High-temperature gas cooled reactor nuclear power station loop purification system

Abstract

The invention relates to the technical field of high-temperature gas cooled reactor nuclear power station systems, and discloses a high-temperature gas cooled reactor nuclear power station loop purification system which comprises a purification operation channel, a first heat exchanger and a cooling capacity recovery channel. Through the arrangement of the cooling capacity backflow pipeline and the arrangement of the first heat exchanger, on-way resistance is increased, escape of liquid nitrogen can be properly reduced, meanwhile, evaporation of a large amount of liquid nitrogen caused by the arrangement of a large opening of the liquid nitrogen tank is avoided, consumption of the liquid nitrogen is remarkably reduced, and the energy cost is effectively reduced. The exhaust pipeline is arranged at the rear end of the first heat exchanger, and the temperature of nitrogen is increased after heat exchange, so that the phenomenon of freezing and blocking of the exhaust pipeline is avoided, and equipment faults caused by too low temperature are reduced; the liquid nitrogen evaporation and heat exchange process is accurately controlled, so that the overall operation stability is improved, the influence of temperature fluctuation on equipment is reduced, and meanwhile, the stability and long-term reliability of the whole loop purification system are enhanced.

Description

Technical Field

[0001] The present invention relates to the technical field of high-temperature gas-cooled reactor nuclear power plant systems, and in particular to a high-temperature gas-cooled reactor nuclear power plant circuit purification system. Background Art

[0002] High-temperature gas-cooled reactors use helium as the coolant in their loops. To prevent corrosion of fuel elements and reactor structural materials by impurities in the helium, and to reduce radioactivity and the generation of radioactive waste, the purity of the loop helium must be strictly controlled, with the impurity content reduced to a specified level. These impurities are primarily chemical and radioactive.

[0003] Chemical impurities in helium coolant are primarily water, oxygen, carbon monoxide, and carbon dioxide. Therefore, in the helium purification system of high-temperature gas-cooled reactor nuclear power plants, a copper oxide bed is used to treat hydrogen and carbon monoxide (converting them into water and carbon dioxide), followed by a molecular sieve bed that adsorbs the water and carbon dioxide. For radioactive impurities and chemical impurities not fully adsorbed by other equipment, a low-temperature activated carbon bed (immersed in a liquid nitrogen tank) is used to adsorb radioactive gas fission products and simultaneously adsorb chemical impurities in the helium.

[0004] Because the helium purification system operates continuously, the activated carbon bed must be kept at a constant low temperature. Otherwise, its adsorption capacity for impurities will be significantly reduced, and impurity gases will be released from the bed and returned to the helium loop. To maintain the required low temperature for the activated carbon bed, liquid nitrogen must be continuously consumed. Based on operating experience, a 250MW high-temperature gas-cooled reactor consumes approximately 4m³ of liquid nitrogen per day. After evaporating from the cryogenic adsorber's liquid nitrogen tank, the liquid nitrogen remains very cold (nitrogen vaporization temperature is approximately -196°C). It is then discharged through insulated piping into the exhaust duct and ultimately into the atmosphere.

[0005] The nitrogen volatilized from the liquid nitrogen tank of the low-temperature adsorber is directly discharged into the exhaust duct, which will lead to a waste of nitrogen cooling capacity. Secondly, the exhaust duct is in a slightly negative pressure state, which is equivalent to continuously pumping the volatilized nitrogen from the liquid nitrogen tank, accelerating the volatilization of liquid nitrogen and causing increased liquid nitrogen consumption. After the volatilized low-temperature nitrogen enters the exhaust duct, the water and part of the carbon dioxide in the exhaust duct will freeze, causing the exhaust port to freeze and block, affecting the operation of the exhaust system. Fourthly, the cabin concrete will be damaged by low temperature, affecting the integrity of the cabin structure. Summary of the Invention

[0006] In view of this, the present invention provides a high-temperature gas-cooled reactor nuclear power plant loop purification system to reduce the waste of nitrogen cooling capacity in the prior art, reduce the consumption of liquid nitrogen, and avoid the problems of freezing and blockage of the exhaust vents and low-temperature damage to the cabin concrete.

