A Coordinated Control Method for Power Regulation in Heat Pipe Reactor-Supercritical Carbon Dioxide Nuclear Power Plants

Abstract

This invention discloses a power regulation and coordinated control method for a heat pipe reactor-supercritical carbon dioxide nuclear power plant, comprising: determining that if the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is less than a preset proportional value or proportional range and greater than zero, then using the working fluid flow control process of the turbine compressor unit as the primary regulation mode and the power control process of the heat pipe reactor as the secondary regulation mode; determining that the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is greater than a preset proportional value or proportional range, then using the power control process of the heat pipe reactor as the primary regulation mode and the working fluid flow control process of the turbine compressor unit as the secondary regulation mode. This multi-objective control mode, which integrates primary and secondary controllers in a coordinated manner, helps ensure that the turbine compressor unit has a fast power response to external forces, while improving the energy conversion efficiency of the heat pipe reactor-supercritical carbon dioxide nuclear power plant, thus balancing the energy conversion efficiency and rapid mobility of the nuclear power plant.

Description

Technical Field

[0001] This invention relates to the field of nuclear power plant control system design technology, and more specifically, to a power regulation and coordinated control method for a heat pipe reactor-supercritical carbon dioxide nuclear power plant. Background Technology

[0002] The deep sea holds various strategic resources needed for the future development of human society, representing a new frontier for sustainable development in the 21st century. Large unmanned underwater vehicles (UUVs) are effective tools for deep-sea and subglacial hydrological surveys, resource exploration, and development, capable of autonomous underwater navigation for extended periods. However, existing conventional energy sources cannot meet the requirements for long-duration, large-scale autonomous operations of large UUVs, and insufficient power has become a key factor restricting their development. Nuclear power plants, with their high energy density, long lifespan, and independence from air, are an ideal choice for the power source of large UUVs.

[0003] However, in the design of existing nuclear power plant control systems, heat pipe reactor power regulation is always approached from the perspective of energy matching between the heat pipe reactor system and the supercritical CO2 power generation system. The control process needs to include both the heat pipe reactor system and the supercritical CO2 power generation system, resulting in poor dynamic response characteristics for output power regulation and low overall system flexibility in heat pipe reactor-supercritical CO2 nuclear power plants. Furthermore, the working fluid flow regulation process of turbine compressor units only includes the supercritical CO2 power generation system, without considering the energy matching relationship between the heat pipe reactor system and the supercritical CO2 power generation system, leading to low energy conversion efficiency in heat pipe reactor-supercritical CO2 nuclear power plants. Summary of the Invention

[0004] In response to at least one defect or improvement requirement in the prior art, the present invention provides a power regulation and coordinated control method for a heat pipe reactor-supercritical carbon dioxide nuclear power plant, which solves the technical problem that the energy conversion efficiency and rapid mobility of the nuclear power plant cannot be simultaneously taken into account when changing the output power of the turbine compressor unit.

[0005] To achieve the above objectives, the present invention provides a method for coordinated power regulation control of a heat pipe reactor-supercritical carbon dioxide nuclear power plant, comprising:

[0006] If the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is less than the preset ratio value or the preset ratio range and is greater than zero, then the working fluid flow control process of the turbine compressor unit will be used as the main regulation mode and the power control process of the heat pipe reactor will be used as the auxiliary regulation mode.

[0007] If the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is greater than the preset ratio value or the preset ratio range, then the heat pipe reactor power control process is used as the main adjustment mode, and the turbine compressor unit working fluid flow control process is used as the auxiliary adjustment mode.

[0008] Furthermore, if the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is less than a preset ratio value or a preset ratio range, and greater than zero, then the turbine compressor unit working fluid flow control process is used as the main adjustment mode, and the heat pipe reactor power control process is used as the auxiliary adjustment mode. Specifically, this includes:

[0009] If the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is less than a preset ratio value or a preset ratio range and is greater than zero, the first weighting coefficient for the working fluid flow control of the turbine compressor unit is set to be greater than the first weighting coefficient for the power control of the heat pipe reactor; the sum of the first weighting coefficient for the working fluid flow control of the turbine compressor unit and the first weighting coefficient for the power control of the heat pipe reactor is 1.

[0010] The first result obtained by multiplying the power deviation signal between the actual output power and the expected output power of the turbine compressor unit by the first weighting coefficient of the working fluid flow control of the turbine compressor unit is input into the working fluid flow control process of the turbine compressor unit.

