Transient working condition control device and method under multi-module high-temperature gas cooled reactor combined heat and power working condition

Abstract

The invention provides a transient working condition control device and method under a multi-module high-temperature gas cooled reactor combined heat and power working condition. The transient condition control device under the multi-module high-temperature gas cooled reactor cogeneration condition comprises a plurality of NSSS module control system modules, a unit control system module, a steam turbine control system module, a main steam pressure control system module, a main feed water pressure control system module and a heat supply station control system module. And the unit control system module is used for controlling a plurality of transient working conditions according to a plurality of received signal parameters output by the NSSS module control system modules, the steam turbine control system module, the main steam pressure control system module, the main feed water pressure control system module and the heat supply station control system module. According to the system, the multiple control system modules are additionally arranged, so that the problems that when the unit occurs in a transient state, the simple jump stop of a steam turbine or a reactor can generate large influence on external steam supply, and industrial enterprise equipment is damaged and economic losses are large are solved.

Description

Technical Field

[0001] The present application belongs to the technical field of multi-module high-temperature gas-cooled reactors, and specifically relates to a transient operating condition control device and method for a multi-module high-temperature gas-cooled reactor under cogeneration conditions. Background Art

[0002] As a clean, efficient and stable energy source, nuclear energy has unique advantages in reducing coal consumption and greenhouse gas emissions. Nuclear energy is relatively mature in the field of power generation, mainly in pressurized water reactor nuclear power plants. However, with the commercial operation of high-temperature gas-cooled reactor units, the application of nuclear energy has been further expanded.

[0003] The high temperature gas-cooled reactor is an internationally recognized fourth-generation advanced nuclear power technology with inherent safety. Even if no intervention measures are taken, the reactor can still remain safe in the event of a loss of all cooling capacity. The high temperature gas-cooled reactor has a large core heat capacity and can produce high-temperature steam. It has broad applications in power generation, cogeneration, high-temperature heating, hydrogen production and other fields.

[0004] In view of the relatively high current construction cost of high-temperature gas-cooled reactors, and taking comprehensive economic benefits into consideration, it is possible to couple high-temperature gas-cooled reactors and Hualong One reactor units with independent intellectual property rights for cogeneration of heat and power, produce steam with various parameters, and provide heat for industrial enterprises such as the chemical industry.

[0005] The process flow diagram of the heating system is as follows: Figure 1 The main steam from the secondary circuit of Hualong One unit 1-2 is used to heat the third circuit heating steam feed water 1-3 through the saturated evaporative heat exchanger 1-4, and then the high-temperature and high-pressure steam from the secondary circuit of the multi-module high-temperature gas-cooled reactor unit 1-1 is used to superheat the saturated industrial steam through the superheat heat exchanger 1-5, and finally the external steam 1-6 that meets the requirements is delivered to the heat users.

[0006] The pure condensing power generation units currently in commercial operation use a typical dual-module high-temperature gas-cooled reactor. The process flow diagram of a typical dual-module high-temperature gas-cooled reactor is shown in Figure 2 , the high temperature gas-cooled reactor module is also called the nuclear steam supply system module (Nuclear Steam Supply System, hereinafter referred to as NSSS module). Figure 3 A typical NSSS module consists of a reactor 1, a main helium blower 2 and a steam generator 3, which is connected to the corresponding steam turbine main regulating valve 4 and feedwater regulating valve 5. Figure 2, NSSS module No. 1 2-1 and NSSS module No. 2 2-2 operate independently of each other, and can be operated as a single NSSS module or as a combination of two NSSS modules. Each NSSS module is equipped with an independent feedwater pump and feedwater regulating valve to adjust the feedwater flow entering the steam generator. Specifically, NSSS module No. 1 2-1 is correspondingly equipped with a first feedwater regulating valve 2-3 and a first feedwater pump 2-4, and NSSS module No. 2 2-2 is correspondingly equipped with a second feedwater regulating valve 2-5 and a second feedwater pump 2-6. The steam generated by NSSS module No. 1 2-1 and NSSS module No. 2 2-2 enters the first steam turbine 2-8 through the first steam turbine main regulating valve 2-7 to perform work. The steam after the first steam turbine 2-8 performs work is condensed in the first condenser 2-10, and the condensate pump group 2-11 pumps water from the first condenser 2-10 to the inlet of the first feedwater pump 2-4 and the second feedwater pump 2-6.

[0007] The high temperature gas-cooled reactor pure condensing power generation unit adopts the "machine-follows-the-reactor" operation mode, that is, the reactor is operated in a set load mode, and the first steam turbine 2-8 tracks the change of the reactor output thermal power by adjusting the first steam turbine main regulating valve 2-7 to control the main steam header pressure. The control principle diagram of the transient operating condition of the dual-module high temperature gas-cooled reactor module pure condensing power generation unit is shown in Figure 4 , NSSS module control system module 3-2 No. 1 and NSSS module control system module 3-3 No. 2 are responsible for manual control and automatic control of NSSS module 2-1 No. 1 and NSSS module 2-2 No. 2, respectively, and output stable thermal power. The unit coordination control system module 3-1 is responsible for allocating the reactor output thermal power setting value to NSSS module control system module 3-2 No. 1 and NSSS module control system module 3-3 No. 2 according to the unit power setting value. The first steam turbine control system module 3-4 is responsible for the control of the first steam turbine main regulating valve 2-7, the first steam turbine 2-8, the first bypass regulating valve group 2-9 and the first condenser 2-10.

[0008] Under the transient condition of turbine tripping, the first steam turbine control system module 3-4 controls the first bypass regulating valve group 2-9 to adjust the pressure of the main steam header and discharge excess steam to the first condenser 2-10; under the transient condition of reactor tripping, the first steam turbine control system module 3-4 protects the shutdown of the first steam turbine 2-8; when the first feedwater pump 2-4 corresponding to NSSS module No. 1 stops, the NSSS module control system module 3-2 controls the NSSS module No. 1 2-1 to shut down, and when the second feedwater pump 2-6 corresponding to NSSS module No. 2 2-2 stops, the NSSS module control system module 3-3 controls the NSSS module No. 2 2-2 to shut down.

[0009] The transient operating conditions of the two-module high-temperature gas-cooled reactor pure condensing power generation unit mainly include the above three types: turbine tripping, reactor tripping and feedwater pump tripping, and the control design is relatively simple. Because the power generation power (200MW) is relatively small relative to the grid capacity, the impact of the unit tripping on the grid is relatively small. After the heating load is increased, the main steam pipeline adds a secondary circuit heating load branch to produce external steam for the heating network. The amount of external steam generally accounts for most or all of the entire heating network. When the unit transient occurs, a simple tripping of the turbine or reactor will have a greater impact on the external steam supply, causing damage to industrial equipment and greater economic losses. Therefore, the multi-module high-temperature gas-cooled reactor cogeneration unit needs to consider more transient conditions, and on the basis of ensuring nuclear safety, try to maintain the stability of the heating system, and give priority to ensuring the coordinated control plan of the reactor, machine, and heat of the heating load. Summary of the invention

[0010] In view of this, the embodiments of the present application are committed to providing a transient operating condition control device and method under a multi-module high-temperature gas-cooled reactor cogeneration condition. By adding multiple control system modules such as a unit control system module, a turbine control system module and a main steam pressure control system module, the problem existing in the prior art that when a unit transient occurs, simply shutting down the turbine or reactor will have a significant impact on the external steam supply, causing damage to industrial enterprise equipment and significant economic losses.