[0007] In order to solve the above technical problems, the technical solutions of the present invention are as follows:

[0008] The present invention provides a loop purification system for a high-temperature gas-cooled reactor nuclear power plant, comprising: a purification operation channel, a first heat exchanger, and a cold recovery channel; the purification operation channel comprises an electric heater, a copper oxide bed, a molecular sieve bed, and a low-temperature adsorber, which are sequentially connected and arranged along the direction of helium flow through a pipeline, the inlet end of the electric heater being connected to the outlet of a helium blower, and the low-temperature adsorber being arranged in a liquid nitrogen tank; the first heat exchanger being arranged between the copper oxide bed and the molecular sieve bed; the cold recovery channel comprising a cold return pipe and an exhaust pipe, one end of the cold return pipe being connected to the outlet of the liquid nitrogen tank, and the other end being connected to the exhaust pipe; nitrogen in the liquid nitrogen tank evaporates, passes through the cold return pipe, undergoes heat exchange with high-temperature helium after passing through the copper oxide bed in the first heat exchanger, and is then discharged from the exhaust pipe.

[0009] It has the following advantages:

[0010] This application optimizes the design of the cold recovery channel. After evaporating nitrogen from the liquid nitrogen tank, it undergoes efficient heat exchange with high-temperature helium purified by a copper oxide bed in the first heat exchanger. The nitrogen cools the high-temperature helium, achieving cold recovery and reuse. Furthermore, the placement of the cold return duct through the first heat exchanger increases the resistance along the way, which can appropriately reduce the escape of liquid nitrogen. This also avoids the large evaporation of liquid nitrogen caused by the large opening of the liquid nitrogen tank, significantly reducing liquid nitrogen consumption and effectively lowering energy costs. The exhaust duct is located at the rear end of the first heat exchanger. After heat exchange, the nitrogen temperature rises, preventing the exhaust duct from freezing and blocking, thereby reducing equipment failures caused by excessively low temperatures. Furthermore, the nitrogen evaporation and heat exchange process in the liquid nitrogen tank reduces potential damage to the cabin concrete due to low temperatures, thereby improving the stability and safety of the system. This application precisely controls the evaporation and heat exchange process of liquid nitrogen to improve the overall operational smoothness, reduce the impact of temperature fluctuations on equipment, and enhance the stability and long-term reliability of the entire loop purification system.

[0011] According to some embodiments of the present invention, the high-temperature gas-cooled reactor nuclear power plant loop purification system also includes a helium reflux channel, a second heat exchanger and a third heat exchanger, the second heat exchanger is arranged between the copper oxide bed and the first heat exchanger, the third heat exchanger is arranged between the molecular sieve bed and the low-temperature adsorber, one end of the helium reflux channel is connected to the outlet of the low-temperature adsorber, the helium reflux channel is connected to the third heat exchanger and the second heat exchanger in sequence, and the other end is connected to the helium blower inlet, and heat is exchanged with the helium in the purification operation channel through the third heat exchanger and the second heat exchanger.

[0012] According to some embodiments of the present invention, along the flow direction of the helium gas, a dust filter is provided at the front end of the electric heater; and a pipeline filter is provided at the rear end of the copper oxide bed.

[0013] According to some embodiments of the present invention, a three-way valve is provided on the cold return pipe, and the exhaust pipe includes a first exhaust pipe and a second exhaust pipe. The first exhaust pipe is connected to the cold return pipe through the first heat exchanger, and the second exhaust pipe is connected to the cold return pipe through the three-way valve.

[0014] According to some embodiments of the present invention, the high-temperature gas-cooled reactor nuclear power plant loop purification system also includes a first bypass pipe, one end of the first bypass pipe is connected to the front end of the copper oxide bed, and the other end of the first bypass pipe is connected to the rear end of the pipeline filter. The first bypass pipe is connected in parallel with the copper oxide bed and the pipeline filter to form a first bypass loop, and a first valve group is provided on the first bypass loop.

[0015] According to some embodiments of the present invention, the second heat exchanger is a medium-temperature helium-helium heat exchanger, the first heat exchanger is a nitrogen-helium heat exchanger, and the third heat exchanger is a low-temperature helium-helium heat exchanger.

[0016] According to some embodiments of the present invention, the purification operation channel is further provided with a fourth heat exchanger and a gas-water separator. The fourth heat exchanger and the gas-water separator are sequentially arranged between the first heat exchanger and the molecular sieve bed along the helium flow direction. The fourth heat exchanger is a water-helium cooler.