[0011] The second result, obtained by multiplying the power deviation signal between the actual output power and the expected output power of the turbine compressor unit by the first weighting coefficient of the heat pipe reactor power control, is input into the heat pipe reactor power control process.

[0012] Furthermore, the step of determining that the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is greater than the preset ratio value or the preset ratio range, and then using the heat pipe reactor power control process as the main regulation mode and the turbine compressor unit working fluid flow control process as the auxiliary regulation mode, specifically includes:

[0013] If the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is greater than the preset ratio value or the preset ratio range, the second weighting coefficient for the working fluid flow control of the turbine compressor unit is set to be less than the second weighting coefficient for the power control of the heat pipe reactor; the sum of the second weighting coefficient for the working fluid flow control of the turbine compressor unit and the second weighting coefficient for the power control of the heat pipe reactor is 1.

[0014] The third result obtained by multiplying the power deviation signal between the actual output power and the expected output power of the turbine compressor unit by the second weighting coefficient of the working fluid flow control of the turbine compressor unit is input into the working fluid flow control process of the turbine compressor unit.

[0015] The fourth result, obtained by multiplying the power deviation signal between the actual output power and the expected output power of the turbine compressor unit by the second weighting coefficient of the heat pipe reactor power control, is input into the heat pipe reactor power control process.

[0016] Furthermore, the smaller the percentage deviation between the actual output power and the expected output power of the turbine compressor unit, the larger the first weighting coefficient for the working fluid flow control of the turbine compressor unit.

[0017] Furthermore, the greater the percentage deviation between the actual output power and the expected output power of the turbine compressor unit, the larger the second weighting coefficient for the power control of the heat pipe reactor.

[0018] Furthermore, if the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is zero, then the power controller command for the heat pipe reactor and the working fluid flow controller command for the turbine compressor unit remain unchanged.

[0019] Furthermore, the working fluid flow control process of the turbine compressor unit includes:

[0020] Input the first or third result into the turbine compressor unit flow demand calculator to obtain the turbine compressor unit working fluid flow set value; obtain the turbine compressor unit working fluid flow output value through the flow measurement device;

[0021] The difference between the working fluid flow output value and the working fluid flow set value of the turbine compressor unit is input to the flow controller to obtain the opening signal of the turbine inlet flow regulating valve, and the working fluid flow of the turbine compressor unit is controlled based on the opening signal.

[0022] Furthermore, the power control process of the heat pipe reactor includes:

[0023] The second or fourth result is input into the heat pipe reactor power demand calculator to obtain the heat pipe reactor power setpoint; the parameters of heat pipe position and reactor temperature are obtained through the nuclear parameter measuring device to obtain the heat pipe reactor power output value;

[0024] The difference between the heat pipe reactor power output value and the heat pipe reactor power set value is input to the reactivity controller to obtain the heat pipe insertion position set value. The heat pipe drive mechanism moves the heat pipe position to the insertion position set value output by the reactivity controller.

[0025] Furthermore, the formula for the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is as follows:

[0026]

[0027] Where η is the percentage of deviation, P EFor the desired output power, P v This represents the actual output power.

[0028] In summary, compared with the prior art, the above-described technical solutions conceived by this invention can achieve the following beneficial effects:

[0029] (1) The multi-objective control mode of the main and auxiliary controllers of the present invention helps to ensure that the turbine compressor unit has a fast power response to the outside world, while improving the energy conversion efficiency of the heat pipe reactor-supercritical carbon dioxide nuclear power plant, taking into account both the energy conversion efficiency and rapid mobility of the nuclear power plant.

[0030] (2) This invention comprehensively considers the energy conversion efficiency and dynamic response speed of the turbine compressor unit output power regulation process, and coordinates the heat pipe reactor power control and the turbine compressor unit working fluid flow control as a whole. It coordinates the operation according to the percentage deviation between the actual output power and the expected output power of the turbine compressor unit, and determines the weight coefficient of the heat pipe reactor power controller and the weight coefficient of the turbine compressor unit working fluid flow controller according to different power deviation percentage signals. Such a more refined weight setting helps to ensure that the turbine compressor unit has a faster power response to the outside world, while improving the energy conversion efficiency of the heat pipe reactor-supercritical carbon dioxide nuclear power plant.

