Nuclear energy heat and power supply system

Abstract

This invention relates to a nuclear power thermoelectric heating system, comprising: at least one nuclear power heating device, the nuclear power heating device including at least one steam supply system, the steam supply system having a steam outlet and a water inlet; a steam distribution device, connected to the steam outlet and the load, allowing steam to enter the load; a feedwater distribution device, connected to the load and the water inlet, allowing the cooling heating medium within the load to flow to the steam supply system via the feedwater distribution device; and a control system, which acquires load level signals from the nuclear power heating device, the steam distribution device, and the load, and adjusts the nuclear power heating device, the steam distribution device, and the load level according to the acquired load level signals. This invention enables completely decoupled control between the reactor side and the thermal load side, achieving mutual adjustment between loads without reactor adjustments, minimizing reactor adjustments while maximizing load adjustments for flexible operation combinations, and optimizing the load level combinations of various loads without reactor adjustments, thus achieving optimal operational economy.

Description

Technical Field

[0001] This invention relates to the field of nuclear power, and more specifically, to a nuclear thermoelectric heating system. Background Technology

[0002] The domestic nuclear power industry widely adopts unit reactor configuration, that is, the reactor and the steam turbine are in a one-to-one relationship and form a unit. With the development of nuclear energy at home and abroad, the demand for nuclear reactors to be used for combined heat and power in various application scenarios is becoming increasingly prominent. In addition to pure power generation, nuclear reactors can also supply steam for industrial heating, residential heating, cooling, seawater desalination and other extended applications. Different application scenarios have different types and sizes of loads. The same reactor or several reactors can simultaneously supply steam for steam turbine power generation and for industrial heating, residential heating, cooling, seawater desalination and so on.

[0003] Steam turbines can be single units or multiple units (two or more). Steam can be supplied at one pressure or at several pressures simultaneously. Heat can be supplied using fresh steam or extracted steam from the turbine. Therefore, in the case of combined heat and power (CHP), it is rare to achieve a one-to-one correspondence between the number of reactors and the number of loads. Instead, there are situations where multiple reactors or a single reactor simultaneously supply steam to support the load. The types of loads supported include pure power generation turbines, extraction steam turbines for heating, heat exchangers, etc. The types of loads supported by the reactor can be one of these types or a combination of some or all of them. The number of loads supported by the reactor can be one or more.

[0004] For ease of description, we will refer to the combination of reactor, turbine, and heater as a multi-reactor, multi-heater configuration. In this configuration, achieving coordinated control of reactor, turbine, and heater functions is a challenge that cannot be addressed using the unit-based reactor-turbine coordination control technology common in the nuclear power industry.

[0005] In the nuclear energy industry, besides unit-type nuclear power units, the only type of reactor that has been put into operation and partially meets the characteristics of multiple reactors, multiple turbines, and multiple thermal systems is the high-temperature gas-cooled reactor (HTGR). This reactor type uses two reactors with one turbine for power generation, solving the coordination and control problems caused by sharing feedwater and steam headers when two nuclear reactors are connected to one turbine. However, the HTGR with two reactors and one turbine is only a very special scenario within the multiple reactor, multiple turbine, and multiple thermal system configuration. It lacks universality and cannot solve the connection problems and reactor-turbine thermal coordination and control problems in various application scenarios of multiple reactors, multiple turbines, and multiple thermal systems. Summary of the Invention

[0006] The technical problem to be solved by the present invention is to provide an improved nuclear thermoelectric heating system in view of the above-mentioned defects of the prior art.

[0007] The technical solution adopted by this invention to solve its technical problem is: constructing a nuclear energy thermoelectric heating system, comprising:

[0008] At least one nuclear heating device, the nuclear heating device including at least one steam supply system, the steam supply system having a steam outlet and a water inlet;

[0009] A steam distribution device connects the steam outlet and the load, allowing steam to enter the load;

[0010] A water distribution device, connecting the load and the water inlet, allows the cooled heating medium within the load to flow through the water distribution device to the steam supply system; and

[0011] The control system collects load level signals from the nuclear heating device, steam distribution device, and load, and adjusts the nuclear heating device, steam distribution device, and load level according to the collected load level signals.

