High-temperature Reactor Main Steam Pressure Control System and Method

Abstract

Embodiments of the present disclosure provide a high-temperature reactor main steam pressure control system and method, including a first reactor group, a steam turbine, a condenser, a main steam pipeline, and a feed water pipeline. The first reactor group includes a first reactor, a first steam generator, and a first atmospheric relief valve serially arranged in the main steam pipeline, which are interconnected. The system further includes a first quick-opening bypass pipeline with a first quick-opening bypass valve serially arranged therein and a first regulating bypass pipeline with a first regulating bypass valve serially arranged therein. The first quick-opening bypass pipeline and the first regulating bypass pipeline are respectively connected to the main steam pipeline and the condenser; wherein, in the case of a transient fault in the system, the first quick-opening bypass valve, the first regulating bypass valve, and the first atmospheric relief valve are opened so that the helium-water flow rate ratio is maintained within a preset range. It is possible to quickly and stably control the main steam pressure under transient conditions, ensure the stability of the main feed water flow rate, and avoid the shutdown of the reactor due to the helium-water flow rate ratio protection in the primary and secondary circuits.

Description

Technical Field

[0001] Embodiments of the present disclosure belong to the technical field of main steam pressure control, and particularly relate to a main steam pressure control system and method for a high-temperature reactor. Background Art

[0002] The steam generator of a nuclear power plant transfers the heat of the primary loop to the feed water of the secondary loop, and the feed water turns into steam to drive the steam turbine to do work. When load rejection or a shutdown transient occurs, the reactor power is much greater than the steam turbine power, and the main steam pressure will rapidly rise significantly. The main steam pressure control system is required to adjust and protect it, otherwise the safety of the unit will be endangered.

[0003] During the normal operation of a high-temperature reactor, the main steam pressure needs to be controlled constantly. However, the dynamic response of the reactor is slow during operation, and it is difficult to control the main steam pressure when a steam turbine generator or the power grid fails. Summary of the Invention

[0004] Embodiments of the present disclosure aim to at least solve one of the technical problems existing in the prior art, and provide a main steam pressure control system and method for a high-temperature reactor.

[0005] In one aspect of the embodiments of the present disclosure, a main steam pressure control system for a high-temperature reactor is provided, including a first reactor group, a steam turbine, a condenser, a main steam pipeline, and a feed water pipeline. The first reactor group includes a first reactor and a first steam generator that are connected to each other. The first steam generator is connected to the steam turbine through the main steam pipeline. The steam turbine is connected to the condenser, and the condenser is connected to the first steam generator through the feed water pipeline. The first reactor group further includes a first atmospheric relief valve serially arranged in the main steam pipeline. The system further includes a first bypass pipeline group, and the first bypass pipeline group includes a first quick-opening bypass pipeline with a first quick-opening bypass valve serially arranged therein and a first regulating bypass pipeline with a first regulating bypass valve serially arranged therein. The first quick-opening bypass pipeline and the first regulating bypass pipeline are respectively connected to the main steam pipeline and the condenser; wherein,

[0006] When a transient fault occurs in the system, the first quick-opening bypass valve, the first regulating bypass valve, and the first atmospheric relief valve are opened to maintain the helium water flow ratio within a preset range.

[0007] Optionally, desuperheating water valves are serially connected to the first quick-opening bypass pipeline, the first regulating bypass pipeline, and the condenser.

[0008] Optionally, the first reactor group further includes a first safety valve;

[0009] The first safety valve is serially arranged in the main steam pipeline and is located between the first steam generator and the first atmospheric relief valve.

[0010] Optionally, the first reactor group further includes a first electric isolation valve connected in series to the first atmospheric relief valve.

[0011] Optionally, the discharge capacities of the first safety valve and the first atmospheric relief valve are the single full power flow rate, and the receiving capacity of the condenser is greater than the single full power flow rate.

[0012] Optionally, the first atmospheric relief valve is set as a pilot-operated safety valve;

[0013] The set value of the pilot-operated safety valve is lower than the set value of the first safety valve.