[0011] The first aspect of the present application provides a transient operating condition control device under a multi-module high-temperature gas-cooled reactor cogeneration condition, and the transient operating condition control device under a multi-module high-temperature gas-cooled reactor cogeneration condition includes multiple NSSS module control system modules, a unit control system module 5-7, a turbine control system module 5-8, a main steam pressure control system module 5-9, a main feed water pressure control system module 5-10 and a heating station control system module 5-11. The multiple NSSS module control system modules are used to respectively control the operation of multiple NSSS modules in the multi-module high-temperature gas-cooled reactor, and output the operating status signals of multiple NSSS modules to the unit control system module 5-7. The turbine control system module 5-8 is used to control the protection and operation of the turbine 4-14 under multiple transient conditions according to the received signal sent by the unit control system module 5-7. The main steam pressure control system module 5-9 is used to control the bypass regulating valve group 4-5 to adjust the pressure of the main steam header to a set value when the turbine trips or the main steam pressure cannot be adjusted under transient conditions. The feedwater pressure control module 5-10 is used to control the steam flow outside the heating island under multiple transient conditions, and to maintain the pressure and temperature parameters of the external steam supply to meet the set requirements, monitor the rupture of the heating network and maintain the stability of the heating load, so as to get rid of part of the heating load or isolate the heating pipeline. The heating station control system module 5-11 is used to control the heating station. The unit control system module 5-7 is used to automatically allocate the reactor output thermal power set values ​​of multiple NSSS modules according to the preset strategy; to automatically allocate the reactor output thermal power set values ​​or output shutdown signals to multiple NSSS module control system modules under multiple transient conditions; to send load shedding or shutdown signals to the turbine control system module 5-8; to send the main steam pressure control switching signal to the main steam pressure control system 5-9; to send the adjustment or pump stop signal to the feedwater pressure control module 5-10. The unit control system module 5-7 is used to perform multiple transient operating condition controls based on the multiple signal parameters output by the received multiple NSSS module control system modules, the turbine control system module 5-8, the main steam pressure control system module 5-9, the main feed water pressure control system module 5-10 and the heating station control system module 5-11.

[0012] In a specific embodiment of the present application, the NSSS module control system module includes a first acquisition submodule, a first receiving submodule, a regulating submodule, a tripping submodule and a first output submodule. The first acquisition submodule is used to acquire the process parameters of the corresponding NSSS module, the first receiving submodule is used to receive the reactor output thermal power setting value signal and the shutdown signal from the unit control system module 5-7, the regulating submodule is used to adjust the corresponding NSSS module feed water regulating valve, the main helium fan 2 and the reactor control rod according to the reactor output thermal power setting value signal so that the reactor output thermal power reaches the set value; the tripping submodule is used to trip the corresponding NSSS module according to the shutdown signal; the first output submodule is used to output the operation status signal of the corresponding NSSS module to the unit control system module 5-7.

[0013] In a specific embodiment of the present application, the NSSS module control system module further includes a power control submodule. The power control submodule is used to manually increase the reactor power and output thermal power within the range of 0% to 30% RPF, automatically maintain the reactor power and output thermal power within the range of 30% to 50% RPF, and automatically convert the reactor power and output thermal power within the range of 50% to 100% RPF to achieve coordinated control within multiple NSSS modules.

[0014] At least one embodiment of the present application also provides a method for coordinated control of the reactor, machine and heat under transient conditions of a multi-module high-temperature gas-cooled reactor cogeneration condition. The method for coordinated control of the reactor, machine and heat under transient conditions of a multi-module high-temperature gas-cooled reactor cogeneration condition includes: determining the type of transient conditions under the multi-module high-temperature gas-cooled reactor cogeneration condition. The types of multiple transient conditions include NSSS module emergency shutdown transient conditions, main transformer high-voltage side circuit breaker disconnection transient conditions, turbine tripping transient conditions, feedwater pump tripping transient conditions, heating network load shedding transient conditions and heating network rupture transient conditions; according to the type of transient conditions, the transient condition control device under the multi-module high-temperature gas-cooled reactor cogeneration condition of the embodiment of the present application is used for control.

[0015] In a specific embodiment of the present application, the above-mentioned type of transient operating condition is controlled by using the transient operating condition control device under the multi-module high-temperature gas-cooled reactor cogeneration condition of the first aspect of the present application, including: the unit control system module 5-7 calculates the current effective reactor output total thermal power and the adjustable reactor output thermal power in real time; under the transient operating condition of the NSSS module emergency shutdown, for the NSSS module without steam in multiple NSSS modules, the unit control system module 5-7 does not make a load shedding judgment; for the other NSSS modules with load in multiple NSSS modules, the unit control system module 5-7 automatically makes a load shedding judgment; the main feed water pressure control system module 5-10 controls the feed water pump to maintain the pressure of the feed water main pipe in the pressure control mode, and switches the corresponding feed water pump to recirculation operation or cuts off according to the total feed water flow and the minimum allowable load of the feed water pump.

[0016] In a specific embodiment of the present application, the above-mentioned type of transient operating condition is controlled by using the transient operating condition control device under the multi-module high-temperature gas-cooled reactor cogeneration condition of the first aspect of the present application, including: under the transient operating condition when the circuit breaker on the high-voltage side of the main transformer is disconnected, the steam turbine suddenly loses load, the steam turbine control system module 5-8 controls the steam turbine to switch to the load control mode, and quickly dumps the load to the island operation load, the main steam pressure control system module 5-9 controls the bypass regulating valve group 4-5 to maintain the pressure of the main steam manifold and remove excess steam; the unit control system module 5-7 controls the total thermal power output of the reactor to remain unchanged, and the heating island control system module 5-11 controls the normal operation of the heating load; after the transient is stable, the total thermal power output of the reactor is manually reduced through the unit control system module 5-7 until the bypass regulating valve is closed.

[0017] In a specific embodiment of the present application, the above-mentioned type of transient operating conditions is controlled by using the transient operating condition control device under the multi-module high-temperature gas-cooled reactor cogeneration condition of the first aspect of the present application, including: under the transient operating condition of the turbine tripping condition, the main steam pressure control system module 5-9 controls the bypass regulating valve group 4-15 to maintain the pressure of the main steam manifold and remove excess steam; the unit control system module 5-10 controls the total thermal power output of the reactor to remain unchanged, and the heating island control system module 5-11 controls the normal operation of the heating load; after the transient is stable, the total thermal power output of the reactor is manually reduced through the unit control system module 5-7 until the bypass regulating valve is closed.

