Anti-freezing device, anti-freezing system and operation method of waste heat removal system of high-temperature gas cooled reactor

Abstract

The invention discloses an anti-freezing device, an anti-freezing system and an operation method for a waste heat removal system of a high-temperature gas cooled reactor, and the anti-freezing device comprises a cooling pool which is filled with a first cooling medium and is suitable for accommodating a heat exchanger and exchanging heat with the heat exchanger; the cooling pond temperature adjusting mechanism is connected with the nuclear island equipment cooling system, a second cooling medium is supplied by the nuclear island equipment cooling system, the cooling pond temperature adjusting mechanism is provided with a heat exchange end, and the heat exchange end extends into the cooling pond and exchanges heat with the cooling pond, so that the first cooling medium in the cooling pond is maintained at the set temperature. According to the invention, winter freezing prevention of the passive residual heat removal system of the high-temperature gas cooled reactor can be realized. And the cooling capacity of the system can be adjusted within a certain flow range, and the power maintenance of the reactor under the low-power operation condition is assisted.

Description

Technical Field

[0001] The present invention relates to the technical field of nuclear reactors, and particularly relates to an anti-freezing device, an anti-freezing system and an operation method for the residual heat removal system of a high-temperature gas-cooled reactor. Background Art

[0002] A passive residual heat removal system is provided in the high-temperature gas-cooled reactor. After the reactor shuts down, the temperature of the pressure vessel and the compartment is reduced through the operation of this system to achieve the cooling of the primary loop. This system belongs to the accident post-defense system. During the low-power operation condition or the shutdown process of the reactor, the heat carried by the system is relatively low, and since the heat exchanger of this system is arranged outdoors, the average temperature of the environment where the power station is located is relatively low in winter conditions and may be below zero for a long time. In such a condition, the outdoor heat exchanger may crack. If a system leak occurs and the internal water volume is insufficient, the natural circulation of the system will be interrupted, the residual heat removal function will be lost, and the power station will lose part of its defense function in depth, reducing the accident mitigation ability of the power station. Summary of the Invention

[0003] In view of this, the present invention provides an anti-freezing device, an anti-freezing system and an operation method for the residual heat removal system of a high-temperature gas-cooled reactor to solve the problem of the heat exchanger in the passive residual heat removal system of the high-temperature gas-cooled reactor cracking in winter.

[0004] In a first aspect, the present invention provides an anti-freezing device for the residual heat removal system of a high-temperature gas-cooled reactor, comprising:

[0005] A cooling pool, which is filled with a first cooling medium inside, and the cooling pool is adapted to accommodate the heat exchanger and exchange heat with the heat exchanger;

[0006] A cooling pool temperature regulating mechanism, which is connected to the nuclear island equipment cooling system and supplied with a second cooling medium by the nuclear island equipment cooling system. The cooling pool temperature regulating mechanism has a heat exchange end, and the heat exchange end extends into the cooling pool to exchange heat with the cooling pool so as to maintain the first cooling medium in the cooling pool at a set temperature.

[0007] The beneficial effects of the above anti-freezing device for the residual heat removal system of a high-temperature gas-cooled reactor are as follows: It can achieve winter anti-freezing for the passive residual heat removal system of the high-temperature gas-cooled reactor. And the cooling capacity of the system can be adjusted within a certain flow range to assist in maintaining the power during the low-power operation of the reactor.

[0008] When the cooling pool temperature regulating mechanism exchanges heat with the cooling pool, it can control the temperature of the first cooling medium in the cooling pool, and then control the temperature of the third medium in the heat exchanger. Therefore, even in cold winter, it can ensure that the passive residual heat removal system of the high-temperature gas-cooled reactor does not suffer from freezing damage, ensure the normal operation of the residual heat removal system, effectively extend the service life of the heat exchanger, and reduce the maintenance cost and downtime.

[0009] When the residual heat removal system is a passive residual heat removal system, the cooling pool temperature regulating mechanism is connected to the nuclear island equipment cooling system to continuously supply the second cooling medium, ensuring the normal operation of the natural circulation of the passive residual heat removal system, avoiding the loss of the residual heat removal function caused by system leakage or interruption of natural circulation, thereby enhancing the accident mitigation ability of the power station and further ensuring the safety of the nuclear power plant.

