Method and device for controlling main steam pressure of multi-module nuclear thermal power system

Abstract

This disclosure relates to a method and apparatus for controlling the main steam pressure of a multi-module nuclear thermal power system. The method includes: acquiring a measured value of the main steam pressure of the multi-module nuclear thermal power system with the opening degree of the main steam regulating valve of the multi-module nuclear thermal power system fixed; if the deviation between the measured value of the main steam pressure and the set value of the main steam pressure of the multi-module nuclear thermal power system is greater than a first threshold, determining an adjustment amount for the feedwater pump speed set value and an adjustment amount for the thermal power set value of the multi-module nuclear thermal power system based on the deviation; adjusting the feedwater pump speed set value of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed set value, and adjusting the thermal power set value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power set value, so as to reduce the deviation.

Description

Technical Field

[0001] This disclosure relates to the field of nuclear energy science and engineering, specifically to a method and apparatus for controlling the main steam pressure of a multi-module nuclear thermoelectric system. Background Technology

[0002] A multi-module nuclear cogeneration system refers to a system where multiple nuclear steam supply modules use nuclear energy to heat water, creating steam that is then combined into main steam. This main steam is then distributed to a turbine and a heating system. The turbine can generate electricity using the steam, while the heating system can provide thermal or mechanical energy. Generally, a main steam regulating valve is installed before the turbine to adjust the distribution ratio of main steam between the turbine and the heating system, achieving the effect of "prioritizing the heating system's load and using the remaining steam for power generation."

[0003] However, in related technologies, when the opening of the main steam regulating valve in front of the turbine is fixed, the steam pressure entering the heating system cannot be effectively adjusted in a multi-module nuclear cogeneration system. As a result, the heat load of the heating system cannot be accurately met, leading to unstable energy supply performance of the heating system. Summary of the Invention

[0004] To overcome the problems existing in the related technologies, this disclosure provides a method and apparatus for controlling the main steam pressure of a multi-module nuclear thermoelectric system, in order to solve the defects in the related technologies.

[0005] According to a first aspect of the present disclosure, a method for controlling the main steam pressure of a multi-module nuclear thermoelectric system is provided, the method comprising:

[0006] With the opening degree of the main steam regulating valve of the multi-module nuclear thermal power system fixed, the main steam pressure measurement value of the multi-module nuclear thermal power system is obtained;

[0007] If the deviation between the measured value of the main steam pressure and the set value of the main steam pressure of the multi-module nuclear thermal power system is greater than the first threshold, then the adjustment amount of the set value of the feedwater pump speed and the set value of the thermal power of the multi-module nuclear thermal power system are determined according to the deviation.

[0008] The feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so as to reduce the deviation.

[0009] In one embodiment of this disclosure, determining the adjustment amount of the feedwater pump speed setpoint and the thermal power setpoint of the multi-module nuclear thermoelectric system based on the deviation includes:

[0010] Based on the deviation and the first proportional-integral control algorithm, the adjustment amount of the feedwater pump speed setpoint of the multi-module nuclear thermal power system is determined;

[0011] The adjustment amount of the thermal power setpoint of the multi-module nuclear thermoelectric system is determined based on the deviation and the second proportional-integral control algorithm.

[0012] In one embodiment of this disclosure, adjusting the feedwater pump speed setpoint of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setpoint includes:

[0013] Based on the adjustment amount of the feedwater pump speed setting value, the hydraulic coupler scoop position setting value of the feedwater pump of the multi-module nuclear thermal power system is adjusted to adjust the speed of the feedwater pump.

[0014] In one embodiment of this disclosure, adjusting the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint includes:

[0015] The thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system is adjusted based on the adjustment amount of the thermal power setpoint, so that the nuclear steam supply system module adjusts the feedwater flow rate based on the adjusted thermal power setpoint.

[0016] In one embodiment of this disclosure, adjusting the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint includes:

[0017] The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the nuclear power based on the adjusted thermal power setting value.

[0018] In one embodiment of this disclosure, adjusting the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint includes:

[0019] The thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system is adjusted based on the adjustment amount of the thermal power setpoint, so that the nuclear steam supply system module adjusts the primary coolant flow rate based on the adjusted thermal power setpoint.

[0020] In one embodiment of this disclosure, the method further includes:

[0021] Based on the deviation, at least one nuclear steam supply system module that participates in the main steam pressure control is determined from all the nuclear steam supply system modules of the multi-module nuclear thermoelectric system.

[0022] The adjustment of the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint includes:

[0023] Based on the adjustment amount of the thermal power setpoint, the thermal power setpoint of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermoelectric system is adjusted.

[0024] In one embodiment of this disclosure, the method further includes:

[0025] According to user instructions, at least one nuclear steam supply system module is identified from all the nuclear steam supply system modules of the multi-module nuclear thermoelectric system that participates in the main steam pressure control.

[0026] The adjustment of the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint includes:

[0027] Based on the adjustment amount of the thermal power setpoint, the thermal power setpoint of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermoelectric system is adjusted.

[0028] In one embodiment of this disclosure, adjusting the feedwater pump speed setpoint of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setpoint, and adjusting the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setpoint, to reduce the deviation, includes:

[0029] The feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, until the deviation is reduced to below a second threshold, wherein the second threshold is less than the first threshold.

[0030] In one embodiment of this disclosure, the main steam regulating valve of the multi-module nuclear thermal power system is used to fix the opening degree when the turbine intake air volume is fixed or when the turbine is under maintenance.