[0014] Optionally, the first reactor group further includes a first pressure gauge and a first main steam isolation valve, and the first bypass pipeline group further includes a first bypass isolation valve;

[0015] The first pressure gauge is connected in series in the main steam pipeline and is close to the first steam generator, the first main steam isolation valve is connected in series in the main steam pipeline, and the first bypass isolation valve is connected in series in the first bypass pipeline group.

[0016] Optionally, the system further includes a second reactor group and a secondary steam pipeline;

[0017] The second reactor group includes a second reactor and a second steam generator that are interconnected, and the second steam generator is connected to the main steam pipeline through the secondary steam pipeline;

[0018] The second reactor group further includes a second pressure gauge, a second safety valve, a second atmospheric relief valve, and a second main steam isolation valve that are connected in series in sequence in the secondary steam pipeline; among them,

[0019] A second electric isolation valve is connected in series to the second atmospheric relief valve.

[0020] Optionally, the system further includes a second bypass pipeline group and a second bypass isolation valve connected in series in the second bypass pipeline group;

[0021] The second bypass pipeline group includes a second quick-opening bypass pipeline with a second quick-opening bypass valve connected in series and a second regulating bypass pipeline with a second regulating bypass valve connected in series. The second quick-opening bypass pipeline and the second regulating bypass pipeline are respectively connected to the main steam pipeline and the condenser, and the second quick-opening bypass pipeline and the second regulating bypass pipeline are also respectively connected in series with a desuperheating water valve.

[0022] Another aspect of the embodiments of the present disclosure provides a high-temperature reactor main steam pressure control method, which uses the system described above, and the method includes:

[0023] At the initial stage of the system transient fault, the quick-opening bypass valve opens, and the atmospheric relief valve makes multiple trips to ensure that the secondary circuit does not lose flow.

[0024] At the middle stage of the system transient fault, the quick-opening bypass valve is fully opened, the regulating bypass valve is partially opened, and the number of trips of the atmospheric relief valve is reduced.

[0025] At the late stage of the system transient fault, the quick-opening bypass valve remains open, the regulating bypass valve is opened to an appropriate opening degree, and the atmospheric relief valve no longer trips.

[0026] The high-temperature reactor main steam pressure control system and method according to the embodiments of the present disclosure can quickly and stably control the main steam pressure under transient conditions through the provided atmospheric relief valve, the quick-opening bypass pipeline with a quick-opening bypass valve in series, and the regulating bypass pipeline with a regulating bypass valve in series, ensure the stability of the main feed water flow, and avoid the reactor trip due to the helium water flow ratio protection between the primary and secondary circuits; at the same time, reduce the response of the reactor measurement, ensure the stable operation of the unit, and the reactor group can not reduce power during the whole process of the system transient fault. Brief Description of the Drawings

[0027] Figure 1 It is a schematic structural diagram of a high-temperature reactor main steam pressure control system according to an embodiment of the present disclosure. Detailed Embodiments

[0028] To enable those skilled in the art to better understand the technical solutions of the present disclosure, the present disclosure will be further described in detail below in conjunction with the drawings and specific embodiments.

[0029] As Figure 1As shown in the figure, a main steam pressure control system for a high-temperature reactor includes a first reactor group 1, a steam turbine 2, a condenser 3, a main steam pipeline 4, and a feed water pipeline 5. The first reactor group 1 includes a first reactor 101 and a first steam generator 102 that are interconnected. The first steam generator 102 is connected to the steam turbine 2 through the main steam pipeline 4. The steam turbine 2 is connected to the condenser 3, and the condenser 3 is connected to the first steam generator 102 through the feed water pipeline 5. The first reactor group 1 further includes a first atmospheric relief valve 103 connected in series in the main steam pipeline 4, and the system further includes a first bypass pipeline group 6. The first bypass pipeline group 6 includes a first quick-opening bypass pipeline 601 with a first quick-opening bypass valve 602 connected in series and a first regulating bypass pipeline 603 with a first regulating bypass valve 604 connected in series. The first quick-opening bypass pipeline 601 and the first regulating bypass pipeline 603 are respectively connected to the main steam pipeline 4 and the condenser 3. Among them, when a transient fault occurs in the system, the first quick-opening bypass valve 602, the first regulating bypass valve 604, and the first atmospheric relief valve 103 are opened to maintain the helium water flow ratio within a preset range.