[0031] (3) The determination process of the weight coefficient of the heat pipe reactor power controller and the weight coefficient of the working fluid flow controller of the turbine compressor unit proposed in this invention is only a design principle. Designers can further modify the specific values ​​in the determination process of the weight coefficient of the heat pipe reactor power controller and the weight coefficient of the working fluid flow controller of the turbine compressor unit according to the application environment of different engineering fields such as nuclear power plants and marine ships. At the same time, this control method can be transplanted to the coordinated control system of conventional nuclear power plants, and has the advantages of being independent of objects, having scalable functions, and being highly adaptable to the environment. Attached Figure Description

[0032] To more clearly illustrate the technical solutions in the embodiments of the present invention, the accompanying drawings used in the embodiments will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the present invention. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0033] Figure 1 This is a schematic diagram of the energy interaction flow of a heat pipe reactor-supercritical carbon dioxide nuclear power plant provided in an embodiment of the present invention;

[0034] Figure 2 A control principle diagram of heat pipe reactor power regulation provided in an embodiment of the present invention;

[0035] Figure 3 This is a control principle diagram for regulating the working fluid flow of a turbine compressor unit provided in an embodiment of the present invention;

[0036] Figure 4 A flowchart illustrating the implementation of the multi-objective coordinated control method for power regulation in a heat pipe reactor-supercritical carbon dioxide nuclear power plant provided in this embodiment of the invention;

[0037] Figure 5 This is a schematic diagram illustrating the multi-objective coordinated control principle of power regulation in a heat pipe reactor-supercritical carbon dioxide nuclear power plant, provided in an embodiment of the present invention. Detailed Implementation

[0038] To make the objectives, technical solutions, and advantages of this invention clearer, the invention will be further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the invention. Furthermore, the technical features involved in the various embodiments of this invention described below can be combined with each other as long as they do not conflict with each other.

[0039] The terms "first," "second," or "third," etc., used in the specification, claims, or accompanying drawings of this application are used to distinguish different objects, not to describe a particular order. Furthermore, the terms "comprising" and "having," and any variations thereof, are intended to cover non-exclusive inclusion. For example, a process, method, system, product, or apparatus that includes a series of steps or units is not limited to the listed steps or units, but may optionally include steps or units not listed, or may optionally include other steps or units inherent to such processes, methods, products, or apparatus.

[0040] like Figure 1 As shown, in one embodiment, the heat pipe reactor-supercritical carbon dioxide nuclear power plant mainly consists of a heat pipe reactor, an intermediate heat exchanger, a compressor, a turbine, a generator, a regenerator, and a cooler. The compressor, turbine, and generator are coaxial, forming an integrated unit. The heat from the solid reactor core is passively transferred to the intermediate heat exchanger via heat pipes to heat the carbon dioxide working fluid. The heated carbon dioxide directly enters the turbine to perform work. The exhaust gas after performing work is cooled by the low-temperature fluid on the regenerator and then cooled by the cooler to the required compressor inlet temperature. It then enters the compressor for compression and pressurization and is reheated in the regenerator, thus forming a closed loop.

[0041] The power regulation and control objective of a heat pipe reactor-supercritical carbon dioxide nuclear power plant is to ensure that the actual output power of the turbine compressor unit tracks the desired output power under steady-state, transient, and switching operating conditions, and to ensure that the thermal parameters of the heat pipe reactor-supercritical carbon dioxide nuclear power plant, such as temperature, pressure, and flow rate, remain stable. The actual output power of the turbine compressor unit can be dynamically adjusted in two ways: by changing the power of the heat pipe reactor and the working fluid flow rate of the turbine compressor unit. The heat pipe reactor power regulation, from the perspective of balancing the energy supply and demand relationship between the heat pipe reactor system and the supercritical carbon dioxide power generation system, changes the reactor reactivity by adjusting the position of the heat pipes, ensuring that the heat pipe reactor power can be converted into the output electrical power of the turbine compressor unit to the maximum extent. This is beneficial to improving the energy conversion efficiency of the heat pipe reactor-supercritical carbon dioxide nuclear power plant, but its response speed and maneuverability are relatively poor. The turbine compressor unit working fluid flow rate regulation scheme directly changes the opening of the turbine inlet regulating valve, thereby changing the flow resistance of the circulation system to achieve the purpose of changing the circulating working fluid flow rate of the turbine compressor unit. This can quickly follow the desired output power value of the turbine compressor unit, but the energy conversion efficiency of the heat pipe reactor-supercritical carbon dioxide nuclear power plant is relatively low.