[0010] Whether in the low-power operation condition of the reactor or during the shutdown process, this anti-freezing device can work effectively and adapt to different operating states. Even in a harsh environment with sub-zero temperature for a long time, it can maintain the normal operation of the system through the cooling pool temperature regulating mechanism, improving the environmental adaptability of the system.

[0011] The above-mentioned anti-freezing device for the residual heat removal system of the high-temperature gas-cooled reactor uses water as the heat transfer medium of the heat exchanger, which has higher heat transfer efficiency and more stable heat transfer compared with air.

[0012] The above-mentioned anti-freezing device for the residual heat removal system of the high-temperature gas-cooled reactor has a simple composition, reliable operation, and does not require additional maintenance, and can ensure the reliable operation of the residual heat removal system at low cost.

[0013] In an alternative embodiment, the cooling pool temperature regulating mechanism includes:

[0014] A second cooling medium input pipe, connected to the output port of the nuclear island equipment cooling system;

[0015] A second cooling medium output pipe, connected to the input port of the nuclear island equipment cooling system;

[0016] At least one heat exchange coil, one end of which is connected to the second cooling medium input pipe and the other end is connected to the second cooling medium output pipe, and at least a part of the heat exchange coil is disposed in the cooling pool.

[0017] In an alternative embodiment, a first electric control valve is provided on the second cooling medium input pipe; and / or, a second electric control valve is provided on the second cooling medium output pipe.

[0018] In an alternative embodiment, the set temperature is 25 - 40 °C.

[0019] In an alternative embodiment, the cooling pool is connected to a supply tank through a supply pipe, and a supply pump is provided on the supply pipe, and the supply pump is adapted to supply the first medium in the supply tank to the cooling pool.

[0020] In a second aspect, the present invention provides a high-temperature gas-cooled reactor anti-freezing system, including:

[0021] The above-mentioned anti-freezing device for the residual heat removal system of the high-temperature gas-cooled reactor;

[0022] The passive residual heat removal system includes heat exchange tubes and a heat exchanger. The heat exchange tubes are arranged on the inner wall of the reactor compartment and exchange heat with the reactor. The heat exchanger is placed in the cooling pool of the anti-freezing device for the residual heat removal system of the high-temperature gas-cooled reactor. The arrangement position of the heat exchanger is higher than that of the heat exchange tubes. The heat exchanger is connected to the heat exchange tubes through system pipelines to form a closed medium flow path, and a third medium is filled in the closed medium flow path.

[0023] In an optional implementation manner, the system pipelines include a horizontal annular water inlet main pipe and a horizontal annular water return main pipe. The heat exchange tubes are divided into multiple vertical straight pipe section cooling tubes, and the third medium output by the heat exchanger is evenly distributed to each vertical straight pipe section cooling tube through the horizontal annular water inlet main pipe.

[0024] In a third aspect, the present invention provides an operation method for an anti-freezing system of a high-temperature gas-cooled reactor. The method is based on the anti-freezing system of the high-temperature gas-cooled reactor and includes the following steps:

[0025] Under the reactor power operation or shutdown state, by adjusting the flow rate of the second cooling medium supplied by the nuclear island equipment cooling system, the temperature of the first cooling medium inside the cooling pool is regulated, and at the same time, the heat transfer power of the passive residual heat removal system is changed.

[0026] When the reactor is operating at high power, the radiation heat dissipation power of the reactor core increases. At this time, the flow rate of the second cooling medium of the nuclear island equipment cooling system is increased to increase the heat exchange power and maintain the temperature of the first cooling medium in the cooling pool within the first threshold.

[0027] When the reactor is operating at low power or in a shutdown state, the nuclear island equipment cooling system continuously supplies the second cooling medium at the lowest flow rate, and ensures that the heat dissipation power of the cooling pool ≤ the heating power of the nuclear island equipment cooling system under winter conditions, so that the temperature of the first cooling medium in the cooling pool is maintained within the second threshold.

[0028] In an optional implementation manner, when the reactor needs to be maintained at a low power level, it is achieved through the following steps:

[0029] The reactor power is reduced to the lowest level through the inherent reactivity control means of the reactor; at the same time, the flow rate of the second cooling medium of the nuclear island equipment cooling system is appropriately increased to increase the cooling power, reversely limit the further decrease of the cooling power, and inhibit the accumulation of xenon poison; the cooling power of the passive residual heat removal system is monitored and adjusted in real time to maintain the reactor power within the set power range for inhibiting the accumulation of xenon poison.