[0030] Specifically, as Figure 1 shown, the first steam generator 102 is a once-through steam generator. During normal operation of the unit, the first atmospheric relief valve 103, the first quick-opening bypass valve 602, and the first regulating bypass valve 604 are all in the closed state. The feed water becomes superheated steam through the first steam generator 102, and the superheated steam enters the first bypass pipeline group 6 and the steam turbine 2 respectively through the main steam pipeline 4. The superheated steam entering the steam turbine 2 drives the steam turbine 2 to do work and then enters the condenser 3 to become condensate. The condensate in the condenser 3 flows back to the first steam generator 102 again through the feed water pipeline 5. During this process, the steam turbine 2 controls the pressure stability in the main steam pipeline 4.

[0031] When transient faults such as load rejection occur, the main steam pressure rises rapidly. In the initial stage of the transient fault, the first atmospheric relief valve 103 will trip multiple times, and the first quick-opening bypass valve 602 will open quickly. In the middle stage of the transient fault, the number of trips of the first atmospheric relief valve 103 gradually decreases, the first quick-opening bypass valve 602 is fully opened, and the first regulating bypass valve 604 is partially opened. In the later stage of the transient fault, the first atmospheric relief valve 103 closes and no longer trips, the first quick-opening bypass valve 602 remains open, and the first regulating bypass valve 604 is opened to an appropriate opening.

[0032] It should be noted that to prevent the first regulating bypass valve 604 from opening frequently during normal operation, its control set value is the rated main steam pressure plus a bias value. When transient faults such as load rejection occur, the control target value of the first regulating bypass valve 604 is the rated main steam pressure minus the bias value, and this lasts for a certain period of time (such as 10 seconds). After that, the control set value of the first regulating bypass valve 604 resumes to the rated main steam pressure. Among them, the bias value can be adjusted according to actual working needs. The reduction of the control target value during transient faults can also enhance the output of the regulating command of the first regulating bypass valve 604, which is beneficial to enhancing its regulating opening speed during transient faults.

[0033] It should be further noted that during the normal operation of the unit, the helium-water flow ratio of the primary and secondary circuits is 1. To ensure that the helium-water flow ratio of the primary and secondary circuits does not exceed the limit during transient faults such as load rejection, it is also necessary to set the capacity of the first quick-opening bypass valve 602. For example, if the protection reactor trip setting value of the helium-water flow ratio is 0.5 to 2, it is appropriate to set the first quick-opening bypass valve 602 to 30% of the flow rate. At this time, the maximum flow rate of the secondary circuit is 100% of the flow rate of the first atmospheric relief valve 103 plus 30% of the flow rate of the first quick-opening bypass valve. The helium-water flow ratio limit value can be obtained by dividing 1 by 1.3, which is 0.77 and will not trigger the protection reactor trip setting value of the helium-water flow ratio. The first atmospheric relief valve 103 is set to have a discharge flow rate of 30% for one opening and closing. In the middle stage of transient faults, the first quick-opening bypass valve 602 is fully opened, and the number of trips of the first atmospheric relief valve 103 decreases, that is, the number of opening and closing times of the first atmospheric relief valve 103 decreases. At this time, the helium-water flow ratio limit value can be obtained by dividing 1 by 0.6, which is 1.67 and will not trigger the protection reactor trip setting value of the helium-water flow ratio.

[0034] The main steam pressure control system of the high-temperature reactor in this embodiment can quickly and stably control the main steam pressure under transient conditions through the first atmospheric relief valve, the first quick-opening bypass pipeline with the first quick-opening bypass valve in series, and the first regulating bypass pipeline with the first regulating bypass valve in series, ensure the stability of the main feed water flow rate, and avoid the protection reactor trip due to the helium-water flow ratio of the primary and secondary circuits. At the same time, it reduces the response on the reactor side, ensures the stable operation of the unit, and the first reactor group can maintain the power without reduction during the whole process of system transient faults.