[0031] According to a second aspect of the present disclosure, a main steam pressure control device for a multi-module nuclear thermoelectric system is provided, the device comprising:

[0032] The acquisition module is used to acquire the measured value of the main steam pressure of the multi-module nuclear thermal power system when the opening degree of the main steam regulating valve of the multi-module nuclear thermal power system is fixed.

[0033] The determination module is used to determine the adjustment amount of the feedwater pump speed setting value and the thermal power setting value of the multi-module nuclear thermal power system based on the deviation if the deviation between the measured value of the main steam pressure and the set value of the main steam pressure of the multi-module nuclear thermal power system is greater than a first threshold.

[0034] An adjustment module is used to adjust the feedwater pump speed of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setting value, and to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, so as to reduce the deviation.

[0035] In one embodiment of this disclosure, the determining module is used to:

[0036] Based on the deviation and the first proportional-integral control algorithm, the adjustment amount of the feedwater pump speed setpoint of the multi-module nuclear thermal power system is determined;

[0037] The adjustment amount of the thermal power setpoint of the multi-module nuclear thermoelectric system is determined based on the deviation and the second proportional-integral control algorithm.

[0038] In one embodiment of this disclosure, when the adjustment module is used to adjust the feedwater pump speed setting value of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setting value, it is used for:

[0039] Based on the adjustment amount of the feedwater pump speed setting value, the hydraulic coupler scoop position setting value of the feedwater pump of the multi-module nuclear thermal power system is adjusted to adjust the speed of the feedwater pump.

[0040] In one embodiment of this disclosure, when the adjustment module adjusts the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint, it is used to:

[0041] The thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system is adjusted based on the adjustment amount of the thermal power setpoint, so that the nuclear steam supply system module adjusts the feedwater flow rate based on the adjusted thermal power setpoint.

[0042] In one embodiment of this disclosure, when the adjustment module adjusts the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint, it is used to:

[0043] The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the nuclear power based on the adjusted thermal power setting value.

[0044] In one embodiment of this disclosure, when the adjustment module adjusts the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint, it is used to:

[0045] The thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system is adjusted based on the adjustment amount of the thermal power setpoint, so that the nuclear steam supply system module adjusts the primary coolant flow rate based on the adjusted thermal power setpoint.

[0046] In one embodiment of this disclosure, the apparatus further includes a selection module for:

[0047] Based on the deviation, at least one nuclear steam supply system module that participates in the main steam pressure control is determined from all the nuclear steam supply system modules of the multi-module nuclear thermoelectric system.

[0048] When the adjustment module is used to adjust the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint, it is used for:

[0049] Based on the adjustment amount of the thermal power setpoint, the thermal power setpoint of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermoelectric system is adjusted.

[0050] In one embodiment of this disclosure, the apparatus further includes a selection module for:

[0051] According to user instructions, at least one nuclear steam supply system module is identified from all the nuclear steam supply system modules of the multi-module nuclear thermoelectric system that participates in the main steam pressure control.

[0052] When the adjustment module is used to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, it is used to: adjust the thermal power setting value of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value.

[0053] In one embodiment of this disclosure, the adjustment module is used to:

[0054] The feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, until the deviation is reduced to below a second threshold, wherein the second threshold is less than the first threshold.

[0055] In one embodiment of this disclosure, the main steam regulating valve of the multi-module nuclear thermal power system is used to fix the opening degree when the turbine intake air volume is fixed or when the turbine is under maintenance.

[0056] According to a third aspect of the present disclosure, a computer program product is provided, including a computer program / instructions that, when executed by a processor, implement the steps of the method described in the first aspect.

[0057] According to a fourth aspect of the present disclosure, an electronic device is provided, the electronic device including a memory and a processor, the memory being configured to store computer instructions executable on the processor, and the processor being configured to implement the method of the first aspect when executing the computer instructions.

[0058] According to a fifth aspect of the present disclosure, a computer-readable storage medium is provided having a computer program stored thereon, which, when executed by a processor, implements the method described in the first aspect.

[0059] The technical solutions provided by the embodiments of this disclosure may include the following beneficial effects:

[0060] The main steam pressure control method for a multi-module nuclear thermal power system provided in this disclosure, with the opening of the main steam regulating valve of the multi-module nuclear thermal power system fixed, acquires the measured value of the main steam pressure of the multi-module nuclear thermal power system to determine the deviation between the measured value and the set value of the main steam pressure. When the deviation exceeds a first threshold, the system's feedwater pump speed set value and the thermal power set value of at least one nuclear steam supply system module are adjusted based on the deviation to reduce the deviation. This method reduces the deviation by adjusting the system's feedwater pump speed and the thermal power of at least one nuclear steam supply system module when the set value and measured value of the main steam pressure deviate. It can quickly respond to heat load fluctuations in the heating system when the opening of the main steam regulating valve is fixed, thereby ensuring that the steam pressure entering the heating system meets the heat load requirements of the heating system and improving the stability of the heating effect. Attached Figure Description

[0061] The accompanying drawings, which are incorporated in and form part of this specification, illustrate embodiments consistent with the invention and, together with the description, serve to explain the principles of the invention.