[0017] According to some embodiments of the present invention, the high-temperature gas-cooled reactor nuclear power plant loop purification system also includes a second bypass pipe, one end of the second bypass pipe is connected to the front end of the molecular sieve bed, and the other end of the second bypass pipe is connected to the rear end of the molecular sieve bed. The second bypass pipe and the molecular sieve bed are arranged in parallel to form a second bypass loop, and a second valve group is provided on the second bypass loop.

[0018] According to some embodiments of the present invention, the high temperature gas-cooled reactor nuclear power plant loop purification system further includes a third bypass pipe, one end of which is connected to the molecular sieve bed, and the other end of which is connected to the helium reflux channel.

[0019] According to some embodiments of the present invention, the high-temperature gas-cooled reactor nuclear power plant loop purification system also includes an additional drive unit, which is arranged in parallel on the helium reflux channel, and the additional drive unit includes a first diaphragm compressor and a second diaphragm compressor arranged in parallel. BRIEF DESCRIPTION OF THE DRAWINGS

[0020] In order to more clearly illustrate the specific embodiments of the present invention or the technical solutions in the prior art, the following briefly introduces the drawings required for use in the specific embodiments or the description of the prior art. Obviously, the drawings described below are some embodiments of the present invention. For ordinary technicians in this field, other drawings can be obtained based on these drawings without paying any creative work.

[0021] Figure 1 A schematic diagram of a high-temperature gas-cooled reactor nuclear power plant circuit purification system provided in some embodiments of the present invention;

[0022] Description of reference numerals:

[0023] 1. Purification operation channel; 101. Electric heater; 102. Copper oxide bed; 103. Molecular sieve bed; 104. Cryogenic adsorber; 105. Liquid nitrogen tank; 106. Dust filter; 107. Pipeline filter; 108. Fourth heat exchanger; 109. Gas-water separator; 2. Helium reflux channel; 3. Cold recovery channel; 301. Cold reflux duct; 302. First exhaust duct; 303. Second exhaust duct; 304. Three-way valve; 4. First heat exchanger; 5. Second heat exchanger; 6. Third heat exchanger; 7. First bypass pipe; 701. First valve group; 8. Second bypass pipe; 801. Second valve group; 9. Third bypass pipe; 10. Helium blower; 11. Additional drive unit; 1101. First diaphragm compressor; 1102. Second diaphragm compressor. DETAILED DESCRIPTION

[0024] To make the purpose, technical solutions, and advantages of the embodiments of the present invention more clear, the technical solutions in the embodiments of the present invention will be clearly and completely described below in conjunction with the accompanying drawings in the embodiments of the present invention. Obviously, the described embodiments are part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without making creative efforts shall fall within the scope of protection of the present invention.

[0025] In the description of the present invention, it should be noted that the terms "center," "upper," "lower," "left," "right," "vertical," "horizontal," "inner," and "outer," etc., indicating orientations or positional relationships, are based on the orientations or positional relationships shown in the accompanying drawings and are intended solely to facilitate and simplify the description of the present invention. They are not intended to indicate or imply that the devices or components referred to must have, be constructed, or operate in a specific orientation, and therefore should not be construed as limitations on the present invention. Furthermore, the terms "first," "second," and "third" are used for descriptive purposes only and should not be construed as indicating or implying relative importance.

[0026] In the description of the present invention, it should be noted that, unless otherwise expressly specified or limited, the terms "mounted," "connected," and "connected" should be understood in a broad sense. For example, they may refer to fixed, detachable, or integral connections; mechanical or electrical connections; direct or indirect connections through an intermediate medium; and internal communication between two components. Those skilled in the art will understand the specific meanings of the above terms in the present invention based on the specific circumstances.

[0027] In addition, the technical features involved in the different embodiments of the present invention described below can be combined with each other as long as they do not conflict with each other.