[0012] In some embodiments, the steam supply system includes a reactor, which has at least two evaporators, each of which is provided with a steam outlet and a water inlet.

[0013] In some embodiments, the steam supply system further includes a steam header, with the steam outlet of each of the evaporators connected to the steam header, and the steam header connected to the steam distribution device via at least one connecting pipe.

[0014] In some embodiments, a steam pipe is connected between the steam outlet of each evaporator and the steam distribution device, and the steam header is located between the steam outlet and the steam distribution device and connects to each of the steam pipes.

[0015] In some embodiments, the steam supply system further includes a water supply manifold connected to the water inlet of each of the evaporators, and the water supply distribution device.

[0016] In some embodiments, a water pump is further provided between the water distribution device and the water header.

[0017] In some embodiments, the nuclear heating device further includes a reactor control module communicatively connected to the control system, which receives adjustment signals from the control system to adjust the reactor power level, collects feedwater flow information in the internal loop of the steam supply system in real time, and controls the flow of feedwater from the feedwater distribution device to the reactor according to the changes in feedwater flow.

[0018] In some embodiments, the steam distribution device includes a steam distribution header connected to loads, and the feedwater distribution device includes a feedwater header connected to the reactor.

[0019] In some embodiments, the load includes a load unit and a control unit, wherein the load unit is connected to the steam distribution device and the water supply distribution device, respectively;

[0020] The control unit is communicatively connected to the control system to receive adjustment signals from the control system, adjust the load level of the load unit, collect load level information of the load unit in real time, and control the load level of the load unit according to the changes in the load level.

[0021] In some embodiments, each load unit includes at least one of a steam turbine, a condenser, a heat exchanger, and a condensate feedwater system.

[0022] The nuclear thermal power heating system of the present invention has the following beneficial effects: The present invention can achieve complete decoupling control between the reactor side and the mechanical and thermal load side, which creates conditions for mutual adjustment between loads without reactor adjustment, and also creates conditions for flexible operation combinations by adjusting loads as much as possible with minimal reactor adjustment, and also creates conditions for optimizing the load level combination of each load without reactor adjustment, thereby achieving optimal operation economy. Attached Figure Description

[0023] The present invention will be further described below with reference to the accompanying drawings and embodiments. In the accompanying drawings:

[0024] Figure 1 This is a schematic diagram of the structural principle of the nuclear energy thermoelectric heating system in an embodiment of the present invention;

[0025] Figure 2 yes Figure 1 Schematic diagram of the structural principle of the heating device of China National Nuclear Corporation;

[0026] Figure 3 yes Figure 1 A schematic diagram showing the connection between the heating unit of China Nuclear Energy and the steam distribution unit via connecting pipes;

[0027] Figure 4 yes Figure 1 A schematic diagram showing the connection between the steam outlet of the CNNC heating unit and the steam distribution unit via a steam pipe.

[0028] Figure 5 yes Figure 1 A schematic diagram showing the connection between the steam outlet and the steam distribution unit after the steam manifold is removed from the heating unit of China Nuclear Energy.

[0029] Figure 6This is a schematic diagram showing the connection of four loads;

[0030] Figures 7 to 10 They are Figure 6 A schematic diagram of the four loads arranged from top to bottom. Detailed Implementation

[0031] To provide a clearer understanding of the technical features, objectives, and effects of the present invention, specific embodiments of the present invention will now be described in detail with reference to the accompanying drawings.

[0032] like Figures 1 to 3 As shown, a nuclear thermal power heating system in a preferred embodiment of the present invention includes a nuclear heating device 10, a steam distribution device 20, a water supply distribution device 30, and a control system 40. The number of nuclear heating devices 10 is two, or there may be one or more.

[0033] Each nuclear heating unit 10 includes a steam supply system 11 and a reactor control module 12. The steam supply system 11 includes a reactor 111, a steam header 112, a feedwater header 113, and a feedwater pump 114. Further, the reactor 111 is equipped with two evaporators 1111. Each evaporator 1111 is provided with a steam outlet A and a water inlet B. The steam outlet A is connected to the steam distribution device 20 via the steam header 112 to distribute the steam to the load 50. After being cooled in the load 50, the steam becomes liquid and flows to the feedwater distribution device 30.

