 to 40, 1 to 30, 1 to 20, 1 to 10, etc.

[0027] The shape of the axial cross section of the microchannel can be arbitrary. In some embodiments, the shape of the axial cross section of the microchannel is rectangular, semi-circular, trapezoidal or triangular.

[0028] In some embodiments, a liquid distributor is included, the outlet of which is connected to the inlet of the microchannel. This is used to divert water containing deuterium and / or tritium into the microchannel.

[0029] In some embodiments, the reaction substrate is tilted. This facilitates the flow of water containing deuterium and / or tritium.

[0030] In some embodiments, a liquid collector is provided at the microchannel outlet to collect the treated water for easy return to the storage unit.

[0031] Another embodiment of the present invention provides a method for separating hydrogen isotopes using microfluidic flow. The method involves circulating water containing deuterium and / or tritium in a microchannel using the above-described system. Under the action of the gas-liquid-solid three-phase interface, deuterium and / or tritium are transferred from the liquid phase to the gas phase, thereby achieving separation.

[0032] In some embodiments, the separation temperature is 15~45°C. Specifically, the separation temperature is 20~30°C. The separation process is carried out under normal pressure conditions (80~110 kPa).

[0033] In some embodiments, the separation factor (α) is 10 to 700.

[0034] In some embodiments, in water containing deuterium and / or tritium, the deuterium concentration is 200 ppm to 20% (w / w), and the tritium concentration is 10 ppm. 4 ~10 9 Bq / L, the recombination is divided into one or more of D2O, T2O, HDO, HTO, and DTO.

[0035] In some embodiments, the reflux ratio during the circulation process is 0.1 to 10:1. Specifically, the reflux ratio is 1 to 5:1, 1 to 2:1, 1 to 1.5:1, 1 to 1.2:1, etc. Specifically, the influent flow rate is 5 to 25 mL / min. -1 Specifically, the reflux flow rate is 5~25 mL·min. -1 .

[0036] A third embodiment of the present invention provides an application of the above-described system or method in treating deuterium-tritium nuclear wastewater, purifying heavy water, preparing semiconductor ultrapure water, synthesizing biomedical deuterium-labeled compounds, or monitoring and recovering tritium.

[0037] To enable those skilled in the art to better understand the technical solution of the present invention, the technical solution of the present invention will be described in detail below with reference to specific embodiments.

[0038] Example 1: Microchannel separation of deuterium water on a nickel substrate I. Construction of a microfluidic system for separating hydrogen isotopes (hereinafter referred to as a microfluidic system) The nickel substrate was placed in a 1 mol·L⁻¹ solution. -1The nickel substrate was soaked in HCl for 30 min, ultrasonically cleaned 5 times with deionized water until pH=7.0, and vacuum dried at 80℃ for 4 h. Ten parallel microchannels (1.0 mm wide and 1.0 mm deep) were machined on the nickel surface using CNC engraving. The processed nickel substrate was used as a reaction substrate and circulated and coupled with a dual peristaltic pump, a liquid distributor, tubing, and a liquid storage bottle to construct a microfluidic system. Specifically, as shown... Figure 1 As shown, the reaction substrate 1 is inclinedly arranged inside the reaction chamber 2, which serves as the reaction unit. The microchannel port at the top of the inclined reaction substrate 2 serves as the inlet of the microchannel. A liquid distributor 3 is installed at the inlet of the microchannel, and the microchannel port at the bottom of the inclined reaction substrate 2 serves as the outlet of the microchannel. A liquid collector 4 is installed at the outlet of the microchannel to receive water flowing out of the microchannel. One pipeline connects the liquid storage bottle 5 and the liquid distributor 3, and a first peristaltic pump 6 transports the water in the liquid storage bottle 5 to the liquid distributor 3. After being split by the liquid distributor 3, the water enters the microchannel of the reaction substrate 1. Another pipeline connects the liquid storage bottle 5 and the liquid collector 4, and a second peristaltic pump 7 transports the water in the liquid collector 4 back to the liquid storage bottle 5.

[0039] II. Microfluidic Separation Method for Hydrogen Isotopes Simulated deuterium-containing wastewater with an initial D2O concentration of 2000 ppm was added to the liquid storage bottle of the microfluidic system constructed in this embodiment. The inflow and outflow rates were set to 15 mL / min. -1 and 15 mL·min -1 (Reflux ratio 1:1), continuous operation at 25℃, 80% RH, and normal pressure.

[0040] Example 2: Separation of deuterium water using a nickel-based microchannel system This embodiment is the same as Embodiment 1, except that the inlet flow rate and the return flow rate are set to 10 mL / min. -1 and 20 mL·min -1 (Reflux ratio 2:1).

[0041] Example 3: Separation of deuterium water using a nickel-based microchannel system This embodiment is the same as Embodiment 1, except that the inlet flow rate and the return flow rate are set to 5 mL / min. -1 and 25 mL·min -1 (Reflux ratio 5:1).