[0062] Figure 1 This is a schematic diagram of the structure of a multi-module nuclear thermoelectric system shown in an exemplary embodiment of the present disclosure;

[0063] Figure 2 This is a flowchart illustrating a main steam pressure control method for a multi-module nuclear thermoelectric system according to an exemplary embodiment of this disclosure;

[0064] Figure 3 This is a schematic diagram of the main steam pressure control logic of a multi-module nuclear thermoelectric system illustrated in an exemplary embodiment of the present disclosure;

[0065] Figure 4 This is a schematic diagram of the main steam pressure control device of a multi-module nuclear thermoelectric system shown in an exemplary embodiment of the present disclosure;

[0066] Figure 5 This is a structural block diagram of an electronic device illustrated in an exemplary embodiment of the present disclosure. Detailed Implementation

[0067] Exemplary embodiments will now be described in detail, examples of which are illustrated in the accompanying drawings. When the following description relates to the drawings, unless otherwise indicated, the same numerals in different drawings denote the same or similar elements. The embodiments described in the following exemplary embodiments do not represent all embodiments consistent with this disclosure. Rather, they are merely examples of apparatuses and methods consistent with some aspects of this disclosure as detailed in the appended claims.

[0068] The terminology used in this disclosure is for the purpose of describing particular embodiments only and is not intended to be limiting of the disclosure. The singular forms “a,” “the,” and “the” as used in this disclosure and the appended claims are also intended to include the plural forms unless the context clearly indicates otherwise. It should also be understood that the term “and / or” as used herein refers to and includes any and all possible combinations of one or more of the associated listed items.

[0069] It should be understood that although the terms first, second, third, etc., may be used in this disclosure to describe various information, such information should not be limited to these terms. These terms are used only to distinguish information of the same type from one another. For example, without departing from the scope of this disclosure, first information may also be referred to as second information, and similarly, second information may also be referred to as first information. Depending on the context, the word "if" as used herein may be interpreted as "when," "when," or "in response to determination."

[0070] A multi-module nuclear cogeneration system refers to a system where multiple nuclear steam supply modules use nuclear energy to heat water, creating steam that is then combined into main steam. This main steam is then distributed to a turbine and a heating system. The turbine can generate electricity using the steam, while the heating system can provide thermal or mechanical energy. Generally, a main steam regulating valve is installed before the turbine to adjust the distribution ratio of main steam between the turbine and the heating system, achieving the effect of "prioritizing the heating system's load and using the remaining steam for power generation."

[0071] However, in related technologies, when the opening of the main steam regulating valve in front of the turbine is fixed, the steam pressure entering the heating system cannot be effectively adjusted in a multi-module nuclear cogeneration system. As a result, the heat load of the heating system cannot be accurately met, leading to unstable energy supply performance of the heating system.

[0072] Based on this, in a first aspect, at least one embodiment of this disclosure provides a main steam pressure control method for a multi-module nuclear thermal power system. This method can ensure that the steam pressure entering the heating system meets the heat load requirements of the heating system by dynamically adjusting the feedwater pump speed and the thermal power of at least one nuclear steam supply system module when the opening of the main steam regulating valve (i.e., the steam valve used to control the steam flow rate entering the turbine) of the multi-module nuclear thermal power system is fixed, thereby ensuring the stable heating effect of the heating system.

[0073] The aforementioned multi-module nuclear cogeneration system has multiple nuclear steam supply system modules. Each module can heat supercooled water by providing a high-temperature inert gas flow through nuclear fission. The coupling effects between these modules are significant, and the side-by-side arrangement of the reactor core and the direct-flow evaporator within each module further exacerbates the internal coupling effects. Therefore, the aforementioned multi-module nuclear cogeneration system cannot use the main steam pressure control method of a thermal power plant's main pipe to control the main steam pressure.

[0074] First, with appendix Figure 1 Taking the multi-module nuclear thermoelectric system shown as an example, the structure of the multi-module nuclear thermoelectric system is explained.

[0075] The generator set includes six nuclear steam supply system modules, a condensate heating system (only the feedwater pumps it contains are shown in the figure), a condenser, a steam turbine (not shown in the figure), a generator (not shown in the figure), and a heating system. It should be understood that there is no limit to the number of nuclear steam supply system modules in the generator set; the six nuclear steam supply system modules shown here are merely an example.

[0076] The condensate heating system may include a condensate pump, a shaft seal heater, multiple low-pressure heaters, a deaerator, a feedwater pump, and multiple high-pressure heaters, all connected sequentially by piping. The condenser outlet is connected to the condensate heating system via piping. Condensate output from the condenser reaches the condensate heating system through piping, where it is sequentially driven by the condensate pump, heated by the shaft seal heater, heated by multiple low-pressure heaters, deaerated by the deaerator, driven and pressurized by the feedwater pump, and heated by multiple high-pressure heaters, finally outputting high-temperature liquid water. Due to the high pressure of the high-pressure heaters, the boiling point of the water is increased, and the output high-temperature liquid water temperature can exceed 100°C. The outlet of the condensate heating system is connected to the evaporators of six nuclear steam supply system modules via piping, and each evaporator has a feedwater regulating valve on the piping between the outlet of the condensate heating system and each evaporator. The condensate output from the condensate heating system is then distributed to the six steam generators.

[0077] The nuclear steam supply system module includes a nuclear reactor and an evaporator. A circulation pipeline connects the reactor and the evaporator, consisting of an upward pipeline from the reactor to the evaporator and a downward pipeline from the evaporator to the reactor. Each reactor generates high temperatures through nuclear fission to heat helium, which is then output to the evaporator as a helium flow through the upward pipeline. In each evaporator of the nuclear steam supply system module, the high-temperature helium entering the evaporator exchanges heat with the condensate entering the evaporator, causing the condensate to vaporize into water vapor. This cools the high-temperature helium, which then returns to the reactor as a helium flow through the downward pipeline.