[0034] The feedwater header 113 is connected to the inlet B of each evaporator 1111 and the feedwater distribution device 30. A feedwater pump 114 is also provided between the feedwater distribution device 30 and the feedwater header 113. The feedwater pump 114 pumps the liquid heating medium from the feedwater distribution device 30 to the feedwater header 113. The feedwater header 113 is connected to the inlet B and is transported to the evaporator 1111 of the reactor 111 through the inlet B. The evaporator 1111 heats the incoming liquid heating medium, turns it into steam, and flows out from the steam outlet A. This cycle continues.

[0035] The reactor control module 12 is communicatively connected to the control system 40 to receive adjustment signals from the control system 40 to adjust the reactor power level, and to collect feedwater flow information in the inner loop of the steam supply system 11 in real time, and control the flow of feedwater distribution device 30 to reactor 111 according to the changes in feedwater flow.

[0036] In some embodiments, the steam outlet A of each evaporator 1111 is connected to a steam header 112, and the steam header 112 is connected to a steam distribution device 20 through a connecting pipe 115. The number of connecting pipes 115 between the steam header 112 and the steam distribution device 20 can be one or more.

[0037] Furthermore, such as Figure 4 As shown, in other embodiments, a steam pipe 116 can also be connected between the steam outlet A of each evaporator 1111 and the steam distribution device 20. A steam header 112 is located between the steam outlet A and the steam distribution device 20 and connects to each steam pipe 116, allowing steam to flow and mix within the steam header 112 as it flows towards the steam distribution device 20. It can be understood that, as Figure 5 As shown, the steam header 112 can also be removed, allowing the steam outlet A to be directly connected to the steam distribution device 20. The steam distribution device 20 is connected to the load 50 via a pipe, and the position of the pipe on the steam distribution device 20 is not limited.

[0038] Combination Figures 6 to 10 As shown, in some embodiments, the load 50 includes a load unit 51 and a control unit 52. The load unit 51 is connected to the steam distribution device 20 and the water supply distribution device 30, respectively, so that steam enters the load unit 51, cools, and becomes liquid before flowing to the water supply distribution device 30. Furthermore, the control unit 52 is communicatively connected to the control system 40 to receive adjustment signals from the control system 40, adjust the load level of the load unit 51, and collect load level information within the load unit 51 in real time, controlling the load level of the load unit 51 according to changes in load level. Of course, some loads 50 may not have a control unit 52 and can be controlled by the control units 52 of other loads 50.

[0039] In some embodiments, load unit 51 includes a steam turbine 511, a condenser 512, a heat exchanger 513, and a condensate feedwater system 514. Each load unit 51 includes at least one of the following: steam turbine 511, condenser 512, heat exchanger 513, and condensate feedwater system 514. In this embodiment, each load unit 51 can be a combination of the above components, such as... Figures 6 to 10 As shown, in order are Figure 5 The system comprises four load units 51 arranged from top to bottom. Furthermore, each load unit 51 includes at least one steam inlet, and the condensate feedwater system 514 is equipped with a deaerator.

[0040] The steam distribution unit 20 includes a steam distribution header, which is connected to the load 50. The feedwater distribution unit 30 includes a feedwater header, which is connected to the reactor 111. Typically, after the liquid heating medium flows into the feedwater distribution unit 30, it is transported to the feedwater header 113 by the feedwater pump 114, and then to the reactor 111.

[0041] The reactor control module 12 connects to the reactor power control rod regulation system inside the reactor 111, changing the output thermal power of the reactor 111, which in turn causes changes in the output parameters of the evaporator 1111. This is the path through which the reactor 111 executes the power regulation command. The reactor control module 12 receives the reactor 111 power regulation shielding command from the control system 40 and transmits the shielding command to the reactor power control rod regulation system inside the reactor 111, causing it to maintain its current operating state and remain inactive. This is the path through which the reactor 111 executes the shielding command.