[0030] In an optional implementation manner, the capacity design of the passive residual heat removal system satisfies: the capacity of the passive residual heat removal system ≥ the lowest power level of the inherent reactivity control means of the reactor.

[0031] The beneficial effects of the operation method of the above-mentioned high-temperature gas-cooled reactor anti-freezing system are as follows: By combining passive and active methods, the system can adjust the cooling capacity within a certain capacity range of the residual heat removal system. It can maintain the reactor power under low-power conditions of the high-temperature reactor. BRIEF DESCRIPTION OF THE DRAWINGS

[0032] In order to more clearly illustrate the specific embodiments of the present invention or the technical solutions in the prior art, the following will briefly introduce the drawings required for the description of the specific embodiments or the prior art. Obviously, the drawings in the following description are some embodiments of the present invention. For those of ordinary skill in the art, without creative efforts, other drawings can also be obtained based on these drawings.

[0033] Figure 1 It is a schematic structural diagram of an anti-freezing device for a residual heat removal system of a high-temperature gas-cooled reactor provided by the present invention.

[0034] Description of the reference numerals:

[0035] 1. Reactor, 2. Heat exchange tube, 3. System pipeline, 4. Heat exchanger, 5. Cooling pool, 6. Heat exchange coil, 7. First electric control valve, 8. Second electric control valve, 9. Nuclear island equipment cooling system, 10. Supply tank, 11. Supply pump, 12. Second cooling medium input pipe, 13. Second cooling medium output pipe. DETAILED DESCRIPTION OF THE EMBODIMENTS

[0036] To make the objectives, technical solutions, and advantages of the embodiments of the present invention clearer, the following will clearly and completely describe the technical solutions in the embodiments of the present invention with reference to the accompanying drawings in the embodiments of the present invention. Obviously, the described embodiments are some, but not all, of the embodiments of the present invention. Based on the embodiments of the present invention, all other embodiments obtained by those of ordinary skill in the art without creative efforts belong to the scope of protection of the present invention.

[0037] The following will elaborate on the specific embodiments of the present invention in detail in combination with the anti-freezing device for the residual heat removal system of the high-temperature gas-cooled reactor in the first aspect of the present invention, the anti-freezing system of the high-temperature gas-cooled reactor in the second aspect of the present invention, and the operation method of the anti-freezing system of the high-temperature gas-cooled reactor in the third aspect of the present invention.

[0038] According to an embodiment of the present invention, in the first aspect, an anti-freezing device for a residual heat removal system of a high-temperature gas-cooled reactor is provided. Combining Figure 1As shown in the figure, it includes a cooling pool 5 and a cooling pool temperature regulating mechanism. The interior of the cooling pool 5 is filled with a first cooling medium. The cooling pool 5 is adapted to accommodate the heat exchanger 4 and exchange heat with the heat exchanger 4. The cooling pool temperature regulating mechanism is connected to the nuclear island equipment cooling system 9 and supplied with a second cooling medium by the nuclear island equipment cooling system 9. The cooling pool temperature regulating mechanism has a heat exchange end, and the heat exchange end extends into the cooling pool 5 and exchanges heat with the cooling pool 5 to maintain the first cooling medium in the cooling pool 5 at a set temperature. Among them, the set temperature can be 25 - 40 °C, or it can be other temperatures. Here, the specific temperature range of the set temperature is not restricted. The first medium is demineralized water, and the second medium is water.

[0039] For the above-mentioned anti-freezing device of the high-temperature gas-cooled reactor residual heat removal system, when the cooling pool temperature regulating mechanism exchanges heat with the cooling pool 5, it can control the temperature of the first cooling medium in the cooling pool 5, and then control the temperature of the third medium in the heat exchanger 4. Thus, even in the cold winter, it can ensure that the passive residual heat removal system of the high-temperature gas-cooled reactor does not suffer from freeze cracking damage, ensure the normal operation of the residual heat removal system, effectively extend the service life of the heat exchanger, and reduce the maintenance cost and downtime.