[0028] Reference Figure 1 As shown, the present invention provides a loop purification system for a high-temperature gas-cooled reactor nuclear power plant, comprising: a purification operation channel 1, a first heat exchanger 4, and a cold recovery channel 3. The purification operation channel 1 includes an electric heater 101, a copper oxide bed 102, a molecular sieve bed 103, and a low-temperature adsorber 104, which are sequentially connected by pipes along the helium flow direction. The inlet end of the electric heater 101 is connected to the outlet of the helium blower 10, and the low-temperature adsorber 104 is located in a liquid nitrogen tank 105. The first heat exchanger 4 is located between the copper oxide bed 102 and the molecular sieve bed 103. The cold recovery channel 3 includes a cold return pipe 301 and an exhaust pipe. One end of the cold return pipe 301 is connected to the outlet of the liquid nitrogen tank 105, and the other end is connected to the exhaust pipe. Nitrogen in the liquid nitrogen tank 105 evaporates, passes through the cold return pipe 301, undergoes heat exchange with the high-temperature helium after passing through the copper oxide bed 102 in the first heat exchanger 4, and is then discharged from the exhaust pipe.

[0029] Specifically, the present application optimizes the design of the cold recovery channel 3. After the nitrogen in the liquid nitrogen tank 105 evaporates, it undergoes efficient heat exchange with the high-temperature helium purified by the copper oxide bed 102 in the first heat exchanger 4. The high-temperature helium is cooled by nitrogen, thereby realizing the recovery and reuse of cold. In addition, by setting up the cold return pipe 301, the resistance along the way is increased through the setting of the first heat exchanger 4, which can appropriately reduce the escape of liquid nitrogen. At the same time, the large evaporation of liquid nitrogen caused by the large opening of the liquid nitrogen tank 105 is avoided, so that the consumption of liquid nitrogen is significantly reduced, effectively reducing energy costs. The exhaust duct is set at the rear end of the first heat exchanger 4. After the nitrogen is heat exchanged, the temperature rises, thereby avoiding the freezing and blockage of the exhaust duct, thereby reducing equipment failures caused by excessively low temperatures. In addition, the evaporation and heat exchange process of the nitrogen in the liquid nitrogen tank 105 reduces the potential damage of low temperature to the cabin concrete, thereby improving the stability and safety of the system. This application improves the overall operational stability and reduces the impact of temperature fluctuations on the equipment by precisely controlling the evaporation and heat exchange process of liquid nitrogen, while enhancing the stability and long-term reliability of the entire loop purification system.

[0030] In some embodiments according to the present invention, the high-temperature gas-cooled reactor nuclear power plant loop purification system also includes a helium reflux channel 2, a second heat exchanger 5 and a third heat exchanger 6. The second heat exchanger 5 is arranged between the copper oxide bed 102 and the first heat exchanger 4, and the third heat exchanger 6 is arranged between the molecular sieve bed 103 and the low-temperature adsorber 104. One end of the helium reflux channel 2 is connected to the outlet of the low-temperature adsorber 104, and the helium reflux channel 2 is connected to the third heat exchanger 6 and the second heat exchanger 5 in sequence. The other end is connected to the inlet of the helium blower 10, and heat is exchanged with the helium in the purification operation channel 1 through the third heat exchanger 6 and the second heat exchanger 5.

[0031] Specifically, one end of the helium reflux channel 2 is connected to the outlet of the low-temperature adsorber 104, and the other end is connected to the inlet of the helium blower 10, so that the low-temperature helium gas whose temperature is reduced after the purification process flows back to the helium blower 10, thereby realizing the reuse of the helium gas. At the same time, the helium reflux channel 2 exchanges heat with the purification operation channel 1 through the second heat exchanger 5 and the third heat exchanger 6 to achieve cooling treatment of the high-temperature helium gas in the purification operation channel 1.

[0032] The second heat exchanger 5 is provided between the copper oxide bed 102 and the first heat exchanger 4. The helium is heated to 250°C after passing through the electric heater 101. The copper oxide bed 102 removes impurities such as H2, CO, and O2 from the helium. The purified helium enters the second heat exchanger 5 and undergoes heat exchange with the low-temperature helium in the helium reflux channel 2, reducing its temperature from 250°C to 80°C.