[0042] When the output steam parameters of evaporator 1111 change, the flow signals of steam outlet A and water inlet B are sent to the stack control module 12 for automatic difference calculation. Based on the difference calculation result, the stack control system then sends a flow adjustment command to feedwater pump 114. This is the path for feedwater pump 114 to adjust the flow to maintain the flow balance of evaporator 1111.

[0043] When the output steam parameters of evaporator 1111 change, the pressure change of steam header 112 is detected and the pressure signal is sent to stack control module 12 for comparison with the set pressure. After program calculation, the adjustment signal is output to control the flow rate of inlet B. This is the path to adjust the feedwater regulating valve to keep the outlet pressure of evaporator 1111 stable.

[0044] When the power control rods of reactor 111 are adjusted, the reactor power measurement system of reactor 111 measures the instantaneous reactor power based on the neutron flux and outputs the instantaneous reactor power level of reactor 111 to the reactor control module 12. This is the feedback path of the instantaneous reactor power of reactor 111.

[0045] When the steam output parameters of evaporator 1111 change, the flow signal from inlet B is transmitted to the reactor control system. This flow signal represents the real-time total load level of the secondary loop and is compared with the real-time reactor power signal of reactor 111. If the difference exceeds the control requirement range, reactor 111 is allowed to execute the reactor power regulation command path; otherwise, the execution of the reactor power regulation command path of reactor 111 is stopped. This is the feedback real-time total load level path.

[0046] The valve position signal of the regulating valve at inlet B is transmitted to the stack control module 12 for program control. This is the valve position feedback path of the feedwater regulating valve.

[0047] The operating status signal (including speed signal) of the feedwater pump 114 is transmitted to the reactor control module 12 for program control. This is the operating status feedback path of the feedwater pump 114.

[0048] exist Figure 7In this process, control unit 52 receives control signals from control system 40 and issues action commands to the turbine's inlet regulating valve for adjustment. The valve position information of the turbine's inlet regulating valve is fed back to control unit 52, which then feeds back the overall control status signal of the turbine to control system 40. Control unit 52 receives load 50 adjustment shielding commands from control system 40, causing load unit 51 to maintain its current load level and operating state without operation.

[0049] exist Figure 8 In the process, for load unit 51, condensate enters the steam side of condenser 512, which is where load unit 51 receives... Figure 9 The path of condensate in medium-load unit 51.

[0050] The load controller receives control signals and sends adjustment commands to the turbine's inlet regulating valve. Figure 9 The medium-load unit 51 issues an adjustment action command, which is Figure 8 The medium load unit 51 receives the adjustment signal path.

[0051] The valve position information of the turbine inlet regulating valve is fed back to the control unit 52. Figure 9 The feedback signal from the load unit 51 is transmitted to the control unit 52. The control unit 52 receives a load 50 adjustment and shielding command from the control system 40, causing the load unit 51 and... Figure 9 The medium load unit 51 remains inactive, maintaining its current load level and operating status.

[0052] exist Figure 9 In the process, for load unit 51, the heating steam is discharged to the feedwater distribution device 30 after passing through the heating heat exchanger 513, and the steam inlet regulating valve receives steam from the feedwater distribution device 30. Figure 8 The control unit 52 of the medium-load unit 51 sends the adjustment action command and the valve position status signal of the steam inlet regulating valve to the control unit 52. Figure 8 Control unit 52 of medium load unit 51.

[0053] exist Figure 10 In the process, for load unit 51, heating steam is discharged to the feedwater distribution device 30 after passing through the heating heat exchanger 513. The control unit 52 receives the adjustment action command from the control system 40 and sends the adjustment action command to the steam inlet regulating valve of the heating heat exchanger 513 for adjustment. The valve position status signal of the steam inlet regulating valve is sent to the control unit 52, and the control unit 52 then sends the overall control status information to the control system 40. The control unit 52 receives the load 50 adjustment shielding command from the control system 40, so that the load unit 51 maintains the current load level and operating state without action.