[0040] When the residual heat removal system is a passive residual heat removal system, the cooling pool temperature regulating mechanism is connected to the nuclear island equipment cooling system 9 to continuously supply the second cooling medium, ensuring the normal operation of the natural circulation of the passive residual heat removal system, and avoiding the loss of the residual heat removal function caused by system leakage or interruption of natural circulation, thereby enhancing the accident mitigation ability of the power station and further ensuring the safety of the nuclear power plant.

[0041] Whether it is the low-power operation condition of the reactor or the shutdown process, this anti-freezing device can work effectively and adapt to different operating states. Even in a harsh environment with sub-zero temperature for a long time, it can maintain the normal operation of the system through the cooling pool temperature regulating mechanism, improving the environmental adaptability of the system.

[0042] In some embodiments, the cooling pool temperature regulating mechanism includes a second cooling medium input pipe 12, a second cooling medium output pipe 13, and a heat exchange coil 6. The second cooling medium input pipe 12 is connected to the output port of the nuclear island equipment cooling system 9. The second cooling medium output pipe 13 is connected to the input port of the nuclear island equipment cooling system 9. At least one heat exchange coil 6 is provided. One end of the heat exchange coil 6 is connected to the second cooling medium input pipe 12, and the other end of the heat exchange coil 6 is connected to the second cooling medium output pipe 13. The heat exchange coil 6 is at least partially disposed in the cooling pool 5.

[0043] The nuclear island equipment cooling system 9 transports the second cooling medium to the heat exchange coil 6 through the second cooling medium input pipe 12, enabling the heat exchange coil 6 to exchange heat with the first medium in the cooling pool 5. The second cooling medium after heat exchange is sent back to the nuclear island equipment cooling system 9 through the second cooling medium output pipe 13, and thus continuous heat exchange between the nuclear island equipment cooling system 9 and the cooling pool 5 can be achieved. When the temperature of the first medium in the cooling pool 5 is relatively high, the second medium in the heat exchange coil 6 can absorb heat in a timely manner, enabling the heat exchanger 4 in the residual heat removal system to quickly cool down, thereby avoiding the accumulation of reactor heat. When the temperature of the first medium in the cooling pool 5 is lower than the temperature of the second medium, the second medium in the heat exchange coil 6 can release heat in a timely manner, enabling the heat exchanger 4 in the residual heat removal system to warm up, thereby avoiding the third medium in the heat exchanger 4 from freezing due to too low temperature.

[0044] Among them, the number of heat exchange coils 6 can be set according to the actual working conditions. When the number of heat exchange coils 6 is large and the heat exchange area with the first medium in the cooling pool 5 is large, the heat exchange effect can be improved.

[0045] In some embodiments, a first electric control valve 7 is provided on the second cooling medium input pipe 12. A second electric control valve 8 is provided on the second cooling medium output pipe 13. In this embodiment, the flow rate of the second medium input into the heat exchange coil 6 can be regulated by controlling the opening degrees of the first electric control valve 7 and the second electric control valve 8, thereby achieving the control of the temperature of the first medium in the cooling pool 5 and maintaining the internal temperature of the cooling pool 5 at 25 - 40 °C.

[0046] In some embodiments, the cooling pool 5 is connected to a supply tank 10 through a supply pipe, and a supply pump 11 is provided on the supply pipe. The supply pump 11 is adapted to supply the first medium in the supply tank 10 to the cooling pool 5. This supply pump 11 fills water from the supply tank 10 to the cooling pool 5 before the system starts and replenishes the evaporated water volume during normal operation.

[0047] The high-temperature gas-cooled reactor anti-freezing system further includes a control system. The control system is electrically connected to the first electric control valve 7, the second electric control valve 8, and the supply pump 11, and is used to automatically adjust the opening degrees of the first electric control valve 7 and the second electric control valve 8 according to the temperature of the first medium in the cooling pool 5 and the operating state of the reactor 1, and control the opening and closing of the supply pump 11, thereby achieving precise control of the entire anti-freezing system and ensuring the stable operation of the system.

[0048] In some embodiments, the cooling pool 5 is in a closed state during the operation of the unit to prevent foreign impurities from entering and affecting the cooling effect. At the same time, the closed state can also effectively reduce heat dissipation and improve the thermal efficiency of the entire residual heat removal system.