[0033] The third heat exchanger 6 is arranged between the molecular sieve bed 103 and the cryogenic adsorber 104. After the helium in the purified operation channel 1 is heat exchanged in the second heat exchanger 5, it flows through the first heat exchanger 4, and the outlet temperature is reduced to 10°C. The helium then enters the molecular sieve bed 103, which is used to remove H2O and CO2 impurities in the helium. After passing through the molecular sieve bed 103, it enters the third heat exchanger 6, and after heat exchange in the third heat exchanger 6, the outlet temperature is reduced to -165°C. Before flowing into the cryogenic adsorber 104, the temperature is reduced to -190°C. The cryogenic adsorber 104 is used to remove N2, CH4, inert gas impurities and radioactive fission gases Kr and Xe from the helium. The helium flowing out of the outlet of the cryogenic adsorber 104 enters the helium reflux channel 2, flows through the helium reflux channel 2, and serves as a cold source for the second heat exchanger 5 and the third heat exchanger 6. After heat exchange in the second heat exchanger 5 and the third heat exchanger 6, the temperature is increased and it flows back to the helium blower 10.

[0034] In some embodiments of the present invention, a dust filter 106 is provided at the front end of the electric heater 101 along the helium flow direction; and a pipeline filter 107 is provided at the rear end of the copper oxide bed 102 .

[0035] Specifically, a dust filter 106 is provided at the front end of the electric heater 101 to remove solid particles. To prevent the helium flowing through the copper oxide bed 102 from carrying away the copper oxide powder and causing blockage of subsequent channels, a pipeline filter 107 is provided at the rear end of the copper oxide bed 102 to collect the copper oxide powder.

[0036] In some embodiments of the present invention, a three-way valve 304 is provided on the cold return pipe, and the exhaust pipe includes a first exhaust pipe 302 and a second exhaust pipe 303. The first exhaust pipe 302 is connected to the cold return pipe 301 through the first heat exchanger 4, and the second exhaust pipe 303 is connected to the cold return pipe 301 through the three-way valve 304.

[0037] It can be understood that when the nitrogen evaporation amount is too large, in order to avoid the heat exchange efficiency of the first heat exchanger 4 being too high, which causes the temperature of the helium to be lower than the operating temperature of the molecular sieve bed 103, a three-way valve 304 is set on the cold return pipe, and the exhaust pipe includes a first exhaust pipe 302 and a second exhaust pipe 303. The first exhaust pipe 302 is used to discharge the nitrogen flowing through the first heat exchanger 4, and the second exhaust pipe 303 can directly discharge the nitrogen on the cold return pipe. By controlling the three-way valve 304, the heat exchange efficiency is controlled to ensure the normal operation of the system and improve the reliability and safety of the system operation.

[0038] In some embodiments of the present invention, the high-temperature gas-cooled reactor nuclear power plant loop purification system also includes a first bypass pipe 7, one end of the first bypass pipe 7 is connected to the front end of the copper oxide bed 102, and the other end of the first bypass pipe 7 is connected to the rear end of the pipeline filter 107. The first bypass pipe 7 is connected in parallel with the copper oxide bed 102 and the pipeline filter 107 to form a first bypass loop, and a first valve group 701 is provided on the first bypass loop.

[0039] Specifically, first valve assembly 701 includes a first valve body located at the front end of copper oxide bed 102, a second valve body located at the rear end of pipe filter 107, and a third valve body located on first bypass pipe 7. When copper oxide bed 102 needs to be regenerated, the first and second valve bodies are closed and the third valve body is opened, allowing helium to flow through first bypass pipe 7, bypassing copper oxide bed 102 and entering molecular sieve bed 103. First bypass pipe 7 is used to achieve regeneration and recovery of copper oxide bed 102.

[0040] In some embodiments of the present invention, the second heat exchanger 5 is a medium-temperature helium-helium heat exchanger, the first heat exchanger 4 is a nitrogen-helium heat exchanger, and the third heat exchanger 6 is a low-temperature helium-helium heat exchanger.

[0041] Specifically, the first heat exchanger 4 includes a first inner loop flow channel and a first outer loop flow channel, wherein the first inner loop flow channel and the first outer loop flow channel are not connected, the helium flow from the purification operation channel 1 flows through the first outer loop flow channel, and the nitrogen flow from the cold recovery channel 3 flows through the first inner loop flow channel, thereby achieving heat exchange;

[0042] Similarly, the second heat exchanger 5 includes a second inner loop flow channel and a second outer loop flow channel isolated from each other, the helium flow in the purification operation channel 1 flows through the second outer loop flow channel, and the helium flow in the helium return channel 2 flows through the second inner loop flow channel; the third heat exchanger 6 includes a third inner loop flow channel and a third outer loop flow channel isolated from each other, the helium flow in the purification operation channel 1 flows through the third outer loop flow channel, and the helium flow in the helium return channel 2 flows through the third inner loop flow channel.