[0018] In a specific embodiment of the present application, the above-mentioned transient operating condition control device under the multi-module high-temperature gas-cooled reactor cogeneration condition of the first aspect of the present application is used for control according to the type of transient operating condition, including: the unit coordination control system module 5-7 calculates and judges in real time whether the feed water volume meets the operating requirements of the NSSS module at the current power according to the status of the tripped pump group, the number of feed water pumps in operation and the status of multiple NSSS modules; under the transient operating condition of the feed water pump tripping condition, the unit control system module 5-7 makes a real-time judgment that when the current feed water flow cannot meet the operating requirements of the NSSS module at the current power, it trips the reactor according to the conditions of the NSSS modules without steam connection, the reactors that have steam connection but are not in the unit coordination control mode, and the reactors that have been put into the unit coordination control mode, and in a preset priority order to ensure the maximum stable output of heat supply under the available feed water flow; the turbine control system module 5-8 controls the turbine to follow the main steam pressure load shedding to the minimum long-term operating power in the pressure control mode. The heating island control system module 5-11 controls to discard part of the externally supplied steam or reduce the quality of part of the externally supplied steam.

[0019] In a specific embodiment of the present application, the above-mentioned type of transient operating conditions is controlled by using the transient operating condition control device under the cogeneration condition of the multi-module high-temperature gas-cooled reactor of the first aspect of the present application, including: under the transient operating condition of the heat network load shedding, when the heat network load shedding occurs, the pressure of the heating pipeline increases rapidly to reduce the required secondary circuit steam. The heating island control system module 5-11 controls the stable operation of the external steam supply; the unit control system module 5-7 controls the reactor output total thermal power to remain unchanged, and the turbine control system module 5-8 controls the turbine main regulating valve 4-13 to maintain the pressure of the main steam header, and increases the load of the turbine within the adjustable range to absorb the excess steam in the secondary circuit. When the turbine power rises to full load, it switches to the fixed load operation mode, and the main steam pressure control system module 5-9 controls the bypass regulating valve group 4-15 to adjust the pressure of the main steam engine header; after the transient is stable, the total thermal power output of the reactor is manually reduced through the unit control system module 5-7 until the bypass regulating valve is closed.

[0020] In a specific embodiment of the present application, the above-mentioned type of transient operating condition is controlled by using the transient operating condition control device under the cogeneration condition of the multi-module high-temperature gas-cooled reactor of the first aspect of the present application, including: under the transient operating condition of the heat network rupture, the heating island control system module 5-11 comprehensively judges that a rupture has occurred based on the two signals of the monitored pressure change and the decrease rate, and the pneumatic fast shut-off valve before the ruptured heating pipe leaves the factory is closed; at the initial stage of the rupture, the heating load rises rapidly, and the heating island control system module 5-11 controls the heating regulating valve 4-19 to open and the turbine control system module 5-8 to control the main steam regulating valve 4-13 to close for follow-up response; during the transient period, the heating island control system module 5-11 limits the flow increase rate and the total heating flow on the heating station side according to the external pipeline rupture condition; after the transient is stable, the total thermal power output of the reactor is manually reduced through the unit control system module 5-7 until the bypass regulating valve is closed.

[0021] The beneficial effects of the technical solution of the present application are: the unit control system module 5-7 can identify the operating status of multiple NSSS modules and calculate the available total thermal power output of the reactor according to the operating status signals of multiple NSSS modules; the status and flow value of each feedwater pump of the main feedwater pressure control system module 5-10 are used to calculate the mismatch between the available main feedwater flow and the total thermal power output of the reactor, and judge the production protection shutdown signal, turbine load rejection signal or shutdown signal, and feedwater pump shutdown signal. For example, if a feedwater pump trips, the feedwater flow cannot meet the total thermal power output of the reactor; the set value of the total thermal power output of the reactor is calculated according to the turbine operating status and power generation value of the turbine control system module 5-8; the set value of the total thermal power output of the reactor is calculated according to the secondary circuit heating flow signal; the adjustment of the total thermal power output of the reactor is stopped according to the heat network rupture signal and the heat network load rejection signal, so as to avoid the risk of coupled oscillation caused by simultaneous regulation of the stack, machine and heat. BRIEF DESCRIPTION OF THE DRAWINGS

[0022] Figure 1 Shown is a simplified diagram of the heating system process flow.

[0023] Figure 2 Shown is a simplified process diagram of a typical dual-module high-temperature gas-cooled reactor pure condensing power generation unit.

[0024] Figure 3 Shown is the transient operating control principle diagram of the dual-module high-temperature gas-cooled reactor module pure condensing power generation unit.

[0025] Figure 4 Shown is a simplified diagram of the NSSS module process.

[0026] Figure 5 Shown is a simplified diagram of the multi-module high-temperature gas-cooled reactor cogeneration process.

[0027] Figure 6The figure shows a simplified process diagram of a transient operating condition control device under a multi-module high-temperature gas-cooled reactor cogeneration condition provided by an embodiment of the present application.

[0028] Figure 7 The figure shows a flow chart of a method for coordinated control of reactor, engine and heat under transient conditions in a multi-module high temperature gas-cooled reactor cogeneration condition provided by an embodiment of the present application. DETAILED DESCRIPTION

[0029] After the heating load is increased, the multi-module high-temperature gas-cooled reactor cogeneration process system becomes more complicated. The schematic diagram of the multi-module high-temperature gas-cooled reactor cogeneration process flow is shown in Figure 5 As shown, according to the heating demand, the HTR-PM600S high temperature reactor model is selected, and the number of NSSS modules is increased to 6, that is, the first NSSS module 4-1 to the sixth NSSS module 4-6, the main water supply adopts the mother pipe, the water supply pump group 4-18 controls the pressure of the main water supply mother pipe, the first NSSS module water supply regulating valve 4-7 controls the water supply flow of the first NSSS module 4-1, the second NSSS module water supply regulating valve 4-8 controls the water supply flow of the second NSSS module 4-2, the third NSSS module water supply regulating valve 4-9 controls the water supply flow of the third NSSS module 4-3, the fourth NSSS module water supply regulating valve 4-10 controls the water supply flow of the fourth NSSS module 4-4, the fifth NSSS module water supply regulating valve 4-11 controls the water supply flow of the fifth NSSS module 4-5, and the sixth NSSS module water supply regulating valve 4-12 controls the water supply flow of the sixth NSSS module 4-6. The feed water is heated into main steam through each NSSS module and transported to the main steam main pipe (the main steam adopts the main pipe control). A part of the main steam from the main steam main pipe enters the steam turbine 4-14 through the main regulating valve 4-13 of the steam turbine to perform work. The exhaust steam from the steam turbine 4-14 enters the condenser 4-16 to condense. The condensate pump group 4-17 extracts the condensate from the condenser 4-16 and sends it to the inlet of the feed water pump group 4-18; another part of the main steam from the main steam main pipe enters the superheat heat exchanger 4-20 through the heating regulating valve 4-19 to control the temperature of the external steam supply. When the main steam pressure is too high, the excess main steam is discharged to the condenser 4-16 through the bypass regulating valve group 4-15 to avoid main steam overpressure. The coordinated control between the stack and the machine of the original pure condensing unit has become the coordinated control between the stack, the machine and the heat. The transient response process needs to consider the coordinated control of the reactor, machine and heat to avoid the simultaneous adjustment of the reactor, machine and heat and the risk of coupled control oscillation, so as to ensure the stable operation of the heating system.