[0078] The steam output from the evaporators of the six nuclear steam supply system modules is collected and then distributed to the steam turbine and heating system. A main steam regulating valve is installed before the steam turbine to regulate the amount of steam entering the turbine. After entering the steam turbine, it drives the turbine to rotate. The steam turbine is connected to the generator, so when the steam turbine rotates, it causes the generator to generate current through electromagnetic induction. The current generated by the generator is input into the power grid. The steam turbine is connected to the condenser through pipelines. The steam passing through the steam turbine enters the condenser through pipelines to be cooled and liquefied into condensate. After entering the heating system, the heating system can use the steam to provide heat or mechanical energy. The heating system is connected to the condenser through pipelines. The steam passing through the heating system also enters the condenser through pipelines to be cooled and liquefied into condensate.

[0079] Next, continue with the appendix Figure 1 Taking the multi-module nuclear thermoelectric system shown as an example, the feedwater flow control logic, nuclear power control logic, and primary coolant flow control logic of the nuclear steam supply system module of the multi-module nuclear thermoelectric system are explained.

[0080] Feedwater flow control logic: The thermal power control strategy (such as the adjustment amount of thermal power) is determined based on the flow rate G of the condensate before entering the nuclear steam supply system module, the temperature T of the condensate before entering the nuclear steam supply system module, the pressure P of the condensate before entering the nuclear steam supply system module, the temperature T of the steam output by the nuclear steam supply system module, and the measured value P of the main steam pressure. The feedwater flow setpoint is determined based on the module thermal power setpoint, the thermal power-feedwater flow steady-state characteristic table, and the thermal power control strategy. Then, the opening degree of the feedwater regulating valve of the nuclear steam supply system module is controlled based on the feedwater flow setpoint and the flow rate G of the condensate before entering the nuclear steam supply system module.

[0081] Nuclear power control logic: The hot helium temperature setpoint is determined based on the module thermal power setpoint and the thermal power-hot helium temperature steady-state characteristic table; the helium temperature control strategy (e.g., helium temperature adjustment amount) is determined based on the hot helium temperature setpoint and the temperature T of the helium gas flow output by the nuclear steam supply system module; the nuclear power setpoint is determined based on the module thermal power setpoint, the thermal power-nuclear power steady-state characteristic table, and the helium temperature control strategy; and then the nuclear power of the nuclear reactor is controlled based on the nuclear power setpoint and the measured nuclear power value of the nuclear reactor.

[0082] The primary loop coolant flow control logic is as follows: The steam temperature setpoint is determined based on the module's thermal power setpoint and the thermal power-steam temperature steady-state characteristic table; the steam temperature control strategy (e.g., steam temperature adjustment amount) is determined based on the steam temperature setpoint and the steam temperature T output by the nuclear steam supply system module; the helium flow setpoint is determined based on the module's thermal power setpoint, the thermal power-helium flow steady-state characteristic table, and the steam temperature control strategy; and then, based on the helium flow setpoint and the helium flow rate G output by the nuclear steam supply system module, the speed of the main helium blower is controlled.

[0083] Next, continue with the appendix. Figure 1 Taking the multi-module nuclear thermoelectric system shown as an example, this paper details the main steam pressure control logic of the multi-module nuclear thermoelectric system, i.e., the specific content of the method.

[0084] Please refer to the appendix. Figure 2 The example illustrates the flow of a main steam pressure control method for a multi-module nuclear thermoelectric system, including steps S201 to S203.

[0085] In step S201, with the opening degree of the main steam regulating valve of the multi-module nuclear thermoelectric system fixed, the measured value of the main steam pressure of the multi-module nuclear thermoelectric system is obtained.

[0086] In this case, the main steam regulating valve of the multi-module nuclear thermal power system has a fixed opening due to fixed turbine air intake or turbine maintenance. In this case, the main steam pressure of the system cannot be controlled by the main steam regulating valve.

[0087] For example, the main steam pressure measurement value can be obtained in real time based on the pressure sensor installed on the main steam pipeline.

[0088] In step S202, if the deviation between the measured value of the main steam pressure and the set value of the main steam pressure of the multi-module nuclear thermal power system is greater than a first threshold, then the adjustment amount of the set value of the feedwater pump speed and the set value of the thermal power of the multi-module nuclear thermal power system are determined according to the deviation.

[0089] The main steam pressure setpoint is the value at which the main steam pressure is desired to be maintained. The first threshold is the tolerance value for fluctuations in the main steam pressure, which can be 0 or other values; preferably, the first threshold is not 0, to avoid frequent and complex adjustments when the main steam pressure experiences small fluctuations.

[0090] The deviation between the measured main steam pressure value and the set value of the main steam pressure of the multi-module nuclear thermoelectric system can be obtained.

[0091] For example, the adjustment amounts of the feedwater pump speed setpoint and the thermal power setpoint of the multi-module nuclear thermoelectric system can be determined in the following manner:

[0092] Based on the aforementioned deviation and the first proportional-integral control algorithm, the adjustment amount for the feedwater pump speed setpoint of the multi-module nuclear thermal power system is determined. For example, the adjustment amount for the feedwater pump speed setpoint is determined according to the following formula:

[0093]

[0094] In the above formula, This is the adjustment amount for the feedwater pump speed setpoint. This is the first proportional control gain. is the first integral time constant.

[0095] The adjustment amount of the thermal power setpoint of the multi-module nuclear thermoelectric system is determined based on the aforementioned deviation and the second proportional-integral control algorithm. For example, the adjustment amount of the thermal power setpoint is determined according to the following formula:

[0096]

[0097] In the above formula, The adjustment amount for the thermal power setpoint. This is the second proportional control gain. This is the second integral time constant.