[0043] In some embodiments of the present invention, the purification operation channel 1 is further provided with a fourth heat exchanger 108 and a gas-water separator 109. The fourth heat exchanger 108 and the gas-water separator 109 are arranged along the helium flow direction and are sequentially arranged between the first heat exchanger 4 and the molecular sieve bed 103. The fourth heat exchanger 108 is a water-helium cooler.

[0044] Specifically, the helium in the purification operation channel 1 passes through the first heat exchanger 4 for heat exchange, and then passes through the fourth heat exchanger 108 to reduce the temperature to 10° C., and then enters the gas-water separator 109 to remove saturated water in the helium.

[0045] In some embodiments of the present invention, the high-temperature gas-cooled reactor nuclear power plant loop purification system also includes a second bypass pipe 8, one end of the second bypass pipe 8 is connected to the front end of the molecular sieve bed 103, and the other end of the second bypass pipe 8 is connected to the rear end of the molecular sieve bed 103. The second bypass pipe 8 and the molecular sieve bed 103 are arranged in parallel to form a second bypass loop, and a second valve group 801 is provided on the second bypass loop.

[0046] Specifically, the second valve group 801 includes a fourth valve body provided at the front end of the molecular sieve bed 103, a fifth valve body provided at the rear end of the molecular sieve bed 103, and a sixth valve body provided on the second bypass pipe 8. When the molecular sieve bed 103 needs to be regenerated, the fourth valve body and the fifth valve body need to be closed, and the sixth valve body needs to be opened, so that helium flows through the second bypass pipe 8 and avoids the molecular sieve bed 103. The second bypass pipe 8 is used for the regeneration and recovery of the molecular sieve bed 103.

[0047] In some embodiments of the present invention, the high temperature gas-cooled reactor nuclear power plant loop purification system further includes a third bypass pipe 9 , one end of which is connected to the molecular sieve bed 103 , and the other end of the third bypass pipe 9 is connected to the helium reflux channel 2 .

[0048] Specifically, one-quarter of the helium flowing out of the molecular sieve bed 103 enters the third heat exchanger 6 for heat exchange, while three-quarters of the flow enters the third bypass pipe 9 and directly enters the helium reflux channel 2. One-quarter of the helium flowing through the cryogenic adsorber 104, after exiting the outlet, passes through the third heat exchanger 6, where its temperature is raised to 3°C. It then merges with the three-quarters of the helium flowing out of the third bypass pipe 9 to reach room temperature. The helium then refluxes through the second heat exchanger 5, where its temperature is raised to 175°C, before returning to the inlet of the helium blower 10 for complete circulation.

[0049] In some embodiments of the present invention, the high-temperature gas-cooled reactor nuclear power plant loop purification system also includes an additional drive unit 11, which is arranged in parallel on the helium reflux channel 2, and the additional drive unit 11 includes a first diaphragm compressor 1101 and a second diaphragm compressor 1102 arranged in parallel.

[0050] Specifically, under normal circumstances, helium is driven by the helium blower 10 to circulate the flow. When the helium blower 10 is not powered enough, the flow circulation can be achieved through an additional driving unit 11. The additional driving unit 11 includes a first diaphragm compressor 1101 and a second diaphragm compressor 1102 arranged in parallel to improve system reliability.

[0051] Although the embodiments of the present invention have been described with reference to the accompanying drawings, those skilled in the art may make various modifications and variations without departing from the spirit and scope of the present invention. Such modifications and variations are all within the scope defined by the appended claims.

Claims

1. A high temperature gas-cooled reactor nuclear power plant circuit purification system, characterized in that: include: A purification operation channel (1), the purification operation channel (1) comprising an electric heater (101), a copper oxide bed (102), a molecular sieve bed (103) and a low-temperature adsorber (104) arranged in sequence and connected through a pipeline along the helium flow direction, the inlet end of the electric heater (101) being connected to the outlet of the helium blower (10), and the low-temperature adsorber (104) being arranged in a liquid nitrogen tank (105); a first heat exchanger (4), the first heat exchanger (4) being disposed between the copper oxide bed (102) and the molecular sieve bed (103); The cold recovery channel (3) comprises a cold return pipe (301) and an exhaust pipe. One end of the cold return pipe (301) is connected to the outlet of the liquid nitrogen tank (105), and the other end is connected to the exhaust pipe. Nitrogen in the liquid nitrogen tank (105) evaporates, passes through the cold return pipe (301), and is heat-exchanged with high-temperature helium after passing through the copper oxide bed (102) in the first heat exchanger (4) before being discharged from the exhaust pipe.