[0030] Based on this, the embodiments of the present application provide a transient operating condition control device and method under a multi-module high-temperature gas-cooled reactor cogeneration condition, which performs decoupling control on the reactor power, turbine load and heating load respectively under multiple transient operating conditions, avoids simultaneous adjustment of the reactor, turbine and heating as much as possible, and gives priority to meeting the heating demand while ensuring nuclear safety and stable operation of the NSSS module, thereby ensuring safe, stable and reliable operation of the entire heating system.

[0031] The following will be combined with the drawings in the embodiments of this application to clearly and completely describe the technical solutions in the embodiments of this application. Obviously, the described embodiments are only part of the embodiments of this application, not all of them. Based on the embodiments in this application, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of this application. Figure 5 The multi-module high temperature gas-cooled reactor shown is used as an example for illustration.

[0032] At least one embodiment of the present application provides a transient operating condition control device under a multi-module high temperature gas-cooled reactor cogeneration condition, referring to Figure 6The transient operating condition control device under the multi-module high-temperature gas-cooled reactor cogeneration condition includes multiple NSSS module control system modules, a unit control system module 5-7, a turbine control system module 5-8, a main steam pressure control system module 5-9, a main feed water pressure control system module 5-10 and a heating station control system module 5-11. The multiple NSSS module control system modules are used to respectively control the operation of multiple NSSS modules in the multi-module high-temperature gas-cooled reactor, and output the operating status signals of multiple NSSS modules to the unit control system module 5-7. The turbine control system module 5-8 is used to control the protection and operation of the turbine 4-14 under multiple transient conditions according to the received signal sent by the unit control system module 5-7. The main steam pressure control system module 5-9 is used to control the bypass regulating valve group 4-5 to adjust the pressure of the main steam header to the set value under transient conditions when the turbine trips or the main steam pressure cannot be adjusted. The feedwater pressure control module 5-10 is used to control the steam flow outside the heating island under multiple transient conditions, and to maintain the pressure and temperature parameters of the external steam supply to meet the set requirements, monitor the rupture of the heating network and maintain the stability of the heating load, so as to get rid of part of the heating load or isolate the heating pipeline. The heating station control system module 5-11 is used to control the heating station. The unit control system module 5-7 is used to automatically allocate the reactor output thermal power set values ​​of multiple NSSS modules according to the preset strategy; to automatically allocate the reactor output thermal power set values ​​or output shutdown signals to multiple NSSS module control system modules under multiple transient conditions; to send load shedding or shutdown signals to the turbine control system module 5-8; to send the main steam pressure control switching signal to the main steam pressure control system 5-9; to send the adjustment or pump stop signal to the feedwater pressure control module 5-10. The unit control system module 5-7 is used to perform multiple transient operating condition controls based on the multiple signal parameters output by the received multiple NSSS module control system modules, the turbine control system module 5-8, the main steam pressure control system module 5-9, the main feed water pressure control system module 5-10 and the heating station control system module 5-11.

[0033] It should be noted that the unit control system module 5-7 is communicatively connected with multiple NSSS module control system modules, the turbine control system module 5-8, the main steam pressure control system module 5-9, the main feed water pressure control system module 5-10 and the heating station control system module 5-11.

[0034] The unit control system module 5-7 automatically distributes the reactor stack output thermal power setting value or outputs a shutdown signal to the multiple NSSS module control system modules. For example, if the feedwater pump trips and stops, resulting in insufficient feedwater flow, some NSSS modules are tripped to ensure the stability of as many NSSS modules as possible. The number of the multiple NSSS modules can be greater than 2, and accordingly, the number of the multiple NSSS module control system modules can be greater than 2.

[0035] The unit control system module 5-7 sends a load shedding or shutdown signal to the steam turbine control system module 5-8. For example, some NSSS modules are tripped and the main steam flow is insufficient. In order to give priority to heat supply, the steam turbine is tripped. The steam turbine control system module 5-8 has various control functions such as speed control mode, load control mode, valve control mode, and load shedding mode. Under transient conditions, the steam turbine control system module 5-8 can control the steam turbine 4-14 to quickly shed load to maintain the stability of the main steam pressure or trip the machine to give priority to heat supply.

[0036] The unit control system module 5-7 sends a main steam pressure control switching signal to the main steam pressure control system 5-9 to maintain the stability of the heating system as much as possible. The main steam pressure control system 5-9 controls the bypass regulating valve group 4-5 to adjust the pressure of the main steam header to the set value, which can ensure that the main steam header pressure is not over-pressured.

[0037] The unit control system module 5-7 sends an adjustment or pump stop signal to the feed water pressure control module 5-10. For example, some NSSS modules are regulated, the feed water flow is too large, and some feed water pumps are stopped to ensure that the total thermal power output of the reactor matches the feed water.

[0038] The various signal parameters include the operating status signal of the NSSS module, the operating status signal of the steam turbine, the power generation value, the main steam pressure setting value and measurement value, the status and flow value of each feedwater pump, the heat network rupture signal and the heat network load rejection signal. The operating status signal of the NSSS module includes but is not limited to the reactor output thermal power, reactor power and trip signal.

[0039] It should be noted that the reactor output thermal power setting values ​​of multiple NSSS modules are automatically allocated according to a preset strategy. For example, an adjustable reactor output thermal power ratio allocation strategy is adopted, that is, the amount of adjustment required for the total reactor output thermal power is allocated to these NSSS modules according to the percentage of the adjustable value of the reactor output thermal power of all NSSS modules in the automatic control mode to the sum of the reactor output thermal power of each NSSS module in all automatic control modes.

[0040] According to the technical solution provided in the embodiment of the present application, the unit control system module 5-7 can identify the operating status of multiple NSSS modules and calculate the available total thermal power output of the reactor according to the operating status signals of multiple NSSS modules; the status and flow value of each feedwater pump of the main feedwater pressure control system module 5-10 are used to calculate the mismatch between the available main feedwater flow and the total thermal power output of the reactor, and judge the production protection shutdown signal, the turbine load rejection signal or the shutdown signal, and the feedwater pump shutdown signal, for example, the feedwater pump trips, resulting in the feedwater flow being unable to meet the total thermal power output of the reactor; the total thermal power output setting value of the reactor is calculated according to the turbine operating status and the power generation value of the turbine control system module 5-8; the total thermal power output setting value of the reactor is calculated according to the secondary circuit heating flow signal; the adjustment of the total thermal power output of the reactor is stopped according to the heat network rupture signal and the heat network load rejection signal, so as to avoid the risk of coupled oscillation caused by simultaneous regulation of the stack, machine and heat.