[0098] In step S103, the feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so as to reduce the deviation.

[0099] For example, the feedwater pump speed setting value of the multi-module nuclear thermal power system can be adjusted as follows: based on the adjustment amount of the feedwater pump speed setting value, the hydraulic coupler scoop position setting value of the feedwater pump of the multi-module nuclear thermal power system is adjusted to adjust the speed of the feedwater pump.

[0100] As another example, the thermal power setpoint of the nuclear steam supply system module can be adjusted in at least one of the following ways.

[0101] Method 1: The thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setpoint, so that the nuclear steam supply system module adjusts the feedwater flow rate based on the adjusted thermal power setpoint. For example, the nuclear steam supply system module can control the feedwater flow rate according to the feedwater flow rate control logic of the nuclear steam supply system module described above. This method can achieve a balance between the feedwater flow rate and the steam flow rate of the heating system.

[0102] Method 2: Adjust the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint, so that the nuclear steam supply system module adjusts the nuclear power based on the adjusted thermal power setpoint. For example, the nuclear steam supply system module can control the nuclear power according to the nuclear power control logic of the nuclear steam supply system module described above, such as adjusting the position of the control rod to adjust the nuclear power.

[0103] Method 3: Adjust the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint, so that the nuclear steam supply system module adjusts the primary coolant flow rate based on the adjusted thermal power setpoint. For example, the nuclear steam supply system module can control the primary coolant flow rate according to the primary coolant flow rate control logic of the nuclear steam supply system module described above. This method can achieve a balance between thermal power and nuclear power.

[0104] The above-mentioned method for adjusting the thermal power setpoint of the nuclear steam supply system module can be applied to some or all of the nuclear steam supply system modules of the multi-module nuclear thermoelectric system. Preferably, when adjusting the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint, the thermal power setpoint of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermoelectric system can be adjusted based on the adjustment amount of the thermal power setpoint.

[0105] For example, based on the aforementioned deviation, at least one nuclear steam supply system module participating in the main steam pressure control can be determined from all the nuclear steam supply system modules of the multi-module nuclear thermoelectric system; with reference to... Figure 1 Taking the multi-module nuclear thermoelectric system as an example, if the deviation reaches the first threshold but does not reach x times the first threshold, then n nuclear steam supply system modules in the multi-module nuclear thermoelectric system are identified as nuclear steam supply system modules participating in the main steam pressure control. If the deviation reaches x times the first threshold but does not reach y times the first threshold, then m nuclear steam supply system modules in the multi-module nuclear thermoelectric system are identified as nuclear steam supply system modules participating in the main steam pressure control. If the deviation reaches y times the first threshold, then p nuclear steam supply system modules in the multi-module nuclear thermoelectric system are identified as nuclear steam supply system modules participating in the main steam pressure control, where x is less than y, and m is greater than n and less than p.

[0106] For another example, at least one nuclear steam supply system module participating in the main steam pressure control can be determined from all the nuclear steam supply system modules of the multi-module nuclear thermal power system according to user instructions. That is, the user (e.g., the staff of the multi-module nuclear thermal power system) has pre-configured the nuclear steam supply system module participating in the main steam pressure control.

[0107] In the two examples above, it is preferable that the number of nuclear steam supply system modules involved in main steam pressure control does not exceed half of the total number of nuclear steam supply system modules in a multi-module nuclear thermoelectric system.

[0108] This step, adjusting the feedwater pump speed setpoint and the thermal power setpoint of the nuclear steam supply system module, aims to reduce the deviation between the main steam measurement value and the main steam setpoint. A cutoff condition can be preset to terminate this adjustment step. Preferably, this step can be performed as follows: adjusting the feedwater pump speed setpoint of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setpoint, and adjusting the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setpoint, until the deviation is reduced to below a second threshold, wherein the second threshold is less than the first threshold.

[0109] By setting the second threshold to be less than the first threshold, it is possible to avoid adjusting the feedwater pump speed and the thermal power of the nuclear steam supply system module too frequently when the main steam measurement value fluctuates, thereby avoiding fluctuations in various process parameters of the system caused by frequent adjustments.

[0110] In summary, when there is a deviation between the set value and the measured value of the main steam pressure, this method reduces the deviation by adjusting the speed of the system's feedwater pump and the thermal power of at least one nuclear steam supply system module. It can quickly respond to the heat load fluctuations of the heating system when the opening of the main steam regulating valve is fixed, thereby ensuring that the steam pressure entering the heating system meets the heat load requirements of the heating system and improving the stability of the heating effect of the heating system.

[0111] Please refer to the appendix. Figure 3 The example illustrates the control logic of the primary frequency modulation method obtained by combining the above embodiments:

[0112] First, the user (e.g., staff of a multi-module nuclear thermal power system) sets the number and number of the nuclear steam supply system modules that participate in the main steam pressure control within the system, that is, selects several nuclear steam supply system modules to participate in the main steam pressure control.

[0113] Next, the measured value of the main steam pressure is obtained and compared with the set value of the main steam pressure. The deviation between the two is sent to the main steam pressure controller. When the deviation between the two is greater than the first threshold, the main steam pressure controller adjusts the set value of the feedwater pump speed and the set value of the thermal power of the nuclear steam supply system module participating in the main steam pressure control according to the deviation.