[0049] According to an embodiment of the present invention, in a second aspect, a high-temperature gas-cooled reactor anti-freezing system is provided, including an anti-freezing device for the residual heat removal system of the high-temperature gas-cooled reactor and a passive residual heat removal system.

[0050] The passive residual heat removal system includes a heat exchange tube 2 and a heat exchanger 4. The heat exchange tube 2 is arranged on the inner wall of the reactor 1 compartment and is adapted to absorb the heat dissipated by the reactor 1. The heat exchanger 4 is accommodated in the cooling pool 5 of the anti-freezing device for the residual heat removal system of the high-temperature gas-cooled reactor. The arrangement position of the heat exchanger 4 is higher than that of the heat exchange tube 2. More specifically, the cooling pool 5 is arranged inside an outdoor structure on the top of the reactor building. The heat exchanger 4 is connected to the heat exchange tube 2 through a system pipeline 3 to form a closed medium flow path. The closed medium flow path is filled with a third medium, and the third medium can be demineralized water.

[0051] The closed medium flow path formed by the heat exchange tube 2 and the system pipeline 3 does not allow a loop arrangement to prevent poor natural circulation.

[0052] The system pipeline 3 includes a horizontal annular inlet header and a horizontal annular return header. The shape of the heat exchange tube 2 can be annular or other shapes. The heat exchange tube 2 is vertically arranged and is divided into multiple vertical straight pipe section cooling tubes. The third medium output by the heat exchanger 4 is evenly distributed to each vertical straight pipe section cooling tube through the horizontal annular inlet header, and then returns to the heat exchanger 4 through the horizontally arranged annular return header. This design ensures the uniform flow of the third medium in the heat exchange tube 2 and improves the heat exchange efficiency. At the same time, the setting of multiple vertical straight pipe section cooling tubes enables the heat to be more evenly distributed on the inner wall of the reactor compartment, improving the heat absorption efficiency.

[0053] According to an embodiment of the present invention, in a third aspect, a method for operating a high-temperature gas-cooled reactor anti-freezing system is provided. The method is based on the high-temperature gas-cooled reactor anti-freezing system and includes the following steps:

[0054] Under the condition of reactor power operation or shutdown, by adjusting the flow rate of the second cooling medium supplied by the nuclear island equipment cooling system 9, the temperature of the first cooling medium inside the cooling pool 5 is regulated, and at the same time, the heat transfer power of the passive residual heat removal system is changed. By adjusting the flow rate of the second cooling medium supplied by the nuclear island equipment cooling system 9, the heat transfer power of the passive residual heat removal system can be dynamically changed to meet the requirements of the reactor under different power operation states. Whether the reactor is in a high-power, low-power or shutdown state, the system can automatically adjust to maintain stable operation, ensuring the efficiency and safety of the heat exchange process.

[0055] When the reactor is operating at high power, the core radiation heat dissipation power increases. In order to dissipate the heat generated by the reactor as soon as possible, at this time, the flow rate of the second cooling medium of the nuclear island equipment cooling system 9 is increased to increase the heat transfer power, maintain the temperature of the first cooling medium in the cooling pool 5 within the first threshold, and improve the heat discharge per unit time of the passive residual heat removal system. In the high-power operation state, ensure that the system can respond quickly and efficiently handle the excess heat, avoid overheating, and make full use of the resources of the nuclear island equipment cooling system.

[0056] When the reactor is operating at low power or in a shutdown state, the heat generation of the reactor decreases, and the nuclear island equipment cooling system 9 continuously supplies the second cooling medium at the minimum flow rate. Since the water temperature of the nuclear island equipment cooling system is maintained at 20 - 40°C, the water temperature of the cooling pool 5 can be maintained ≥ 20°C (the anti-freezing lower limit).

[0057] It should be noted that: the minimum cold water flow rate of the nuclear island equipment cooling system needs to be actually calculated according to the volume and heat dissipation area of the cooling pool 5 to ensure that the heat dissipation power of the cooling pool 5 ≤ the heating power of the nuclear island equipment cooling system under winter conditions, so as to ensure that the internal temperature of the cooling pool 5 is maintained within the second threshold and in a relatively constant state, ensure that the heating input by the cooling water to the cooling pool 5 is sufficient to offset the environmental heat dissipation, avoid freezing of the heat exchanger due to low temperature, and improve the reliability and service life of the system.