[0041] In at least one embodiment of the present application, the NSSS module control system module includes a first acquisition submodule, a first receiving submodule, a regulating submodule, a tripping submodule and a first output submodule. The first acquisition submodule is used to acquire the process parameters of the corresponding NSSS module, the first receiving submodule is used to receive the reactor output thermal power setting value signal and the shutdown signal from the unit control system module 5-7, the regulating submodule is used to adjust the corresponding NSSS module feed water regulating valve, the main helium fan 2 and the reactor control rod according to the reactor output thermal power setting value signal so that the reactor output thermal power reaches the set value; the tripping submodule is used to trip the corresponding NSSS module according to the shutdown signal; the first output submodule is used to output the operation status signal of the corresponding NSSS module to the unit control system module 5-7.

[0042] For example, the process parameters of the NSSS module include but are not limited to nuclear power, helium flow, hot helium temperature, cold helium temperature, main feed water flow, control rod position, main feed water temperature, main steam pressure and main steam temperature.

[0043] In at least one embodiment of the present application, the unit control system module 5-7 includes a second receiving submodule. The second receiving submodule is used to receive operating status signals from multiple NSSS modules; to identify the operating status signals of the NSSS modules and calculate the total thermal power output of the available reactor; to receive the status and flow value of each feedwater pump from the main feedwater pressure control system module 5-10; to receive the operating status signal of the steam turbine from the steam turbine control system module 5-8, and when receiving the turbine shutdown signal, send a signal to the main steam pressure control system 5-9, switch to the bypass regulating valve group 4-15 to control the pressure of the main steam header; receive the secondary circuit heating flow signal, the heating network rupture signal and the heating network load rejection signal from the heating station control system module 5-11.

[0044] The operation status signal of the steam turbine includes but is not limited to the power generation, the steam turbine shutdown signal, the load rejection signal, etc. The status of the feed water pump includes but is not limited to the start and stop status.

[0045] In at least one embodiment of the present application, the steam turbine control system module 5-8 includes a second acquisition submodule, a first control submodule, a third receiving submodule and a second output submodule. The second acquisition submodule is used to collect process data of the steam turbine. The first control submodule is used to control the main regulating valve 4-13 of the steam turbine to realize turbine run-up, grid connection, load increase and decrease, load rejection or shutdown. The third receiving submodule is used to receive the turbine load rejection or shutdown signal from the unit control system module 5-7; and is used to receive the main steam pressure set value and measurement value from the main steam pressure control system module 5-9 to control the main steam pressure at a fixed value. The second output submodule is used to output the operating status and power generation value of the steam turbine to the unit control system module 5-7 to participate in the adjustment of the total thermal power set value output by the reactor.

[0046] For example, the process data of the steam turbine include but are not limited to the steam turbine speed and the regulating stage inlet steam pressure.

[0047] In at least one embodiment of the present application, the main steam pressure control system module 5-9 includes a third acquisition submodule, a second control submodule and a third output submodule. The third acquisition submodule is used to collect process parameters of the main steam system. The second control submodule is used to control the bypass regulating valve group 4-15 to maintain the pressure of the main steam header. The third output submodule is used to output the main steam pressure set value and the measured value to the turbine control system module 5-8 to participate in the main steam pressure control.

[0048] For example, the process parameters of the main steam system include, but are not limited to, main steam pressure and temperature.

[0049] In at least one embodiment of the present application, the main feed water pressure control system module 5-10 includes a fourth acquisition submodule, a third control submodule, a fourth output submodule and a fourth receiving submodule. The fourth acquisition submodule is used to collect process parameters of the main feed water system. The third control submodule is used to control the pressure of the feed water main pipe by controlling the speed of the feed water pump group 4-18; the fourth output submodule is used to output the status and flow value of each feed water pump to the unit control system module 5-7 to participate in the total thermal power output of the reactor and the feed water mismatch. The fourth receiving submodule is used to receive a feed water pump stop signal from the unit control system module 5-7 to stop the feed water pump.

[0050] For example, the process parameters of the main feed water system include, but are not limited to, the main feed water pressure and temperature, and the status of the main feed water pump.

[0051] In at least one embodiment of the present application, the heating station control system module 5-11 includes a fifth acquisition submodule, a fourth control submodule, a monitoring module and a fifth output submodule. The fifth acquisition submodule is used to collect process parameters of the superheat exchanger and the external steam supply network of the heating station. The fourth control submodule is used to control the heating regulating valve 4-19 to maintain the temperature parameters of the heating steam parameters at the set value. The monitoring module is used to monitor the occurrence of transient conditions of heating network rupture and heating network load shedding, and to perform control responses to maintain the stability of the heating system. The fifth output submodule is used to output the heating network rupture signal and the heating network load shedding signal to the unit control system module 5-7 to participate in the adjustment of the total thermal power output of the reactor.

[0052] Multiple NSSS modules operate independently, and there are multiple combinations of operations. In at least one embodiment of the present application, the NSSS module control system module also includes a power control submodule. The power control submodule is used to manually increase the reactor power and output thermal power within the range of 0-30% RPF, automatically maintain the reactor power and output thermal power within the range of 30%-50% RPF, and realize coordinated control within multiple NSSS modules within the range of 50%-100% RPF, and automatically convert the reactor power and output thermal power.

[0053] It should be noted that RPF represents the full reactor power value of the NSSS module.

[0054] For example, the plurality of NSSS modules include a first NSSS module 4-1, a second NSSS module 4-2, a third NSSS module 4-3, a fourth NSSS module 4-4, a fifth NSSS module 4-5, and a sixth NSSS module 4-6. The plurality of NSSS module control system modules include a first NSSS module control system module 5-1, a second NSSS module control system module 5-2, a third NSSS module control system module 5-3, a fourth NSSS module control system module 5-4, a fifth NSSS module control system module 5-5, and a sixth NSSS module control system module 5-6.

[0055] Taking the first NSSS module control system module 5-1 as an example, the first NSSS module control system module 5-1 collects the process data of the first NSSS module 4-1; and within the range of 0-30% RPF, manually increases the reactor power and output thermal power, automatically maintains the reactor power and output thermal power within the power range of 30%-50% RPF, and realizes coordinated control within multiple NSSS modules within the range of 50%-100% RPF, and automatically converts the reactor power and output thermal power; receives the reactor output thermal power set value signal and the shutdown signal from the unit control system module 5-7, and adjusts the feed water regulating valve 4-7, the main helium fan 2 and the reactor control rod according to the reactor output thermal power set value signal to make the reactor output thermal power reach the set value; trips the first NSSS module 4-1 according to the shutdown signal; outputs the operating status signals of the first NSSS module 4-1 such as the reactor output thermal power, reactor power, and trip signal to the unit control system module 5-7. The functions of the second NSSS module control system module 5 - 2 to the sixth NSSS module control system module 5 - 6 are the same as those of the first NSSS module control system module 5 - 1 .

[0056] At least one embodiment of the present application also provides a method for coordinated control of reactor, machine and heat under transient conditions under cogeneration conditions of a multi-module high-temperature gas-cooled reactor, Figure 7 The transient condition reactor, machine and heat coordinated control method under the multi-module high temperature gas-cooled reactor cogeneration condition includes the following steps.