[0114] With attachment Figure 1Using a multi-module nuclear thermoelectric system as an example, the typical application scenario of this method is described in detail. The operator selects three nuclear steam supply system modules to participate in the main steam pressure control. At this time, when the load on the heating system decreases, the main steam pressure rises, the feedwater flow rate of all nuclear steam supply system modules decreases, the evaporator outlet steam temperature rises, and consequently, the main steam temperature rises. These deviations drive the control method of this invention to take action. The main steam pressure controller reduces the hydraulic coupler scoop position setpoint using a proportional-integral algorithm, directly and quickly compensating for the main steam pressure by reducing the feedwater pump speed. The main steam pressure controller also reduces the thermal power setpoint of the selected nuclear steam supply system modules using a proportional-integral algorithm, achieving a balance between the total feedwater flow rate and the steam flow rate corresponding to the heating system load by reducing the feedwater flow rate of these modules. All nuclear steam supply system module steam temperature controllers reduce the primary loop helium flow rate setpoint. By reducing the primary loop helium flow rate, the evaporator outlet steam temperature is maintained. If the module thermal power setpoint remains unchanged, the primary loop helium flow rate returns to its original value after a transient period; otherwise, it decreases along with the set power. The selected nuclear steam supply system module's nuclear power controller lowers the nuclear power setpoint by reducing the control rod position, thereby balancing nuclear power with thermal power.

[0115] The reason this method simultaneously adjusts the feedwater pump speed and the thermal power setpoint of selected nuclear steam supply system modules is as follows: When a deviation occurs between the measured main steam pressure and the setpoint, reducing the main steam pressure deviation solely by adjusting the feedwater pump speed would cause a change in feedwater flow. This change in flow would further drive the feedwater flow controller to maintain the flow at the setpoint, which in turn would increase the deviation between the main steam pressure and the setpoint, having the opposite effect. Therefore, this invention, while adjusting the feedwater pump speed, simultaneously adjusts the thermal power setpoint of the nuclear steam supply system modules involved in main steam pressure control to maintain consistency between the feedwater flow and the corresponding steam flow of the heating system.

[0116] According to a second aspect of the embodiments of this disclosure, a main steam pressure control device for a multi-module nuclear thermoelectric system is provided. Please refer to the appendix. Figure 4 The device includes:

[0117] The acquisition module 401 is used to acquire the measured value of the main steam pressure of the multi-module nuclear thermal power system when the opening degree of the main steam regulating valve of the multi-module nuclear thermal power system is fixed.

[0118] The determining module 402 is used to determine the adjustment amount of the feedwater pump speed setting value and the thermal power setting value of the multi-module nuclear thermal power system based on the deviation if the deviation between the measured value of the main steam pressure and the set value of the main steam pressure of the multi-module nuclear thermal power system is greater than a first threshold.

[0119] The adjustment module 403 is used to adjust the feedwater pump speed of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setting value, and to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, so as to reduce the deviation.

[0120] In one embodiment of this disclosure, the determining module is used to:

[0121] Based on the deviation and the first proportional-integral control algorithm, the adjustment amount of the feedwater pump speed setpoint of the multi-module nuclear thermal power system is determined;

[0122] The adjustment amount of the thermal power setpoint of the multi-module nuclear thermoelectric system is determined based on the deviation and the second proportional-integral control algorithm.

[0123] In one embodiment of this disclosure, when the adjustment module is used to adjust the feedwater pump speed setting value of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setting value, it is used for:

[0124] Based on the adjustment amount of the feedwater pump speed setting value, the hydraulic coupler scoop position setting value of the feedwater pump of the multi-module nuclear thermal power system is adjusted to adjust the speed of the feedwater pump.

[0125] In one embodiment of this disclosure, when the adjustment module adjusts the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint, it is used to:

[0126] The thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system is adjusted based on the adjustment amount of the thermal power setpoint, so that the nuclear steam supply system module adjusts the feedwater flow rate based on the adjusted thermal power setpoint.

[0127] In one embodiment of this disclosure, when the adjustment module adjusts the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint, it is used to:

[0128] The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the nuclear power based on the adjusted thermal power setting value.

[0129] In one embodiment of this disclosure, when the adjustment module adjusts the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint, it is used to:

[0130] The thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system is adjusted based on the adjustment amount of the thermal power setpoint, so that the nuclear steam supply system module adjusts the primary coolant flow rate based on the adjusted thermal power setpoint.

[0131] In one embodiment of this disclosure, the apparatus further includes a selection module for:

[0132] Based on the deviation, at least one nuclear steam supply system module that participates in the main steam pressure control is determined from all the nuclear steam supply system modules of the multi-module nuclear thermoelectric system.

[0133] When the adjustment module is used to adjust the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint, it is used for:

[0134] Based on the adjustment amount of the thermal power setpoint, the thermal power setpoint of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermoelectric system is adjusted.

[0135] In one embodiment of this disclosure, the apparatus further includes a selection module for:

[0136] According to user instructions, at least one nuclear steam supply system module is identified from all the nuclear steam supply system modules of the multi-module nuclear thermoelectric system that participates in the main steam pressure control.

[0137] When the adjustment module is used to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, it is used to: adjust the thermal power setting value of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value.

[0138] In one embodiment of this disclosure, the adjustment module is used to:

[0139] The feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, until the deviation is reduced to below a second threshold, wherein the second threshold is less than the first threshold.

[0140] In one embodiment of this disclosure, the main steam regulating valve of the multi-module nuclear thermal power system is used to fix the opening degree when the turbine intake air volume is fixed or when the turbine is under maintenance.