[0035] As an example, as Figure 1 shown, the feed water pipeline 5 is successively provided with a condensate pump, a low-pressure heater, a deaerator, a main feed water pump, and a high-pressure heater in series from the condenser 3 to the direction of the first steam generator 102 to preheat the condensate water in the condenser 3 and transport it into the first steam generator 102.

[0036] Exemplarily, as Figure 1As shown, a desuperheating water valve 7 is connected in series to the first quick-opening bypass pipeline 601, the first regulating bypass pipeline 603, and the condenser 3.

[0037] Specifically, as Figure 1 shown, a desuperheating water valve 7 is connected in series to the first quick-opening bypass pipeline 601, and the desuperheating water valve 7 is connected to the first quick-opening bypass valve 602. A desuperheating water valve 7 is connected in series to the first regulating bypass pipeline 603, and the desuperheating water valve 7 is connected to the first regulating bypass valve 604. A desuperheating water valve 7 is connected in series to the condenser 3. When a transient fault such as load rejection occurs, the main steam pressure rises rapidly. At this time, the first quick-opening bypass valve 602, the first regulating bypass valve 604, and the first atmospheric relief valve 103 open, and the superheated steam can also enter the condenser 3 through the first bypass pipeline group 6. The set desuperheating water valve can cool down and reduce the pressure of the superheated steam to protect the condenser from overheating and overpressure.

[0038] Exemplarily, as Figure 1 shown, the first reactor group 1 further includes a first safety valve 104. The first safety valve 104 is connected in series to the main steam pipeline 4 and is located between the first steam generator 102 and the first atmospheric relief valve 103.

[0039] Specifically, as Figure 1 stated, a first safety valve 104 is connected in series to the main steam pipeline 4, and the first safety valve 104 is arranged between the first steam generator 102 and the first atmospheric relief valve 103. The first safety valve 104 is set as a pilot-operated safety valve with the discharge capacity of single full-power flow, which can ensure that the steam generator does not overpressure and better protect each device in the main steam pressure control system of the high-temperature reactor.

[0040] Exemplarily, as Figure 1 shown, the first reactor group 1 further includes a first electric isolation valve 105 connected in series to the first atmospheric relief valve 103. The set electric isolation valve can achieve reliable isolation when the first atmospheric relief valve fails.

[0041] Exemplarily, as Figure 1 shown, the discharge capacities of the first safety valve 104 and the first atmospheric relief valve 103 are single full-power flow, and the receiving capacity of the condenser 3 is greater than the single full-power flow. The set first safety valve and first atmospheric relief valve both have the discharge capacity of single full-power flow and the condenser receiving capacity is greater than the single full-power flow, which can maintain the reactor at full power operation when a transient condition occurs in the secondary circuit.

[0042] Exemplarily, as Figure 1 shown, the first atmospheric relief valve 103 is set as a pilot-operated safety valve. The set value of the pilot-operated safety valve is lower than the set value of the first safety valve 104.

[0043] Specifically, as Figure 1 shown, the atmospheric relief valve 103 is set as a pilot-operated safety valve, and the set value of the pilot-operated safety valve is set lower than the set value of the first safety valve 104. Such a setting can better redundantly control the steam generator from overpressure and protect the equipment in the high-temperature reactor main steam pressure control system.

[0044] Exemplarily, as Figure 1 shown, the first reactor group 1 further includes a first pressure gauge 106 and a first main steam isolation valve 107, and the first bypass pipeline group 6 further includes a first bypass isolation valve 605. The first pressure gauge 106 is serially arranged in the main steam pipeline 4 and close to the first steam generator 102, the first main steam isolation valve 107 is serially arranged in the main steam pipeline 4, and the first bypass isolation valve 605 is serially arranged in the first bypass pipeline group 6.