[0054] The control system 40 receives pressure signals from the pressure gauge on the steam distribution unit 20, feedback signals from the load 50, and feedback signals from the nuclear heating unit 10. This is the signal feedback path for the pressure controller.

[0055] The control system 40, through program control, outputs load 50 adjustment commands and load unit 51 shielding commands, and outputs nuclear reactor power adjustment commands and reactor control shielding commands to the nuclear heating device 10. This is the control signal path of the pressure controller control output.

[0056] The basic control methods for nuclear cogeneration heating systems include:

[0057] 1. "Load-Bus-Load" Control Mode

[0058] This is a load self-regulation mode.

[0059] A slight change in a load unit 51 will cause a slight change in the pressure of the steam distribution header. The control system 40 will receive the pressure change signal of the steam distribution device 20, the real-time power level signal of each nuclear reactor, the total load level signal, and the load level signal of each load unit 51.

[0060] After analyzing these signals, the control system 40 determines to use the "load-bus-load" control mode to output adjustment signals and shielding signals. The control system 40 sends load level adjustment signals to the load units 51 that need to be adjusted first and sends shielding signals to other load units 51. During the adjustment process, the control system 40 receives feedback signals of bus pressure change, real-time power level feedback signals of each nuclear reactor, total load level feedback signals, and load level feedback signals of each load unit 51.

[0061] Repeated adjustments until convergence is achieved, completing the adjustment process.

[0062] During the above adjustment process, before outputting the load level adjustment command, the control system 40 needs to prioritize selecting the load unit 51 to be adjusted according to the program settings. Throughout the adjustment process, to achieve stability as quickly as possible, the program prioritizes selecting one load unit 51 to respond to the adjustment in one adjustment cycle. If the risk of control divergence is low, multiple load units 51 can also respond to the adjustment simultaneously, which can be set by the operator.

[0063] 2. "Nuclear Reactor-Host-Load" Control Mode

[0064] This is the reactor power adjustment mode that follows the load level.

[0065] If a significant change occurs in a certain load unit 51, it will cause a significant change in the steam distribution header pressure. The control system 40 will receive the header pressure change signal, the real-time power level signal of each nuclear reactor, the total load level signal, and the load level signal of each load unit 51.

[0066] After program analysis, the control system 40 determines to adopt the "nuclear reactor-host-load" control mode and outputs adjustment signals and shielding signals. The control system 40 sends power level adjustment signals to the nuclear reactor control system that needs to be adjusted first and sends shielding signals to other nuclear reactor control systems to start the adjustment process. The control system 40 receives the host pressure change feedback signal, the real-time power level feedback signal of each nuclear reactor, the total load level feedback signal, and the load level feedback signal of each load unit 51.

[0067] Repeated adjustments until convergence is achieved, completing the adjustment process.

[0068] During the above adjustment process, before outputting the nuclear reactor power level adjustment command, the control system 40 needs to prioritize selecting the nuclear heating device 10 to be adjusted according to the program settings. To achieve stability as quickly as possible during the adjustment process, the program prioritizes selecting one nuclear heating device 10 to respond to the adjustment. If the risk of control divergence is low, multiple nuclear heating devices 10 can also respond to the adjustment simultaneously, and this can be set by the operator.

[0069] Under load regulation, the control program of the control system 40 prioritizes the use of the "reactor-head pipe-load" control mode to achieve a rapid response to rapid and large-amplitude fluctuations in the head pipe pressure. After the basic stabilization, there are still small-amplitude fluctuations in the steam distribution head pipe pressure with a large lag. In response, the "load-head pipe-load" control mode is used to respond to the small fluctuations in the steam distribution head pipe pressure. The load level of the load unit 51 is adjusted to mitigate or even eliminate the impact of the large-amplitude fluctuations in the steam distribution head pipe pressure caused by the rapid changes in the load 50.

[0070] 3. "Nuclear Reactor-Mother Tube-Nuclear Reactor" Control Mode

[0071] This is the nuclear reactor intermodulation adjustment mode.

[0072] In extremely special operating conditions, it may be necessary to adjust the power levels of the two nuclear heating units while maintaining a constant load level.