[0141] Regarding the apparatus in the above embodiments, the specific manner in which each module performs its operation has been described in detail in the embodiments of the method in the first aspect, and will not be elaborated upon here.

[0142] According to a third aspect of the present disclosure, a computer program product is provided, including a computer program / instructions that, when executed by a processor, implement the steps of the method described in the first aspect.

[0143] According to the fourth aspect of the embodiments of this disclosure, please refer to the appendix. Figure 5 The diagram illustrates, for example, a block diagram of an electronic device. For instance, device 500 could be a mobile phone, computer, digital broadcasting terminal, messaging device, game console, tablet device, medical device, fitness equipment, personal digital assistant, etc.

[0144] Reference Figure 5 The device 500 may include one or more of the following components: processing component 502, memory 504, power supply component 506, multimedia component 508, audio component 510, input / output (I / O) interface 512, sensor component 514, and communication component 516.

[0145] Processing component 502 typically controls the overall operation of device 500, such as operations associated with display, telephone calls, data communication, camera operation, and recording. Processing component 502 may include one or more processors 520 to execute instructions to perform all or part of the steps of the methods described above. Furthermore, processing component 502 may include one or more modules to facilitate interaction between processing component 502 and other components. For example, processing component 502 may include a multimedia module to facilitate interaction between multimedia component 508 and processing component 502.

[0146] Memory 504 is configured to store various types of data to support the operation of device 500. Examples of this data include instructions for any application or method operating on device 500, contact data, phonebook data, messages, pictures, videos, etc. Memory 504 can be implemented by any type of volatile or non-volatile storage device or a combination thereof, such as static random access memory (SRAM), electrically erasable programmable read-only memory (EEPROM), erasable programmable read-only memory (EPROM), programmable read-only memory (PROM), read-only memory (ROM), magnetic storage, flash memory, magnetic disk, or optical disk.

[0147] The power supply component 506 provides power to the various components of the device 500. The power supply component 506 may include a power management system, one or more power sources, and other components associated with generating, managing, and distributing power to the device 500.

[0148] Multimedia component 508 includes a screen that provides an output interface between the device 500 and the user. In some embodiments, the screen may include a liquid crystal display (LCD) and a touch panel (TP). If the screen includes a touch panel, the screen may be implemented as a touchscreen to receive input signals from the user. The touch panel includes one or more touch sensors to sense touch, swipe, and gestures on the touch panel. The touch sensors may sense not only the boundaries of the touch or swipe action but also the duration and pressure associated with the touch or swipe operation. In some embodiments, multimedia component 508 includes a front-facing camera and / or a rear-facing camera. When the device 500 is in an operating mode, such as a shooting mode or a video mode, the front-facing camera and / or the rear-facing camera may receive external multimedia data. Each front-facing camera and rear-facing camera may be a fixed optical lens system or have focal length and optical zoom capabilities.

[0149] Audio component 510 is configured to output and / or input audio signals. For example, audio component 510 includes a microphone (MIC) configured to receive external audio signals when device 500 is in an operating mode, such as call mode, recording mode, and voice recognition mode. The received audio signals may be further stored in memory 504 or transmitted via communication component 516. In some embodiments, audio component 510 also includes a speaker for outputting audio signals.

[0150] I / O interface 512 provides an interface between processing component 502 and peripheral interface modules, such as keyboards, click wheels, buttons, etc. These buttons may include, but are not limited to, home buttons, volume buttons, power buttons, and lock buttons.

[0151] Sensor assembly 514 includes one or more sensors for providing status assessments of various aspects of device 500. For example, sensor assembly 514 may detect the on / off state of device 500, the relative positioning of components such as the display and keypad of device 500, changes in the position of device 500 or a component of device 500, the presence or absence of user contact with device 500, the orientation or acceleration / deceleration of device 500, and temperature changes of device 500. Sensor assembly 514 may also include a proximity sensor configured to detect the presence of nearby objects without any physical contact. Sensor assembly 514 may also include a light sensor, such as a CMOS or CCD image sensor, for use in imaging applications. In some embodiments, sensor assembly 514 may also include an accelerometer, a gyroscope, a magnetometer, a pressure sensor, or a temperature sensor.

[0152] Communication component 516 is configured to facilitate wired or wireless communication between device 500 and other devices. Device 500 can access wireless networks based on communication standards, such as WiFi, 2G or 3G, 4G or 5G, or combinations thereof. In one exemplary embodiment, communication component 516 receives broadcast signals or broadcast-related information from an external broadcast management system via a broadcast channel. In one exemplary embodiment, communication component 516 also includes a near-field communication (NFC) module to facilitate short-range communication. For example, the NFC module may be implemented based on radio frequency identification (RFID) technology, Infrared Data Association (IrDA) technology, ultra-wideband (UWB) technology, Bluetooth (BT) technology, and other technologies.

[0153] In an exemplary embodiment, device 500 may be implemented by one or more application-specific integrated circuits (ASICs), digital signal processors (DSPs), digital signal processing devices (DSPDs), programmable logic devices (PLDs), field-programmable gate arrays (FPGAs), controllers, microcontrollers, microprocessors, or other electronic components to perform the main steam control method of the aforementioned electronic device.

[0154] Fifthly, in exemplary embodiments, this disclosure also provides a non-transitory computer-readable storage medium including instructions, such as a memory 504 including instructions, which can be executed by a processor 520 of device 500 to complete the main steam control method of the electronic device. For example, the non-transitory computer-readable storage medium may be a ROM, random access memory (RAM), CD-ROM, magnetic tape, floppy disk, and optical data storage device, etc.