[0058] In this embodiment, regardless of the operating state of the reactor, this method can ensure the normal operation of the passive residual heat removal system, avoid the loss of the residual heat removal function caused by the interruption of natural circulation, further improve the accident mitigation ability of the nuclear power plant, enhance the overall safety performance, and provide an important guarantee for the long-term stable operation of the nuclear power plant. And make full use of the resources of the nuclear island equipment cooling system 9, reduce additional energy consumption, and avoid potential environmental pollution problems caused by equipment damage or leakage.

[0059] In some embodiments, when the reactor 1 needs to be maintained at a lower power level, in cooperation with the in-core reactivity control means, the heat discharge of the reactor can be achieved by this method, and the reactor can be maintained at a certain power level. It is specifically achieved through the following steps:

[0060] Try to reduce the reactor power to the lowest level through the inherent reactivity control means of the reactor. The inherent reactivity control means of the reactor are traditional power control means, such as inserting control rods and reducing the rotational speed of the main helium blower, suppressing the core chain reaction, and reducing the power to the xenon poison safety threshold. The lowest level of the reactor power is mainly determined according to the xenon poison accumulation level calculated under the power operation level to prevent the reactor from shutting down due to xenon poison accumulation during power change.

[0061] If the power is too low, the accumulation of xenon poisoning may lead to a sudden drop in reactivity and trigger an unscheduled reactor shutdown. It is necessary to select the dynamic equilibrium point so that the power level can avoid the out-of-control of xenon poisoning and maintain long-term stability. Therefore, while reducing the reactor power level, appropriately increase the flow rate of the second cooling medium of the nuclear island equipment cooling system 9 to increase the cooling power, improve the residual heat removal capacity, reverse the further decrease of the cooling power, and inhibit the accumulation of xenon poisoning.

[0062] Real-time monitor and adjust the cooling power of the passive residual heat removal system to maintain the reactor power at the highest possible operating level, maintain the reactor power within the set power range that inhibits the accumulation of xenon poisoning, prevent the accumulation of xenon poisoning when the power decreases, further ensure the stability of the reactor power operation, ensure that the reactor power is maintained at a relatively high level of "resistant to xenon poisoning fluctuations", and avoid falling into the vicious cycle of "low power - xenon poisoning accumulation - reactor shutdown".

[0063] The capacity design of the passive residual heat removal system meets the requirement: passive residual heat removal system capacity ≥ the lowest power level of traditional power control means. Ensure that even when the reactor reduces to the lowest theoretical power through means such as control rods and fan speed regulation, by adjusting the flow rate of the nuclear island equipment cooling system 9, the residual heat can still be effectively removed, preventing the core residual heat from accumulating and causing temperature out-of-control.

[0064] The above operation method of the high-temperature gas-cooled reactor anti-freezing system can achieve adjustable cooling capacity within a certain capacity range of the residual heat removal system through a combination of passive and active methods. It can maintain the reactor power under the low-power condition of the high-temperature reactor.

[0065] Although the embodiments of the present invention have been described in conjunction with the accompanying drawings, those skilled in the art can make various modifications and variations without departing from the spirit and scope of the present invention, and such modifications and variations all fall within the scope defined by the appended claims.

Claims

1. The anti-freezing device for the residual heat removal system of a high-temperature gas-cooled reactor, characterized in that, Comprising: A cooling pool (5) filled with a first cooling medium inside, the cooling pool (5) being adapted to accommodate a heat exchanger (4) and perform heat exchange with the heat exchanger (4); A cooling pool temperature regulating mechanism, connected to the nuclear island equipment cooling system (9) and supplied with a second cooling medium by the nuclear island equipment cooling system (9), the cooling pool temperature regulating mechanism having a heat exchange end, the heat exchange end extending into the cooling pool (5) and performing heat exchange with the cooling pool (5) so as to maintain the first cooling medium in the cooling pool (5) at a set temperature.

2. The anti-freezing device for the residual heat removal system of the high-temperature gas-cooled reactor according to claim 1, wherein The cooling pool temperature regulating mechanism includes: A second cooling medium input pipe (12), connected to the output port of the nuclear island equipment cooling system (9); A second cooling medium output pipe (13), connected to the input port of the nuclear island equipment cooling system (9); At least one heat exchange coil (6), one end connected to the second cooling medium input pipe (12) and the other end connected to the second cooling medium output pipe (13), the heat exchange coil (6) being at least partially disposed in the cooling pool (5).