[0057] S1: Determine the types of transient conditions under the multi-module high-temperature gas-cooled reactor cogeneration conditions. The types of multiple transient conditions include NSSS module emergency shutdown transient conditions, main transformer high-voltage side circuit breaker disconnection transient conditions, turbine tripping transient conditions, feedwater pump tripping transient conditions, heating network load shedding transient conditions and heating network rupture transient conditions.

[0058] S2: According to the type of transient operating condition, control is performed using the transient operating condition control device under the multi-module high temperature gas-cooled reactor cogeneration operating condition of the embodiment of the present application.

[0059] In at least one embodiment of the present application, if the type of the transient operating condition is an NSSS module emergency shutdown transient operating condition, then S2.1 to S2.4 are a specific implementation of the above S2.

[0060] S2.1: The unit control system module 5-7 calculates the current effective reactor output total thermal power and the adjustable reactor output thermal power in real time.

[0061] It should be noted that the current effective total thermal power output of the reactor is also the output thermal power that has been loaded. The reactor output thermal power is also the adjustable part of the NSSS module that is put into automatic coordinated control.

[0062] S2.2: Under the transient condition of NSSS module emergency shutdown, for the NSSS modules that are not connected to steam among multiple NSSS modules, the unit control system modules 5-7 do not make a load shedding judgment.

[0063] It should be noted that the NSSS module emergency shutdown transient condition refers to the transient condition when an NSSS module emergency shutdown event occurs.

[0064] S2.3: For other loaded NSSS modules among multiple NSSS modules that trip, the unit control system module 5-7 automatically performs load shedding judgment.

[0065] It should be noted that, in normal operation, multiple NSSS modules are all operating above 50% RPF and are in automatic coordinated control mode. However, in maintenance and startup conditions, some of the multiple NSSS modules are operating above 50% RPF, and other modules of the multiple NSSS modules are in shutdown or startup state. Therefore, at the moment of partial module tripping, the most complex operating conditions of multiple NSSS modules may be: some of the multiple NSSS modules are in the unit coordinated control mode; another part of the multiple NSSS modules have completed steam connection, but are not in the unit coordinated control mode; another part of the multiple NSSS modules have been started and completed partial steam connection; another part of the multiple NSSS modules have been started but not steam connected; other parts of the multiple NSSS modules have not been started. For the NSSS module tripping without steam connection, no load shedding judgment is performed. For the NSSS module tripping with load, the load shedding judgment is automatically performed.

[0066] S2.4: The main water supply pressure control system module 5-10 controls the water supply pump in the pressure control mode to maintain the pressure of the water supply main pipe. According to the total water supply flow and the minimum allowable load of the water supply pump, the corresponding water supply pump is switched to recirculation operation or cut off.

[0067] In at least one embodiment of the present application, S2.3.1 and S2.3.3 are a specific implementation of the above S2.3.

[0068] S2.3.1: The unit control system module 5-7 determines whether the total output thermal power of the operating NSSS module with load is greater than or less than the sum of the heating load and the minimum load of the turbine.

[0069] S2.3.2: If the judgment result is that the total output thermal power of the operating NSSS module with load is greater than the sum of the heating load and the minimum load of the turbine, the heating island control system module 5-11 controls the heating load to operate normally, and the turbine control system module 5-8 controls the turbine to follow the main steam pressure to shed load in the pressure control mode.

[0070] S2.3.2: If the judgment result is that the total output thermal power of the operating NSSS modules is less than the sum of the heating load and the minimum load of the turbine, the turbine control system module 5-8 controls the turbine to follow the main steam pressure load shedding to the minimum long-term operating power under the pressure control mode, and the heating island control system module 5-11 controls to reduce the quality of part of the external steam supply.

[0071] In at least one embodiment of the present application, if the type of transient operating condition is a transient operating condition in which the circuit breaker on the high-voltage side of the main transformer is disconnected, then S2.5 to S2.7 are a specific implementation of the above S2.

[0072] S2.5: Under the transient condition of the main transformer high-voltage side circuit breaker being disconnected, the steam turbine suddenly loses load, and the steam turbine control system module 5-8 controls the steam turbine to switch to load control mode, quickly shedding load to the island operation load, and the main steam pressure control system module 5-9 controls the bypass regulating valve group 4-5 to maintain the pressure of the main steam header and discharge excess steam.

[0073] It should be noted that the transient operating condition of the main transformer high-voltage side circuit breaker disconnection refers to the transient operating condition of the main transformer high-voltage side circuit breaker disconnection event.

[0074] S2.6: The unit control system module 5-7 controls the total thermal power output of the reactor to remain unchanged, and the heating island control system module 5-11 controls the heating load to operate normally.

[0075] S2.7: After the transient state is stabilized, the total thermal power output of the reactor is manually reduced through the unit control system module 5-7 until the bypass regulating valve group 4-15 is closed.

[0076] In at least one embodiment of the present application, if the type of the transient operating condition is a turbine tripping operating condition transient operating condition, then S2.8 to S2.10 are a specific implementation of the above S2.

[0077] S2.8: Under the transient condition of turbine tripping, the main steam pressure control system module 5-9 controls the bypass regulating valve group 4-15 to maintain the pressure of the main steam header and discharge excess steam.

[0078] It should be noted that the transient operating condition of the steam turbine tripping condition refers to the transient operating condition in which a steam turbine tripping event occurs.

[0079] S2.9: The unit control system module 5-10 controls the total thermal power output of the reactor to remain unchanged, and the heating island control system module 5-11 controls the heating load to operate normally.

[0080] S2.10: After the transient state is stabilized, the total thermal power output of the reactor is manually reduced through the unit control system module 5-7 until the bypass regulating valve group 4-15 is closed.

[0081] In at least one embodiment of the present application, if the type of the transient operating condition is a water supply pump tripping condition transient operating condition, then S2.11 to S2.13 are a specific implementation of the above S2.

[0082] S2.11: The unit coordination control system module 5-7 calculates and determines in real time whether the water supply meets the operating requirements of the NSSS module at the current power according to the status of the tripped pump group, the number of water supply pumps in operation and the status of multiple NSSS modules.

[0083] S2.12: Under the transient condition of feedwater pump tripping, the unit control system modules 5-7 make real-time judgments. When the current feedwater flow cannot meet the operating requirements of the NSSS module at the current power, the modules will be tripped in accordance with the preset priority order based on the conditions of the NSSS modules without steam connection, the reactors that have steam connection but are not in the unit coordinated control mode, and the reactors that have been put into the unit coordinated control mode, to ensure the maximum stable output of heat supply under the available feedwater flow.

[0084] It should be noted that the transient condition of the water supply pump tripping condition refers to the transient condition of the main water supply pump tripping event. The preset priority order can be preset and adjusted by the operator according to the actual situation.

[0085] At the moment when the feedwater pump trips, the most complex operating conditions that may exist in multiple NSSS modules are: some NSSS modules are in the unit coordinated control mode; some of the multiple NSSS modules have completed steam connection, but are not in the unit coordinated control mode; another part of the multiple NSSS modules have been started and completed partial steam connection; another part of the multiple NSSS modules have been started but have not been connected to steam; and other parts of the multiple NSSS modules have not been started.