[0042] The FT-IR monitoring results of Examples 1-3 are as follows: Figures 2-4 As shown, the separation efficiency of isotopic hydrogen is highest when the reflux ratio is 1:1. After 3 hours, the deuterium concentration drops to its natural abundance (approximately 150 ppm), corresponding to the HD exchange rate ( H-DThe concentration was 0.78 mg / min. -1 D2O mass transfer flux ( J ) is 52 kg·m -2 ·h -1 D / H escape rate ratio ( R The value is 350, and the water separation factor (α) is 13.37. The optimal HD exchange rate in the microdroplet method ( H-D The value was 0.0197 mg·min. -1 Optimal D / H escape rate ratio ( R The value is 2.6. This indicates that the microfluidic method has a higher D / H escape rate ratio and a faster HD exchange rate, proving that the microfluidic method of the present invention produces a more significant hydrogen isotope separation effect.

[0043] Example 4: Microchannel separation of deuterium water on a copper substrate This embodiment is the same as Embodiment 1, except that the nickel substrate is replaced with a copper substrate.

[0044] Example 5: Microchannel separation of deuterium water on an aluminum substrate This embodiment is the same as Embodiment 1, except that the nickel substrate is replaced with an aluminum substrate.

[0045] The results are as follows Figures 5-7 As shown, Al has the worst deuterium removal efficiency, with a deuterium removal cycle of 6 hours, corresponding to a HD exchange rate ( H-D Only 0.39 mg·min -1 The performance of Cu was slightly improved, and the deuterium removal cycle was shortened to 5 hours. H-D Increased to 0.46 mg·min -1 Al and Cu substrates J The values ​​were 26 and 31 kg m, respectively. -2 h -1 Al and Cu substrates R The values ​​were 140 and 233, respectively, and α was 13.37 for both. Both metals could effectively separate isotopes, proving that metallic substrates are generally applicable.

[0046] Example 6: Separation of deuterium water using a polymer substrate (PTFE) This embodiment is the same as Embodiment 1, except that the nickel substrate is replaced with a PTFE substrate.

[0047] The results showed that the deuterium removal cycle of the PTFE substrate was 4 h, corresponding to a HD exchange rate ( H-D The concentration was 0.58 mg / min. -1 ,J The value is 38.7 kg·m -2 ·h -1 , R The value is 116.67, and α is 13.37. PTFE can also effectively separate isotopes, proving that polymeric substrates are generally applicable.

[0048] Example 7: Separation of deuterium water using a nickel-based microchannel This embodiment is the same as Embodiment 1, except that the initial D2O concentration in the simulated deuterium-containing wastewater is 15,000 ppm.

[0049] Example 8: Separation of deuterium water using a nickel-based microchannel system This embodiment is the same as Embodiment 1, except that the initial D2O concentration in the simulated deuterium-containing wastewater is 50,000 ppm.

[0050] Example 9: Microchannel separation of deuterium water on a nickel substrate This embodiment is the same as Embodiment 1, except that the initial D2O concentration in the simulated deuterium-containing wastewater is 100,000 ppm.

[0051] The results of Examples 1 and 7-9 are as follows Figures 8-11 As shown, the low concentration system (2000 ppm) has the shortest deuterium removal cycle (3 h). H-D It is 0.78 mg·min -1 When the concentration was increased to 15,000 and 50,000 ppm, the deuterium removal cycle was extended to 13 h and 27 h, respectively. H-D The levels increased to 1.3 and 1.93 mg min, respectively. -1 The deuterium removal cycle for the high-concentration system (100,000 ppm) is 50 h. H-D Stable at 1.94 mg·min -1 2000, 15000, 50000 and 100000 ppm conditions J The values ​​were 52, 89, 144, and 155 kg m, respectively. -2 h -1 At 100,000 ppm J The highest value confirms its optimal deuterium / tritium removal capability. However... R It decreases with increasing initial concentration, at 100,000 ppm. RThe value still reaches 5.93. Furthermore, the separation factors (α) of water with increasing D2O concentrations are 13.37, 98.35, 359.67, and 696.7, respectively. This demonstrates that the system can maintain efficient hydrogen-deuterium separation performance even under high concentration conditions, and can be directly applied to the treatment of high-concentration hydrogen isotope wastewater, reducing the additional load and energy consumption caused by dilution in traditional treatment processes.

[0052] Example 10: Separation of tritium-containing radioactive wastewater using nickel-based microchannels This embodiment is the same as Embodiment 1, except that the simulated deuterium-containing wastewater is replaced with tritium-containing wastewater (initial tritium concentration is 2.5 × 10⁻⁶). 5 Bq·L -1 ).