[0073] In this situation, if the operator manually changes the power level of a nuclear heating unit 10, it will cause a change in the steam distribution header pressure. The control system 40 will receive the header pressure change signal, the real-time power level signal of each nuclear reactor, the total load level signal, and the load level signal of each load unit 51.

[0074] After program analysis, the control system 40 determines to adopt the "nuclear reactor-header-nuclear reactor" control mode and outputs adjustment and shielding signals. The control system 40 sends power level adjustment signals to other nuclear reactor control systems that need adjustment and sends shielding signals to other nuclear heating devices 10. The adjustment process begins, and the control system 40 receives header pressure change feedback signals, real-time power level feedback signals from each nuclear reactor, total unit load level feedback signals from load 50, and load level feedback signals from each load unit 51.

[0075] Repeated adjustments until convergence is achieved, completing the adjustment process.

[0076] During the above adjustment process, before outputting the nuclear reactor power level adjustment command, the control system 40 needs to prioritize selecting the nuclear heating device 10 to be adjusted according to the program settings. To achieve stability as quickly as possible during the adjustment process, the program prioritizes selecting one nuclear heating device 10 to respond to the adjustment. If the risk of control divergence is low, multiple nuclear heating devices 10 can also respond to the adjustment simultaneously, and this can be set by the operator.

[0077] 4. "Load-Host-Reactor" Control Mode

[0078] This is a method of adjusting the load level in accordance with the reactor power.

[0079] In this situation, the power level of a nuclear heating unit 10 will be changed through manual operation by the operator or protection action of the reactor control system, which will cause a change in the pressure of the steam distribution header. The control system 40 will receive the header pressure change signal, the real-time power level signal of each nuclear reactor, the load level signal of the total unit of load 50, and the load level signal of each load unit 51.

[0080] After program analysis, the control system 40 determines to adopt the "load-host-reaction" control mode and outputs adjustment and shielding signals. The control system 40 sends load level adjustment signals to the load unit 51 that is prioritized for adjustment and sends shielding signals to other load units 51 to start the adjustment process. The control system 40 receives the host pressure change feedback signal, the instantaneous power level feedback signal of each nuclear reactor, the total load level feedback signal, and the load level feedback signal of each load unit 51.

[0081] Repeated adjustments until convergence is achieved, completing the adjustment process.

[0082] During the above adjustment process, before issuing a load level adjustment command, the control system 40 needs to prioritize selecting the load unit 51 to be adjusted according to the program settings. To achieve stability as quickly as possible during the entire adjustment process, the program prioritizes selecting one load unit 51 to respond to the adjustment. If the risk of control divergence is low, multiple load units 51 can also respond to the adjustment simultaneously, which can be set by the operator.

[0083] 5. Load Trip Mode

[0084] In the load skipping mode, the bypass discharge system of each load unit 51 needs to participate in the regulation of the steam distribution header pressure, otherwise the same as the "nuclear reactor-header-load" control mode.

[0085] 6. Skip-heap mode

[0086] In the hop-reactor mode, the control system 40 needs to calculate and determine the load unit 51 of the load 50 to be shed and the total amount of the load shedding level through program calculation. Other aspects are the same as in the "load-management-reactor" control mode.

[0087] This invention enables complete decoupled control between the reactor side and the thermal load side, which creates conditions for mutual adjustment between loads without reactor adjustment, and also creates conditions for flexible operation combinations by adjusting loads as much as possible with minimal reactor adjustment. Furthermore, it creates conditions for optimizing the load level combination of each load without reactor adjustment, thereby achieving optimal operation economy.

[0088] In cases where the main steam pressure experiences significant residual lag and fluctuations due to load changes, this invention can mitigate pressure fluctuations by coordinating with the reactor on the thermal load side.

[0089] The reactor control modules of this invention can respond to changes in total mechanical and thermal load and transient changes in an orderly and rapid manner by calculating the priority order of output in real time through the program, thereby avoiding the problem of "load competition" between reactors and solving the control divergence problem caused by the different response characteristics of each reactor loop.