[0086] S2.13: The steam turbine control system module 5-8 controls the steam turbine to follow the main steam pressure load shedding to the minimum long-term operating power in the pressure control mode. The heating island control system module 5-11 controls the shedding of part of the external steam or reduces the quality of part of the external steam.

[0087] It should be noted that the heat island control system module 5-11 controls to discard part of the external steam or reduce the quality of part of the external steam, so as to ensure that the steam turbine works at the lowest long-term operating power.

[0088] In at least one embodiment of the present application, if the type of transient operating condition is a transient operating condition of heat network load rejection, then S2.14 to S2.16 are a specific implementation of the above S2. It should be noted that when the heat supply network rejects the heat load, the pressure of the heating pipeline increases rapidly. By monitoring the two signals of pressure change and rising rate, according to the state of the total load of the secondary circuit, the heating load, and the turbine load, the stack, machine, and heat coordinated control process is described as follows S2.14 to S2.16.

[0089] S2.14: Under the transient condition of heat network load shedding, when the heat network load shedding occurs, the pressure of the heating pipeline increases rapidly to reduce the required secondary circuit steam. The heating island control system module 5-11 controls the stable operation of the external steam supply.

[0090] S2.15: The unit control system module 5-7 controls the reactor to output a constant total thermal power, and the steam turbine control system module 5-8 controls the steam turbine main regulating valve 4-13 to maintain the pressure of the main steam header, and increases the load of the steam turbine within the adjustable range to absorb the excess steam in the secondary circuit. When the steam turbine power rises to full load, it switches to the fixed load operation mode, and the main steam pressure control system module 5-9 controls the bypass regulating valve group 4-15 to adjust the pressure of the main steam turbine header.

[0091] S2.16: After the transient state is stabilized, the total thermal power output of the reactor is manually reduced through the unit control system module 5-7 until the bypass regulating valve group 4-15 is closed.

[0092] In at least one embodiment of the present application, if the type of transient operating condition is a heating network rupture transient operating condition, then S2.17 to S2.20 are a specific implementation of the above S2.

[0093] S2.17: Under the transient condition of heat network rupture, the heating island control system module 5-11 comprehensively judges the occurrence of rupture based on the monitored pressure change and drop rate signals, and the pneumatic fast shut-off valve of the ruptured heating pipeline is closed before leaving the factory.

[0094] It should be noted that the transient condition of heat network rupture refers to a transient condition in which an external pipeline ruptures and the pressure in the pipeline drops rapidly.

[0095] S2.18: At the initial stage of the rupture, the heating load rises rapidly, and the heating island control system module 5-11 controls the heating regulating valve 4-19 to open and the turbine control system module 5-8 controls the main steam regulating valve 4-13 to close for follow-up response.

[0096] S2.19: During the transient period, the heating island control system module 5-11 limits the flow increase rate and the total heating flow on the heating station side according to the external pipeline rupture condition.

[0097] It should be noted that, through step S2.19, the stability during the transient period is maintained, and the short-term rapid opening of the heating regulating valve 4-19 is avoided, which causes system instability.

[0098] S2.20: After the transient state is stabilized, the total thermal power output of the reactor is manually reduced through the unit control system module 5-7 until the bypass regulating valve group 4-15 is closed.

[0099] According to the technical solution provided in the embodiment of the present application, by coordinating and controlling the reactor power, turbine load and heating load under transient conditions, the risk of coupled control oscillation caused by simultaneous regulation of the reactor, turbine and heating is avoided, and the heating demand is met first on the premise of ensuring nuclear safety and stable operation of the NSSS module, ensuring the safe, stable and reliable operation of the entire heating system. In addition, on the premise of ensuring nuclear safety, heating is given priority, and the remaining heat is used for power generation, ensuring the safe, stable and reliable operation of the entire heating system under various conditions, and trying to avoid simultaneous control of the reactor, machine and heat, mutual influence, and the introduction of unstable factors.

[0100] It should be noted that the combination of the various technical features in the embodiments of the present application is not limited to the combination described in the embodiments of the present application or the combination described in the specific embodiments, and all technical features described in the present application can be freely combined or combined in any way unless there is a contradiction between them.

[0101] The above description is only a preferred embodiment of the present application and is not intended to limit the present application. Any modifications, equivalent substitutions, etc. made within the spirit and principles of the present application shall be included in the protection scope of the present application.

Claims

1. A transient operating condition control device for a multi-module high temperature gas-cooled reactor cogeneration condition, characterized in that: It includes multiple NSSS module control system modules, unit control system modules, turbine control system modules, main steam pressure control system modules, main feed water pressure control system modules and heating station control system modules. Among them, the multiple NSSS module control system modules are used to respectively control the operation of multiple NSSS modules in the multi-module high-temperature gas-cooled reactor, and output the operation status signals of the multiple NSSS modules to the unit control system module; The steam turbine control system module is used to control the protection and operation of the steam turbine under multiple transient operating conditions according to the signals received from the unit control system module; The main steam pressure control system module is used to control the bypass regulating valve group to adjust the pressure of the main steam header to the set value under transient conditions when the steam turbine trips or the main steam pressure cannot be adjusted; The water supply pressure control module is used to control the steam flow outside the heating island under multiple transient conditions, and to maintain the pressure and temperature parameters of the external steam supply to meet the set requirements, monitor the rupture of the heating pipe network and maintain the stability of the heating load, so as to get rid of part of the heating load or isolate the heating pipeline; the heating station control system module is used to control the heating station; The unit control system module is used to automatically distribute the reactor output thermal power setting values ​​of multiple NSSS modules according to a preset strategy, to automatically distribute the reactor output thermal power setting values ​​or output shutdown signals to multiple NSSS module control system modules under multiple transient conditions, to send a load rejection or shutdown signal to the turbine control system module, to send a main steam pressure control switching signal to the main steam pressure control system, and to send a regulation or pump stop signal to the feed water pressure control module; The unit control system module is used to perform multiple transient operating condition controls based on the multiple signal parameters output by multiple NSSS module control system modules, turbine control system modules, main steam pressure control system modules, main feed water pressure control system modules and heating station control system modules.

2. The transient operating condition control device for a multi-module high temperature gas-cooled reactor cogeneration system according to claim 1, characterized in that: The NSSS module control system module includes a first acquisition submodule, a first receiving submodule, a regulating submodule, a tripping submodule and a first output submodule. The first acquisition submodule is used to collect the process parameters of the corresponding NSSS module, the first receiving submodule is used to receive the reactor output thermal power set value signal and the shutdown signal from the unit control system module, the adjustment submodule is used to adjust the corresponding NSSS module feed water regulating valve, main helium fan and reactor control rod according to the reactor output thermal power set value signal so that the reactor output thermal power reaches the set value; the trip submodule is used to trip the corresponding NSSS module according to the shutdown signal; the first output submodule is used to output the operating status signal of the corresponding NSSS module to the unit control system module.