[0155] Other embodiments of this disclosure will readily occur to those skilled in the art upon consideration of the specification and practice of the disclosure herein. This disclosure 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 disclosed herein. The specification and examples are to be considered exemplary only, and the true scope and spirit of this disclosure are indicated by the following claims.

[0156] It should be understood that this disclosure is not limited to the precise structures described above and shown in the accompanying drawings, and various modifications and changes can be made without departing from its scope. The scope of this disclosure is limited only by the appended claims.

Claims

1. A method for controlling the main steam pressure of a multi-module nuclear thermoelectric system, characterized in that, The method includes: With the main steam regulating valve opening of the multi-module nuclear thermal power system fixed, the main steam pressure measurement value of the multi-module nuclear thermal power system is obtained; If the deviation between the measured value of the main steam pressure and the set value of the main steam pressure of the multi-module nuclear thermal power system is greater than the first threshold, then the adjustment amount of the set value of the feedwater pump speed and the set value of the thermal power of the multi-module nuclear thermal power system are determined according to the deviation. The feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so as to reduce the deviation.

2. The main steam pressure control method for a multi-module nuclear thermoelectric system according to claim 1, characterized in that, The step of determining the adjustment amount of the feedwater pump speed setpoint and the thermal power setpoint of the multi-module nuclear thermal power system based on the deviation includes: Based on the deviation and the first proportional-integral control algorithm, the adjustment amount of the feedwater pump speed setpoint of the multi-module nuclear thermal power system is determined; The adjustment amount of the thermal power setpoint of the multi-module nuclear thermoelectric system is determined based on the deviation and the second proportional-integral control algorithm.

3. The main steam pressure control method for a multi-module nuclear thermoelectric system according to claim 1, characterized in that, The adjustment of the feedwater pump speed setpoint of the multi-module nuclear cogeneration system based on the adjustment amount of the feedwater pump speed setpoint includes: Based on the adjustment amount of the feedwater pump speed setting value, the hydraulic coupler scoop position setting value of the feedwater pump of the multi-module nuclear thermal power system is adjusted to adjust the speed of the feedwater pump.

4. The main steam pressure control method for a multi-module nuclear thermoelectric system according to claim 1, characterized in that, The adjustment of the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint includes: The thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system is adjusted based on the adjustment amount of the thermal power setpoint, so that the nuclear steam supply system module adjusts the feedwater flow rate based on the adjusted thermal power setpoint.

5. The main steam pressure control method for a multi-module nuclear thermoelectric system according to claim 1, characterized in that, The adjustment of the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint includes: The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the nuclear power based on the adjusted thermal power setting value.

6. The main steam pressure control method for a multi-module nuclear thermoelectric system according to claim 1, characterized in that, The adjustment of the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint includes: The thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system is adjusted based on the adjustment amount of the thermal power setpoint, so that the nuclear steam supply system module adjusts the primary coolant flow rate based on the adjusted thermal power setpoint.

7. The main steam pressure control method for a multi-module nuclear thermoelectric system according to claim 1, characterized in that, The method further includes: Based on the deviation, at least one nuclear steam supply system module that participates in the main steam pressure control is determined from all the nuclear steam supply system modules of the multi-module nuclear thermoelectric system. The adjustment of the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint includes: Based on the adjustment amount of the thermal power setpoint, the thermal power setpoint of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermoelectric system is adjusted.

8. The main steam pressure control method for a multi-module nuclear thermoelectric system according to claim 1, characterized in that, The method further includes: According to user instructions, at least one nuclear steam supply system module is identified from all the nuclear steam supply system modules of the multi-module nuclear thermoelectric system to participate in the main steam pressure control; The adjustment of the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power setpoint includes: Based on the adjustment amount of the thermal power setpoint, the thermal power setpoint of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermoelectric system is adjusted.

9. The main steam pressure control method for a multi-module nuclear thermoelectric system according to claim 1, characterized in that, The adjustment of the feedwater pump speed setpoint of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setpoint, and the adjustment of the thermal power setpoint of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setpoint, to reduce the deviation, includes: The feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, until the deviation is reduced to below a second threshold, wherein the second threshold is less than the first threshold.

10. The main steam pressure control method for a multi-module nuclear thermoelectric system according to claim 1, characterized in that, The main steam regulating valve of the multi-module nuclear thermal power system is used to fix the opening degree when the turbine intake air volume is fixed or when the turbine is under maintenance.

11. A main steam pressure control device for a multi-module nuclear thermoelectric system, characterized in that, The device includes: The acquisition module is used to acquire the measured value of the main steam pressure of the multi-module nuclear thermal power system when the opening degree of the main steam regulating valve of the multi-module nuclear thermal power system is fixed. The determination module is used to determine the adjustment amount of the feedwater pump speed setting value and the thermal power setting value of the multi-module nuclear thermal power system based on the deviation if the deviation between the measured value of the main steam pressure and the set value of the main steam pressure of the multi-module nuclear thermal power system is greater than a first threshold. An adjustment module is used to adjust the feedwater pump speed of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setting value, and to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, so as to reduce the deviation.

12. A computer program product comprising a computer program / instructions, characterized in that, When the computer program / instructions are executed by the processor, they implement the steps of the method described in any one of claims 1 to 10.

13. An electronic device, characterized in that, The electronic device includes a memory and a processor, the memory being used to store computer instructions that can be executed on the processor, and the processor being used to implement the method of any one of claims 1 to 10 when executing the computer instructions.

14. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the program is executed by the processor, it implements the method of any one of claims 1 to 10.

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