[0053] The results are as follows Figure 12 As shown, the initial tritium concentration in the system is 2.5 × 10⁻⁶. 5 Bq·L -1 After 42 hours of continuous operation, the tritium concentration finally dropped to 1.2 × 10⁻⁶. 5 Bq·L -1 The tritium removal rate reached 52%, which clearly demonstrated the feasibility and effectiveness of the system, enabling the treatment of radioactive tritium water and making it suitable for radioactive wastewater treatment scenarios in the nuclear industry.

[0054] Cost and energy consumption assessment The system cost structure according to the embodiments of the present invention is as follows: peristaltic pump ($47.8%, $557.1); reaction unit ($21.3%, $248.2); main body of the deuterium / tritium removal microfluidic system (i.e., the reaction chamber in Example 1, $18.9%, $220.1); liquid distributor ($7.2%, $83.6); liquid collector ($3.6%, $41.8), auxiliary accessories ($0.7%, $8.4), and liquid storage bottle ($0.6%, $7.0), the total cost of the system is $1166.2. Based on the treatment capacity of 800,000 kg / year of deuterium-containing wastewater, combined with the system treatment efficiency and operating energy consumption, the unit cost of deuterium / tritium removal is $0.44·kg. -1 The system's cost is significantly lower than existing similar deuterium removal equipment (5 $·kg). -1 This further confirms that the advantages of the microfluidic system stem from the low-cost nickel catalyst and the efficient three-phase interface catalytic mechanism.

[0055] The microfluidic hydrogen isotope separation system constructed in this invention can achieve low-cost, low-energy-consumption, high-throughput, and highly selective deuterium and tritium removal, providing an industrial upgrading technology solution for nuclear wastewater treatment, semiconductor ultrapure water preparation, and biomedical deuterium-labeled compound synthesis, with broad application prospects.

[0056] The above description is merely a preferred embodiment of the present invention and is not intended to limit the invention. Various modifications and variations can be made to the present invention by those skilled in the art. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of the present invention should be included within the scope of protection of the present invention.

Claims

1. A system for separating hydrogen isotopes using microfluidics, characterized in that it comprises: A gas-liquid separation unit is provided with an internal reaction substrate. The reaction substrate has at least one open microchannel, allowing water containing deuterium and / or tritium to flow continuously within the microchannel. During this continuous flow, the water, the reaction substrate, and the gas within the gas-liquid separation unit form a gas-liquid-solid three-phase interface. The width or diameter of the axial cross-section of the microchannel is 0.5~3 mm. During system operation, the humidity within the gas-liquid separation unit is 70-98% RH. A liquid storage unit for storing water containing deuterium and / or tritium; The first fluid delivery unit is used to deliver water containing deuterium and / or tritium in the liquid storage unit to the microchannel inlet of the gas-liquid separation unit; The second fluid delivery unit is used to transport the water processed by the microchannel of the gas-liquid separation unit back to the liquid storage unit, thereby realizing the circulating flow of water containing deuterium and / or tritium. And the piping connecting each unit.

2. The system as described in claim 1, characterized in that, The reaction substrate is made of metal, polymer material or inorganic non-metal.

3. The system as described in claim 1, characterized in that, The methods for creating microchannels include computer digital control engraving technology, laser etching, chemical etching, injection molding, or 3D printing.

4. The system as described in claim 1, characterized in that, The shape of the axial cross section of the microchannel can be rectangular, semi-circular, trapezoidal, or triangular.

5. The system as described in claim 1, characterized in that, Includes a liquid distributor, the outlet of which is connected to the inlet of the microchannel.

6. The system as claimed in claim 1, characterized in that, The reaction substrate is tilted.

7. The system as claimed in claim 1, characterized in that, A liquid collector is installed at the microchannel outlet to collect the treated water for easy return to the storage unit.

8. A method for separating hydrogen isotopes using microfluidics, characterized in that, The system described in any one of claims 1 to 7 is used to circulate water containing deuterium and / or tritium in a microchannel. Under the action of the gas-liquid-solid three-phase interface, deuterium and / or tritium are transferred from the liquid phase to the gas phase, thereby achieving separation.

9. The method of claim 8, characterized in that, The separation temperature is 20~30℃; Alternatively, the separation factor can be 10 to 700. Alternatively, in water containing deuterium and / or tritium, the deuterium concentration is 200 ppm to 20% w / w, and the tritium concentration is 10 ppm. 4 ~10 9 Bq / L, recombination is divided into one or more of D2O, T2O, HDO, HTO, and DTO; Alternatively, during the cyclic process, the reflux ratio is 0.1 to 10:

1.

10. The application of the system according to any one of claims 1 to 7 or the method according to claim 8 or 9 in the treatment of deuterium-tritium nuclear wastewater, heavy water purification, preparation of semiconductor ultrapure water, synthesis of biomedical deuterium-labeled compounds, or tritium monitoring and recovery.

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