[0045] Specifically, as Figure 1 shown, during normal operation of the unit, the first safety valve 104, the first atmospheric relief valve 103, the first quick-opening bypass valve 602, and the first regulating bypass valve 604 are all in the closed state, and the first electric isolation valve 105, the first main steam isolation valve 107, and the first bypass isolation valve 605 are in the open state. The first pressure gauge 106 is used to monitor the steam pressure on the side of the first steam generator 102.

[0046] When transient faults such as load rejection occur, the main steam pressure rises rapidly. In the initial stage of the transient fault, the first atmospheric relief valve 103 will trip multiple times, the first quick-opening bypass valve 602 will open quickly, and the corresponding desuperheating water valve 7 will open and cool down and reduce the pressure of the superheated steam. In the middle stage of the transient fault, the number of trips of the first atmospheric relief valve 103 gradually decreases, the first quick-opening bypass valve 602 is fully opened, the first regulating bypass valve 604 is partially opened, and all desuperheating water valves 7 are opened and cool down and reduce the pressure of the superheated steam. In the later stage of the transient fault, the first atmospheric relief valve 103 closes and no longer trips, the first quick-opening bypass valve 602 remains open, the first regulating bypass valve 604 is opened to an appropriate opening, and the corresponding desuperheating water valve 7 remains open and continues to cool down and reduce the pressure of the superheated steam to a certain extent.

[0047] The high-temperature reactor main steam pressure control system of this embodiment can keep the helium-water flow ratio within a suitable range during the entire transient fault process and will not trigger a protective reactor shutdown. It cools down and reduces the pressure of the discharged steam to protect the condenser from overheating and overpressure. It reduces the response on the reactor side to ensure the stable operation of the unit, and the first reactor group can maintain its power without reduction during the whole process of the system transient fault.

[0048] Exemplarily, as Figure 1As shown, the system further includes a second reactor group 8 and a secondary steam pipeline 9. The second reactor group 8 includes a second reactor (not shown in the figure) and a second steam generator (not shown in the figure) that are interconnected. The second steam generator is connected to the main steam pipeline 4 through the secondary steam pipeline 9. The second reactor group 8 further includes a second pressure gauge (not shown in the figure), a second safety valve (not shown in the figure), a second atmospheric relief valve (not shown in the figure), and a second main steam isolation valve (not shown in the figure) that are sequentially connected in series in the secondary steam pipeline 9. Among them, a second electric isolation valve (not shown in the figure) is connected in series with the second atmospheric relief valve.

[0049] Further, as Figure 1 shown, the system further includes a second bypass pipeline group 10 and a second bypass isolation valve (not shown in the figure) connected in series in the second bypass pipeline group 10. The second bypass pipeline group 10 includes a second quick-opening bypass pipeline (not shown in the figure) with a second quick-opening bypass valve (not shown in the figure) connected in series and a second regulating bypass pipeline (not shown in the figure) with a second regulating bypass valve (not shown in the figure) connected in series. The second quick-opening bypass pipeline and the second regulating bypass pipeline are respectively connected to the main steam pipeline 4 and the condenser 3, and the second quick-opening bypass pipeline and the second regulating bypass pipeline are also respectively connected in series with the desuperheating water valve 7.

[0050] Specifically, as Figure 1 shown, when the unit is operating normally, the first safety valve 104, the second safety valve, the first atmospheric relief valve 103, the second atmospheric relief valve, the first quick-opening bypass valve 602, the second quick-opening bypass valve, the first regulating bypass valve 604, and the second regulating bypass valve are all in the closed state, and the first electric isolation valve 105, the second electric isolation valve, the first main steam isolation valve 107, the second main steam isolation valve, the first bypass isolation valve 605, and the second bypass isolation valve are in the open state. The first pressure gauge 106 is used to monitor the steam pressure on the side of the first steam generator 102, and the second pressure gauge is used to monitor the steam pressure on the side of the second steam generator.