[0042] The control principle diagram of heat pipe reactor power regulation is as follows: Figure 2 As shown, the system mainly includes a reactivity controller, a heat pipe drive mechanism, a heat pipe reactor, a supercritical carbon dioxide power generation system, a nuclear parameter measuring device, a supercritical carbon dioxide parameter measuring device, and a reactor power demand calculator. When there is a deviation between the actual output power and the expected output power of the supercritical carbon dioxide power generation system, the supercritical carbon dioxide parameter measuring device acquires signals such as temperature, pressure, flow rate, rotational speed, and power of the supercritical carbon dioxide power generation system. These signals are input into the reactor power demand calculator to obtain the heat pipe reactor power setpoint. Simultaneously, the nuclear parameter measuring device acquires parameters such as heat pipe position and reactor temperature to obtain the heat pipe reactor power output value. The difference between the heat pipe reactor power output value and the reactor power setpoint is input into the reactivity controller. The reactivity controller calculates the heat pipe insertion position setpoint and moves the heat pipe position to the insertion position setpoint output by the reactivity controller through the heat pipe drive mechanism.

[0043] The control principle diagram of working fluid flow regulation of turbine compressor unit is as follows: Figure 3As shown, the system mainly includes a flow controller, regulating valve, integrated turbine compressor unit, flow measurement device (synchronized with the speed measurement device), power parameter measurement device, and flow demand calculator (synchronized and equivalent to the demand speed calculator). When there is a deviation between the actual output power and the expected output power of the supercritical carbon dioxide power generation system, the power signal of the integrated turbine compressor unit is obtained through the supercritical carbon dioxide parameter measurement device. These signals are input to the flow demand calculator of the turbine compressor unit to obtain the set value of the working fluid flow of the turbine compressor unit. At the same time, the working fluid flow at the turbine unit inlet is obtained through the flow measurement device. The difference between the flow output value of the turbine compressor unit and the flow set value is input to the flow controller. The flow controller calculates the opening signal of the turbine inlet flow regulating valve, thereby achieving the function of changing the circulating working fluid flow of the integrated turbine compressor unit.

[0044] The control processes described above for power regulation in heat pipe reactors and working fluid flow regulation in turbine compressor units reveal that power regulation in heat pipe reactors always starts from the energy matching perspective of the heat pipe reactor system and the supercritical CO2 power generation system. This control process requires consideration of both systems, resulting in poor dynamic response characteristics for power regulation in heat pipe reactor-supercritical CO2 nuclear power plants and low overall system flexibility. Conversely, the working fluid flow regulation process in turbine compressor units only includes the supercritical CO2 power generation system, neglecting the energy matching relationship between the heat pipe reactor system and the supercritical CO2 power generation system. This leads to lower energy conversion efficiency in heat pipe reactor-supercritical CO2 nuclear power plants.

[0045] This application comprehensively considers the energy conversion efficiency and dynamic response speed of the turbine compressor unit's output power regulation process, and proposes a multi-objective coordinated control method for power regulation of a heat pipe reactor-supercritical carbon dioxide nuclear power plant. The method integrates heat pipe reactor power control and turbine compressor unit working fluid flow control for overall coordinated control, and coordinates operation based on the percentage deviation between the actual and expected output power of the turbine compressor unit. Here, the percentage deviation is defined as:

[0046]

[0047] Where η is the percentage deviation between the actual output power and the expected output power, and P E For the desired output power, P v This represents the actual output power.

[0048] The implementation idea of ​​the multi-objective cooperative control method for power regulation in heat pipe reactor-supercritical carbon dioxide nuclear power plants is as follows: Figure 4As shown, the power deviation signal is obtained by subtracting the actual output power from the expected output power of the turbine compressor unit. This power deviation signal is then multiplied by the power control weighting coefficient of the heat pipe reactor and the working fluid flow control weighting coefficient of the turbine compressor unit, respectively, and then input into the power control loop of the heat pipe reactor and the working fluid flow control loop of the turbine compressor unit, respectively, to achieve overall coordinated control of the heat pipe reactor power and the working fluid flow of the turbine compressor unit. The heat pipe reactor power control loop is as follows: Figure 2 As shown, the working fluid flow control link of the turbine compressor unit is as follows: Figure 3 As shown, it will not be elaborated further here.

[0049] Specifically, when the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is large, such as η > 70%, the heat pipe reactor power control acts as the primary regulation mode with a weight of 0.9, while the turbine compressor unit working fluid flow control acts as the auxiliary regulation mode with a weight of 0.1. When the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is small, such as η ≤ 30%, the turbine compressor unit working fluid flow control acts as the primary regulation mode with a weight of 0.8, while the heat pipe reactor power control acts as the auxiliary regulation mode with a weight of 0.2. This multi-objective control mode, which integrates the primary and auxiliary controllers, helps ensure that the turbine compressor unit has a fast power response characteristic, while also improving the energy conversion efficiency of the heat pipe reactor-supercritical carbon dioxide nuclear power plant, achieving the beneficial effect of balancing the energy conversion efficiency and rapid mobility of the nuclear power plant.