3. A transient operating condition control device for a multi-module high temperature gas-cooled reactor cogeneration operating condition according to claim 1 or 2, characterized in that: The NSSS module control system module also includes a power control submodule. The power control submodule is used to manually increase the reactor power and output thermal power within the RPF range of 0% to 30%, automatically maintain the reactor power and output thermal power within the RPF power range of 30% to 50%, and realize coordinated control within multiple NSSS modules and automatic conversion of reactor power and output thermal power within the RPF range of 50% to 100%.

4. A method for coordinated control of reactor, machine and heat in transient conditions under cogeneration conditions of a multi-module high temperature gas-cooled reactor, characterized in that: include: Determine the types of transient conditions under the multi-module high-temperature gas-cooled reactor cogeneration conditions. The types of multiple transient conditions include NSSS module emergency shutdown transient conditions, main transformer high-voltage side circuit breaker disconnection transient conditions, turbine tripping transient conditions, feedwater pump tripping transient conditions, heating network load shedding transient conditions and heating network rupture transient conditions; According to the type of transient operating condition, control is performed using the transient operating condition control device under the multi-module high temperature gas-cooled reactor cogeneration operating condition as described in any one of claims 1 to 3.

5. The method for coordinated control of reactor, machine and heat in transient condition under cogeneration condition of multi-module high temperature gas-cooled reactor according to claim 4, characterized in that: According to the type of transient operating condition, the transient operating condition control device under the multi-module high temperature gas-cooled reactor cogeneration operating condition according to any one of claims 1 to 3 is used for control, including: The unit control system module calculates the current effective reactor total thermal output power and the adjustable reactor thermal output power in real time; Under the transient condition of NSSS module emergency shutdown, for the NSSS modules that are not connected to steam in multiple NSSS modules, the unit control system module does not make a load shedding judgment; If other NSSS modules with load among multiple NSSS modules trip, the unit control system module automatically makes a load shedding judgment; The main water supply pressure control system module controls the water supply pump in the pressure control mode to maintain the pressure of the water supply main pipe. According to the total water supply flow and the minimum allowable load of the water supply pump, the corresponding water supply pump is switched to recirculation operation or cut off.

6. The method for coordinated control of reactor, machine and heat in transient condition under cogeneration condition of multi-module high temperature gas-cooled reactor according to claim 4, characterized in that: According to the type of transient operating condition, the transient operating condition control device under the multi-module high temperature gas-cooled reactor cogeneration operating condition according to any one of claims 1 to 3 is used for control, including: Under the transient condition of the main transformer high-voltage side circuit breaker disconnecting, the steam turbine suddenly loses load, and the steam turbine control system module controls the steam turbine to switch to the load control mode, quickly shedding the load to the island operation load, and the main steam pressure control system module controls the bypass regulating valve group to maintain the pressure of the main steam header and discharge excess steam; The unit control system module controls the total thermal power output of the reactor to remain constant, and the heating island control system module controls the heating load to operate normally; After the transient state stabilizes, the total thermal power output of the reactor is manually reduced through the unit control system module until the bypass regulating valve is closed.

7. The method for coordinated control of reactor, machine and heat in transient condition under cogeneration condition of multi-module high temperature gas-cooled reactor according to claim 4, characterized in that: According to the type of transient operating condition, the transient operating condition control device under the multi-module high temperature gas-cooled reactor cogeneration operating condition according to any one of claims 1 to 3 is used for control, including: Under transient conditions of turbine tripping, the main steam pressure control system module controls the bypass regulating valve group to maintain the pressure of the main steam header and discharge excess steam; The unit control system module controls the total thermal power output of the reactor to remain constant, and the heating island control system module controls the heating load to operate normally; After the transient state stabilizes, the total thermal power output of the reactor is manually reduced through the unit control system module until the bypass regulating valve is closed.

8. The method for coordinated control of reactor, machine and heat in transient condition under cogeneration condition of multi-module high temperature gas-cooled reactor according to claim 4, characterized in that: According to the type of transient operating condition, the transient operating condition control device under the multi-module high temperature gas-cooled reactor cogeneration operating condition according to any one of claims 1 to 3 is used for control, including: The unit coordination control system module calculates and determines in real time whether the water supply volume meets the operating requirements of the NSSS module at the current power according to the status of the tripped pump group, the number of water supply pumps in operation and the status of multiple NSSS modules; Under the transient working condition of feedwater pump tripping, the unit control system module makes a real-time judgment. When the current feedwater flow cannot meet the operating requirements of the NSSS module at the current power, the unit control system module will trip the reactor in the preset priority order according to the conditions of the NSSS module without steam connection, the reactor with steam connection but not in the unit coordinated control mode, and the reactor in the unit coordinated control mode, so as to ensure the maximum stable output of heat supply under the available feedwater flow; In the pressure control mode, the steam turbine control system module controls the steam turbine to follow the main steam pressure load shedding to the minimum long-term operating power, and the heating island control system module controls the shedding of part of the external steam or reduces the quality of part of the external steam.

9. The method for coordinated control of reactor, machine and heat in transient condition under cogeneration condition of multi-module high temperature gas-cooled reactor according to claim 4, characterized in that: According to the type of transient operating condition, the transient operating condition control device under the multi-module high temperature gas-cooled reactor cogeneration operating condition according to any one of claims 1 to 3 is used for control, including: Under the transient condition of heat network load shedding, when the heat network load shedding occurs, the pressure of the heating pipeline increases rapidly to reduce the required secondary circuit steam, and the heating island control system module controls the stable operation of the external steam supply; The unit control system module controls the reactor to output a constant total thermal power. The steam turbine control system module controls the steam turbine main regulating valve to maintain the pressure of the main steam header. Within the adjustable range, the load of the steam turbine is increased to absorb the excess steam in the secondary circuit. When the steam turbine power reaches full load, it switches to the fixed load operation mode. The main steam pressure control system module controls the bypass regulating valve group to adjust the pressure of the main steam turbine header. After the transient state stabilizes, the total thermal power output of the reactor is manually reduced through the unit control system module until the bypass regulating valve is closed.

10. The method for coordinated control of reactor, machine and heat in transient condition under cogeneration condition of multi-module high temperature gas-cooled reactor according to claim 4, characterized in that: According to the type of transient operating condition, the transient operating condition control device under the multi-module high temperature gas-cooled reactor cogeneration operating condition according to any one of claims 1 to 3 is used for control, including: Under the transient condition of heat network rupture, the heating island control system module comprehensively judges the occurrence of rupture based on the monitored pressure change and drop rate signals, and the pneumatic fast shut-off valve before the ruptured heating pipeline leaves the factory is closed; At the initial stage of the rupture, the heating load increases rapidly, and the heating island control system module controls the heating regulating valve to open wide and the steam turbine control system module controls the main steam regulating valve to close narrowly for follow-up response; During the transient period, the heating island control system module limits the flow increase rate and the total heating flow at the heating station side according to the external pipeline rupture condition; After the transient state stabilizes, the total thermal power output of the reactor is manually reduced through the unit control system module until the bypass regulating valve is closed.

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