3. The anti-freezing device for the residual heat removal system of the high-temperature gas-cooled reactor according to claim 2, characterized in that, A first electric control valve (7) is provided on the second cooling medium input pipe (12); and / or, a second electric control valve (8) is provided on the second cooling medium output pipe (13).

4. The anti-freezing device for the residual heat removal system of a high-temperature gas-cooled reactor according to claim 1, wherein The set temperature is 25 - 40 °C.

5. The anti-freezing device for the residual heat removal system of the high-temperature gas-cooled reactor according to claim 1, wherein The cooling pool (5) is connected to a supply tank (10) through a supply pipe, a supply pump (11) is provided on the supply pipe, and the supply pump (11) is adapted to supply the first medium in the supply tank (10) to the cooling pool (5).

6. High-temperature gas-cooled reactor anti-freezing system, characterized in that, Comprising: An anti-freezing device for the residual heat removal system of a high-temperature gas-cooled reactor according to any one of claims 1 - 5; A passive residual heat removal system, including heat exchange tubes (2) and a heat exchanger (4), the heat exchange tubes (2) being arranged on the inner wall of the reactor (1) compartment and performing heat exchange with the reactor (1), the heat exchanger (4) being accommodated in the cooling pool (5) of the anti-freezing device for the high-temperature gas-cooled reactor residual heat removal system, the arrangement position of the heat exchanger (4) being higher than the arrangement position of the heat exchange tubes (2), and the heat exchanger (4) being connected to the heat exchange tubes (2) through a system pipeline (3) to form a closed medium flow path, and a third medium being filled in the closed medium flow path.

7. The high-temperature gas-cooled reactor anti-freezing system according to claim 6, characterized in that, The system pipeline (3) includes a horizontal annular water inlet main pipe and a horizontal annular water return main pipe, the heat exchange tubes (2) are divided into a plurality of vertical straight pipe section cooling tubes, and the third medium output by the heat exchanger (4) is evenly distributed to each vertical straight pipe section cooling tube through the horizontal annular water inlet main pipe.

8. Operating method of the high-temperature gas-cooled reactor anti-freezing system, characterized in that, The method is carried out based on the high-temperature gas-cooled reactor anti-freezing system according to claim 6 or 7, and includes the following steps: During the reactor power operation or shutdown state, by adjusting the flow rate of the second cooling medium supplied by the nuclear island equipment cooling system (9), the temperature of the first cooling medium inside the cooling pool (5) is regulated, and at the same time, the heat transfer power of the passive residual heat removal system is changed; When the reactor is operating at high power, the core radiation heat dissipation power increases. At this time, the flow rate of the second cooling medium of the nuclear island equipment cooling system (9) is increased to increase the heat exchange power and maintain the temperature of the first cooling medium in the cooling pool (5) within the first threshold. When the reactor is operating at low power or in a shutdown state, the nuclear island equipment cooling system (9) continuously supplies the second cooling medium at the minimum flow rate, and ensures that the heat dissipation power of the cooling pool ≤ the heating power of the nuclear island equipment cooling system under winter conditions, so as to maintain the temperature of the first cooling medium in the cooling pool (5) within the second threshold value.

9. The operation method of the high-temperature gas-cooled reactor anti-freezing system according to claim 8, characterized in that, When the reactor (1) needs to be maintained at a low power level, it is achieved through the following steps: Reduce the reactor power to the lowest level through the inherent reactivity control means of the reactor; at the same time, appropriately increase the flow rate of the second cooling medium of the nuclear island equipment cooling system (9) to increase the cooling power and inhibit the accumulation of xenon poison; continuously monitor and adjust the cooling power of the passive residual heat removal system to maintain the reactor power within the set power range for inhibiting the accumulation of xenon poison.

10. The operating method of the high-temperature gas-cooled reactor anti-freezing system according to claim 9, characterized in that, The capacity design of the passive residual heat removal system meets the requirement that the capacity of the passive residual heat removal system ≥ the lowest power level of the inherent reactivity control means of the reactor.

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