[0050] To further refine the details, when the actual output power of the turbine compressor unit is within the expected range (i.e., the deviation percentage η = 0), both the heat pipe reactor power controller command and the turbine compressor unit working fluid flow controller command remain unchanged. When the deviation percentage between the actual output power and the expected output power is 30% ≥ η > 0, the turbine compressor unit working fluid flow control becomes the primary control mode with a weight of 0.8, and the heat pipe reactor power control becomes the secondary control mode with a weight of 0.2. When the deviation percentage between the actual output power and the expected output power is 50% ≥ η > 30%, the turbine compressor unit working fluid flow control becomes the primary control mode with a weight of 0.8. The weight of the flow control component is 0.5, and the weight of the heat pipe reactor power control component is also 0.5. When the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is 70% ≥ η > 50%, the heat pipe reactor power control is used as the main regulation mode with a weight of 0.7, and the turbine compressor unit working fluid flow control is used as the auxiliary regulation mode with a weight of 0.3. When the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is large, such as η > 70%, the heat pipe reactor power control is used as the main regulation mode with a weight of 0.9, and the turbine compressor unit working fluid flow control is used as the auxiliary regulation mode with a weight of 0.1. Combining the above principles for determining the weight coefficients of the heat pipe reactor power controller and the turbine compressor unit working fluid flow controller, the multi-objective collaborative control principle of power regulation in a heat pipe reactor-supercritical carbon dioxide nuclear power plant is as follows: Figure 5 As shown. By Figure 5 It can also be seen that the preset intermediate value of the deviation percentage when the weights are the same can be either a fixed value, such as 50%, or a numerical range, such as 50% ≥ η > 30%. The determination process of the weight coefficient of the heat pipe reactor power controller and the weight coefficient of the turbine compressor unit working fluid flow controller proposed in this embodiment is only a design principle. Designers can further modify the specific values ​​in the determination process of the weight coefficient of the heat pipe reactor power controller and the weight coefficient of the turbine compressor unit working fluid flow controller according to the application environment of different engineering fields such as nuclear power plants and marine vessels. At the same time, this control method can be transplanted to the coordinated control system of conventional nuclear power plants, and has the advantages of being independent of objects, having scalable functions, and being highly adaptable to the environment.

[0051] This application comprehensively considers the energy conversion efficiency and dynamic response speed of the turbine compressor unit's output power regulation process. It integrates the heat pipe reactor power control and the turbine compressor unit's working fluid flow control as a whole for coordinated control. It coordinates the operation based on the percentage deviation between the actual output power and the expected output power of the turbine compressor unit. The weighting coefficients of the heat pipe reactor power controller and the turbine compressor unit's working fluid flow controller are determined according to different power deviation percentage signals. This more refined weighting setting helps to ensure that the turbine compressor unit has a faster power response to external forces, while improving the energy conversion efficiency of the heat pipe reactor-supercritical carbon dioxide nuclear power plant.

[0052] The foregoing description is merely an exemplary embodiment of this disclosure and should not be construed as limiting the scope of this disclosure. Any equivalent changes and modifications made in accordance with the teachings of this disclosure shall still fall within the scope of this disclosure. Other embodiments of this disclosure will be readily apparent to those skilled in the art upon consideration of the specification and practice of the disclosure herein. This invention is intended to cover any variations, uses, or adaptations of this disclosure that follow the general principles of this disclosure and include common knowledge or customary techniques in the art not described herein. The specification and embodiments are to be considered exemplary only, and the scope and spirit of this disclosure are defined by the claims.

[0053] The technical features of the above embodiments can be combined in any way. For the sake of brevity, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0054] Those skilled in the art will readily understand that the above description is merely a preferred embodiment of the present invention and is not intended to limit the present invention. Any modifications, equivalent substitutions, and improvements made within the spirit and principles of the present invention should be included within the scope of protection of the present invention.