2. The high temperature gas-cooled reactor nuclear power plant loop purification system according to claim 1, characterized in that: The invention also includes a helium reflux channel (2), a second heat exchanger (5) and a third heat exchanger (6), wherein the second heat exchanger (5) is arranged between the copper oxide bed (102) and the first heat exchanger (4), and the third heat exchanger (6) is arranged between the molecular sieve bed (103) and the low-temperature adsorber (104). One end of the helium reflux channel (2) is connected to the outlet of the low-temperature adsorber (104), and the helium reflux channel (2) is connected to the third heat exchanger (6) and the second heat exchanger (5) in sequence, and the other end is connected to the inlet of the helium blower (10), and heat is exchanged with the helium in the purification operation channel (1) through the third heat exchanger (6) and the second heat exchanger (5).

3. The high temperature gas-cooled reactor nuclear power plant loop purification system according to claim 1, characterized in that: Along the helium flow direction, a dust filter (106) is provided at the front end of the electric heater (101); and a pipeline filter (107) is provided at the rear end of the copper oxide bed (102).

4. The high temperature gas-cooled reactor nuclear power plant loop purification system according to claim 3, characterized in that: A three-way valve (304) is provided on the cold return pipe, and the exhaust pipe comprises a first exhaust pipe (302) and a second exhaust pipe (303), wherein the first exhaust pipe (302) is connected to the cold return pipe (301) via the first heat exchanger (4), and the second exhaust pipe (303) is connected to the cold return pipe (301) via the three-way valve (304).

5. The high temperature gas-cooled reactor nuclear power plant loop purification system according to claim 4, characterized in that: The invention also includes a first bypass pipe (7), one end of which is in communication with the front end of the copper oxide bed (102), and the other end of which is in communication with the rear end of the pipeline filter (107). The first bypass pipe (7) is connected in parallel with the copper oxide bed (102) and the pipeline filter (107) to form a first bypass loop. A first valve group (701) is provided on the first bypass loop.

6. The high temperature gas-cooled reactor nuclear power plant loop purification system according to claim 2, characterized in that: The second heat exchanger (5) is a medium-temperature helium-helium heat exchanger, the first heat exchanger (4) is a nitrogen-helium heat exchanger, and the third heat exchanger (6) is a low-temperature helium-helium heat exchanger.

7. The high temperature gas-cooled reactor nuclear power plant loop purification system according to claim 1, characterized in that: The purification operation channel (1) is further provided with a fourth heat exchanger (108) and a gas-water separator (109). The fourth heat exchanger (108) and the gas-water separator (109) are arranged along the helium flow direction and in sequence between the first heat exchanger (4) and the molecular sieve bed (103). The fourth heat exchanger (108) is a water-helium cooler.

8. The high temperature gas-cooled reactor nuclear power plant loop purification system according to claim 1, characterized in that: The device further comprises a second bypass pipe (8), one end of which is in communication with the front end of the molecular sieve bed (103), and the other end of which is in communication with the rear end of the molecular sieve bed (103). The second bypass pipe (8) and the molecular sieve bed (103) are arranged in parallel to form a second bypass loop, and a second valve group (801) is provided on the second bypass loop.

9. The high temperature gas-cooled reactor nuclear power plant loop purification system according to claim 2, characterized in that: It also includes a third bypass pipe (9), one end of which is in communication with the molecular sieve bed (103), and the other end of which is in communication with the helium reflux channel (2).

10. The high temperature gas-cooled reactor nuclear power plant loop purification system according to claim 2, characterized in that: The invention also includes an additional driving unit (11), wherein the additional driving unit (11) is arranged in parallel on the helium reflux channel (2), and the additional driving unit (11) includes a first diaphragm compressor (1101) and a second diaphragm compressor (1102) arranged in parallel.

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