[0090] This invention proposes a universal connection method for multiple reactors, multiple machines, and multiple heat sources, as well as a technical solution for achieving reactor-machine thermal coordination control based on these connection methods. The reactor-machine thermal coordination control solution can provide a clear underlying logic and a flexible basis for realizing engineering design.

[0091] This invention proposes a method to achieve complete decoupled control between the reactor side and the thermal load side without reactor adjustment. This creates conditions for mutual adjustment between loads without reactor adjustment, and also creates conditions for flexible operation combinations by adjusting loads as much as possible with minimal reactor adjustment. Furthermore, it creates conditions for optimizing the load level combination of various loads to achieve optimal operation economy without reactor adjustment.

[0092] Understandably, the above-mentioned technical features can be used in any combination without restriction.

[0093] The above description is merely an embodiment of the present invention and does not limit the patent scope of the present invention. Any equivalent structural or procedural transformations made based on the content of the present invention's specification and drawings, or direct or indirect applications in other related technical fields, are similarly included within the patent protection scope of the present invention.

Claims

1. A nuclear-powered thermoelectric heating system, characterized in that, include: At least one nuclear heating device (10), the nuclear heating device (10) includes at least one steam supply system (11), the steam supply system (11) is provided with a steam outlet (A) and a water inlet (B); A steam distribution device (20) is connected to the steam outlet (A) and the load (50) to allow steam to enter the load (50); A water distribution device (30) connects the load (50) and the inlet (B), allowing the cooling heating medium within the load (50) to flow through the water distribution device (30) to the steam supply system (11); and The control system (40) collects load level signals from the nuclear heating device (10), the steam distribution device (20), and the load (50), and adjusts the load levels of the nuclear heating device (10), the steam distribution device (20), and the load (50) according to the collected load level signals. The load (50) includes a load unit (51) and a control unit (52), wherein the load unit (51) is connected to the steam distribution device (20) and the water supply distribution device (30) respectively. The control unit (52) is communicatively connected to the control system (40) to receive the adjustment signal from the control system (40), adjust the load level of the load unit (51), collect the load level information of the load unit (51) in real time, and control the load level of the load unit (51) according to the load level change.

2. The nuclear thermal power heating system according to claim 1, characterized in that, The steam supply system (11) includes a reactor (111), which is provided with at least two evaporators (1111), each of which is provided with a steam outlet (A) and a water inlet (B).

3. The nuclear power thermoelectric heating system according to claim 2, characterized in that, The steam supply system (11) also includes a steam header (112), the steam outlet (A) of each of the evaporators (1111) is connected to the steam header (112), and the steam header (112) is connected to the steam distribution device (20) through at least one connecting pipe (115).

4. The nuclear power thermoelectric heating system according to claim 3, characterized in that, A steam pipe (116) is connected between the steam outlet (A) of each of the evaporators (1111) and the steam distribution device (20). The steam header (112) is located between the steam outlet (A) and the steam distribution device (20) and is connected to each of the steam pipes (116).

5. The nuclear thermal power heating system according to claim 2, characterized in that, The steam supply system (11) also includes a water supply manifold (113), which is connected to the water inlet (B) of each of the evaporators (1111) and the water supply distribution device (30).

6. The nuclear thermal power heating system according to claim 5, characterized in that, A water pump (114) is also provided between the water distribution device (30) and the water header (113).

7. The nuclear thermal power heating system according to any one of claims 1 to 6, characterized in that, The nuclear heating device (10) also includes a reactor control module (12) that is communicatively connected to the control system (40) to receive the adjustment signal from the control system (40) to adjust the reactor power level, collect the feedwater flow information in the inner loop of the steam supply system (11) in real time, and control the flow of the feedwater distribution device (30) to the reactor (111) according to the change of feedwater flow.

8. The nuclear thermal power heating system according to any one of claims 1 to 6, characterized in that, The steam distribution device (20) includes a steam distribution header, which is connected to the load (50). The feedwater distribution device (30) includes a feedwater header, which is connected to the reactor (111).

9. The nuclear thermal power heating system according to claim 1, characterized in that, Each of the load units (51) includes at least one of a steam turbine (511), a condenser (512), a heat exchanger (513), and a condensate feedwater system (514).

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