Claims

1. A method for coordinated power regulation control of a heat pipe reactor-supercritical carbon dioxide nuclear power plant, characterized in that, include: If the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is less than the preset ratio value or the preset ratio range and is greater than zero, then the working fluid flow control process of the turbine compressor unit will be used as the main regulation mode and the power control process of the heat pipe reactor will be used as the auxiliary regulation mode. If the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is greater than the preset ratio value or the preset ratio range, then the heat pipe reactor power control process is used as the main adjustment mode, and the turbine compressor unit working fluid flow control process is used as the auxiliary adjustment mode.

2. The collaborative control method as described in claim 1, characterized in that, The determination that the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is less than a preset ratio value or a preset ratio range, and greater than zero, specifically includes using the turbine compressor unit working fluid flow control process as the main regulation mode and the heat pipe reactor power control process as the auxiliary regulation mode: If the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is less than a preset ratio value or a preset ratio range and is greater than zero, the first weighting coefficient for the working fluid flow control of the turbine compressor unit is set to be greater than the first weighting coefficient for the power control of the heat pipe reactor; the sum of the first weighting coefficient for the working fluid flow control of the turbine compressor unit and the first weighting coefficient for the power control of the heat pipe reactor is 1. The first result obtained by multiplying the power deviation signal between the actual output power and the expected output power of the turbine compressor unit by the first weighting coefficient of the working fluid flow control of the turbine compressor unit is input into the working fluid flow control process of the turbine compressor unit. The second result, obtained by multiplying the power deviation signal between the actual output power and the expected output power of the turbine compressor unit by the first weighting coefficient of the heat pipe reactor power control, is input into the heat pipe reactor power control process.

3. The collaborative control method as described in claim 1, characterized in that, The step of determining that the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is greater than the preset ratio value or the preset ratio range, and then using the heat pipe reactor power control process as the main regulation mode and the turbine compressor unit working fluid flow control process as the auxiliary regulation mode, specifically includes: If the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is greater than the preset ratio value or the preset ratio range, the second weighting coefficient for the working fluid flow control of the turbine compressor unit is set to be less than the second weighting coefficient for the power control of the heat pipe reactor; the sum of the second weighting coefficient for the working fluid flow control of the turbine compressor unit and the second weighting coefficient for the power control of the heat pipe reactor is 1. The third result obtained by multiplying the power deviation signal between the actual output power and the expected output power of the turbine compressor unit by the second weighting coefficient of the working fluid flow control of the turbine compressor unit is input into the working fluid flow control process of the turbine compressor unit. The fourth result, obtained by multiplying the power deviation signal between the actual output power and the expected output power of the turbine compressor unit by the second weighting coefficient of the heat pipe reactor power control, is input into the heat pipe reactor power control process.

4. The cooperative control method as described in claim 2, characterized in that, The smaller the percentage deviation between the actual output power and the expected output power of the turbine compressor unit, the larger the first weighting coefficient for the working fluid flow control of the turbine compressor unit.

5. The cooperative control method as described in claim 3, characterized in that, The greater the percentage deviation between the actual output power and the expected output power of the turbine compressor unit, the greater the second weighting coefficient for the power control of the heat pipe reactor.

6. The collaborative control method as described in claim 1, characterized in that, If the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is zero, then the power controller command for the heat pipe reactor and the working fluid flow controller command for the turbine compressor unit remain unchanged.

7. The cooperative control method according to any one of claims 2-3, characterized in that, The working fluid flow control process of the turbine compressor unit includes: Input the first or third result into the turbine compressor unit flow demand calculator to obtain the turbine compressor unit working fluid flow set value; obtain the turbine compressor unit working fluid flow output value through the flow measurement device; The difference between the working fluid flow output value and the working fluid flow set value of the turbine compressor unit is input to the flow controller to obtain the opening signal of the turbine inlet flow regulating valve, and the working fluid flow of the turbine compressor unit is controlled based on the opening signal.

8. The cooperative control method according to any one of claims 2-3, characterized in that, The power control process for the heat pipe reactor includes: The second or fourth result is input into the heat pipe reactor power demand calculator to obtain the heat pipe reactor power setpoint; the parameters of heat pipe position and reactor temperature are obtained through the nuclear parameter measuring device to obtain the heat pipe reactor power output value; The difference between the heat pipe reactor power output value and the heat pipe reactor power set value is input to the reactivity controller to obtain the heat pipe insertion position set value. The heat pipe drive mechanism moves the heat pipe position to the insertion position set value output by the reactivity controller.

9. The cooperative control method as described in claim 1, characterized in that, The formula for the percentage deviation between the actual output power and the expected output power of the turbine compressor unit is as follows: Where η is the percentage of deviation, P E For the desired output power, P v This represents the actual output power.

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