[0051] When transient faults such as load rejection occur, the main steam pressure rises rapidly. At the initial stage of the transient fault, the first atmospheric relief valve 103 and the second atmospheric relief valve will trip multiple times, the first quick-opening bypass valve 602 and the second quick-opening bypass valve will open quickly, and the corresponding desuperheating water valve 7 will open to cool down and reduce the pressure of the superheated steam. At the middle stage of the transient fault, the number of trips of the first atmospheric relief valve 103 and the second atmospheric relief valve gradually decreases, the first quick-opening bypass valve 602 and the second quick-opening bypass valve are fully opened, and one of the first regulating bypass valve 604 and the second regulating bypass valve is partially opened and the other is blocked. Such a setting can not only meet the discharge requirements, but also minimize the coupling between the first bypass pipeline group 6 and the second bypass pipeline group. The corresponding desuperheating water valve 7 opens to cool down and reduce the pressure of the superheated steam. At the later stage of the transient fault, the first atmospheric relief valve 103 and the second atmospheric relief valve close and no longer trip, the first quick-opening bypass valve 602 and the second quick-opening bypass valve remain open, the regulating bypass valve that is partially opened is opened to an appropriate opening, and the corresponding desuperheating water valve 7 remains open to continue to reduce the temperature and pressure of the superheated steam to a certain extent. As an example, the receiving capacity of the condenser 3 can be designed to be 150% of a single reactor. When transient faults such as load rejection occur, the two reactors can each reduce their power to 75%, which can avoid large-scale changes on the reactor side. As another example, the receiving capacity of the condenser 3 can be designed to be 200% of a single reactor. When transient faults such as load rejection occur, the two reactors can still maintain full power.

[0052] It should be noted that the main steam pressure control system of the high-temperature reactor can be provided with one reactor group or two reactor groups as described above, or can be provided with three reactor groups, four reactor groups, etc. The number of reactor groups set in this embodiment is not limited. Similarly, the bypass pipeline group can also be provided with one group, two groups, three groups, four groups, etc. The number of bypass pipeline groups set in this embodiment is also not limited.

[0053] The main steam pressure control system of the high-temperature reactor in this embodiment can quickly and stably control the main steam pressure under transient conditions, ensure the stability of the main feed water flow, avoid the protection shutdown of the helium water flow ratio between the primary and secondary circuits, and at the same time reduce the response on the reactor side, ensuring the stable operation of the unit.

[0054] In another aspect, an embodiment of the present disclosure provides a method for controlling the main steam pressure of a high-temperature reactor, which uses the system described above. The method includes: at the initial stage of the transient fault of the system, the quick-opening bypass valve is opened, and the atmospheric relief valve jumps multiple times to ensure that the secondary circuit does not lose flow. At the middle stage of the transient fault of the system, the quick-opening bypass valve is fully opened, the regulating bypass valve is partially opened, and the number of jumps of the atmospheric relief valve is reduced. At the later stage of the transient fault of the system, the quick-opening bypass valve remains open, the regulating bypass valve is opened to an appropriate opening degree, and the atmospheric relief valve no longer jumps.

[0055] The method for controlling the main steam pressure of the high-temperature reactor in this embodiment can quickly and stably control the main steam pressure under transient conditions by controlling the opening and closing of the atmospheric relief valve, the quick-opening bypass valve, and the regulating bypass valve, ensure the stability of the main feed water flow, and avoid the reactor trip due to the protection of the helium water flow ratio between the primary and secondary circuits. At the same time, the response on the reactor side is reduced, ensuring the stable operation of the unit.

[0056] It can be understood that the above embodiments are merely exemplary embodiments adopted to illustrate the principles of the present disclosure. However, the present disclosure is not limited thereto. For those of ordinary skill in the art, various modifications and improvements can be made without departing from the spirit and essence of the present disclosure, and these modifications and improvements are also considered within the protection scope of the present disclosure.

Claims

1. A method for controlling the main steam pressure of a high-temperature reactor, which uses a main steam pressure control system for a high-temperature reactor. The system includes a first reactor group, a steam turbine, a condenser, a main steam pipeline, and a feed water pipeline. The first reactor group includes a first reactor and a first steam generator that are interconnected. The first steam generator is connected to the steam turbine through the main steam pipeline. The steam turbine is connected to the condenser, and the condenser is connected to the first steam generator through the feed water pipeline. It is characterized in that, The first reactor group further includes a first atmospheric relief valve connected in series to the main steam pipeline. The system further includes a first bypass pipeline group, which includes a first quick-opening bypass pipeline with a first quick-opening bypass valve connected in series and a first regulating bypass pipeline with a first regulating bypass valve connected in series. The first quick-opening bypass pipeline and the first regulating bypass pipeline are respectively connected to the main steam pipeline and the condenser; a desuperheating water valve is connected in series to the first quick-opening bypass pipeline, the first regulating bypass pipeline and the condenser; wherein, During a transient fault of the system, the first quick-opening bypass valve, the first regulating bypass valve and the first atmospheric relief valve open, so that the helium water flow rate ratio is maintained within a preset range; The control method includes that at the initial stage of the transient fault of the system, the first quick-opening bypass valve opens, and the first atmospheric relief valve makes multiple trips to ensure that the secondary circuit does not lose flow; During the middle stage of the transient fault of the system, the first quick-opening bypass valve is fully opened, the first regulating bypass valve is partially opened, and the number of trips of the first atmospheric relief valve decreases; During the late stage of the transient fault of the system, the first quick-opening bypass valve remains open, the first regulating bypass valve is opened to an appropriate opening degree, and the first atmospheric relief valve no longer makes trips.

2. The high-temperature reactor main steam pressure control method according to claim 1, wherein The first reactor group further includes a first safety valve; The first safety valve is connected in series to the main steam pipeline and is located between the first steam generator and the first atmospheric relief valve.

3. The high-temperature reactor main steam pressure control method according to claim 2, characterized in that The first reactor group further includes a first electric isolation valve connected in series to the first atmospheric relief valve.

4. The high-temperature reactor main steam pressure control method according to claim 3, characterized in that The discharge capacities of the first safety valve and the first atmospheric relief valve are the single full-power flow rate, and the receiving capacity of the condenser is greater than the single full-power flow rate.

5. The high-temperature reactor main steam pressure control method according to any one of claims 2 to 4, characterized in that The first atmospheric relief valve is set as a pilot-operated safety valve; The set value of the pilot-operated safety valve is lower than the set value of the first safety valve.

6. The method for controlling the main steam pressure of a high-temperature reactor according to any one of claims 1 to 4, characterized in that, The first reactor group further includes a first pressure gauge and a first main steam isolation valve, and the first bypass pipeline group further includes a first bypass isolation valve; The first pressure gauge is connected in series to the main steam pipeline and is close to the first steam generator, the first main steam isolation valve is connected in series to the main steam pipeline, and the first bypass isolation valve is connected in series to the first bypass pipeline group.

7. The main steam pressure control method for a high-temperature reactor according to any one of claims 1 to 4, characterized in that, The system further includes a second reactor group and a secondary steam pipeline; The second reactor group includes a second reactor and a second steam generator that are connected to each other. The second steam generator is connected to the main steam pipeline through the secondary steam pipeline; The second reactor group further includes a second pressure gauge, a second safety valve, a second atmospheric relief valve and a second main steam isolation valve connected in series to the secondary steam pipeline in sequence; wherein, A second electric isolation valve is connected in series to the second atmospheric relief valve.

8. The high-temperature reactor main steam pressure control method according to any one of claims 1 to 4, characterized in that The system further includes a second bypass pipeline group and a second bypass isolation valve connected in series to the second bypass pipeline group; The second bypass pipeline group includes a second quick-opening bypass pipeline with a second quick-opening bypass valve in series and a second regulating bypass pipeline with a second regulating bypass valve in series. The second quick-opening bypass pipeline and the second regulating bypass pipeline are respectively communicated with the main steam pipeline and the condenser, and the second quick-opening bypass pipeline and the second regulating bypass pipeline are also respectively connected in series with the desuperheating water valve.

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