Method of performing a curve calibration experiment, electronic device and computer program product

Abstract

The embodiment of the application is suitable for the field of nuclear power technology, and provides an execution method of curve calibration experiment, an electronic device and a computer program product. The method comprises the following steps: if a step deviation event is identified at any moment when the curve calibration experiment is executed, determining the maximum deviation step number corresponding to the power control rod based on the deviation step number of the power control rod at at least one expected rod position; the curve calibration experiment is used for curve calibration of a relationship curve between the power control rod and the load; determining a correction factor corresponding to the relationship curve according to the maximum deviation step number; if the correction factor satisfies a power adjustment condition, inputting the correction factor into a power adjustment function to determine an initial power corresponding to a nuclear power unit where the power control rod is located; and executing the curve calibration experiment based on the initial power, the correction factor and the relationship curve. Through the method provided in the embodiment, the safety of the curve calibration experiment of the nuclear power unit in the case of step deviation can be improved.

Description

TECHNICAL FIELD

[0001] The embodiment of the present application belongs to the technical field of nuclear power, and particularly relates to an execution method of a curve calibration experiment, an electronic device and a computer program product. BACKGROUND

[0002] The G9 curve is a curve describing the relationship between the rod position of a power control rod and the working load of a steam turbine in a nuclear power unit, and has great guiding significance in the actual operation of a nuclear power plant. However, in the actual operation of the nuclear power plant, the relationship between the rod position of the power control rod and the working load of the steam turbine will change due to actual conditions, and therefore, the operator needs to calibrate the G9 curve through a curve calibration experiment at regular intervals.

[0003] In the execution of the curve calibration experiment, the operator can first adjust the initial power of one loop component in the nuclear power unit to the maximum power, and then control the power control rod to move according to the G9 curve to be adjusted, and record the actual working load of the steam turbine corresponding to the power control rod at different rod positions. Finally, the operator can generate a new G9 curve by processing the recorded data.

[0004] However, in the case that the actual rod position inserted under a certain power control rod deviates from the expected rod position corresponding to the power control rod, that is, in the case that the power control rod has a step deviation, directly executing the curve calibration experiment according to the G9 curve to be adjusted and the maximum power may cause the actual insertion position of the power control rod to exceed the rod position threshold, and then cause the reactor to overheat, thereby causing a safety accident. SUMMARY

[0005] Therefore, the embodiment of the present application provides an execution method of a curve calibration experiment, an electronic device and a computer program product, to improve the safety of executing the curve calibration experiment under the step deviation, so that the curve calibration experiment can be performed in the case that the power control rod has a step deviation.

[0006] The first aspect of the embodiment of the present application provides an execution method of a curve calibration experiment, comprising:

[0007] If a step deviation event is identified at any time during the execution of the curve calibration experiment, the maximum deviation step number corresponding to the power control rod is determined based on the deviation step number of the power control rod at at least one expected rod position; and the curve calibration experiment is used to calibrate the relationship curve between the power control rod and the load.

[0008] The correction factor corresponding to the relationship curve is determined according to the maximum deviation step number.

[0009] If the correction factor meets a power adjustment condition, the correction factor is input into a preset power adjustment function to determine an initial power corresponding to the nuclear power unit in which the power control rod is located.

[0010] The curve calibration experiment is performed based on the initial power, the correction factor and the relationship curve.

[0011] In a possible implementation of the first aspect, if the correction factor meets a power adjustment condition, the correction factor is input into a preset power adjustment function to determine an initial power corresponding to the nuclear power unit in which the power control rod is located.

[0012] The correction factor is input into a preset temperature estimation function to determine an expected maximum temperature corresponding to the correction factor.

[0013] If the expected maximum temperature corresponding to the correction factor is greater than a preset temperature threshold, the correction factor is input into a preset power adjustment function to determine an initial power corresponding to the correction factor.

[0014] In a possible implementation of the first aspect, the correction factor is input into a preset temperature estimation function to determine an expected maximum temperature corresponding to the correction factor.

[0015] A temperature change value corresponding to the correction factor is determined based on the correction factor, a rated power generation of the nuclear power unit, an actual power generation of the nuclear power unit, a power coefficient of the nuclear power unit and a temperature coefficient of the nuclear power unit.

[0016] The expected maximum temperature corresponding to the correction factor is determined based on the temperature change value corresponding to the correction factor and a historical maximum temperature of the nuclear power unit.

[0017] The temperature estimation function is specifically as follows:

[0018]

[0019] Wherein, the P is the actual power generation of the nuclear power unit; the P 额 is the rated power generation of the nuclear power unit; the ΔP is the correction factor; the is the power coefficient of the nuclear power unit; the is the temperature coefficient of the nuclear power unit; the T max is the historical maximum temperature of the nuclear power unit; the T est is the expected maximum temperature corresponding to the correction factor; the is the temperature change value corresponding to the correction factor.

[0020] In a possible implementation manner of the first aspect, the inputting the correction factor into a preset power adjustment function to determine the initial power corresponding to the correction factor comprises:

[0021] determining a temperature difference value based on the expected maximum temperature corresponding to the correction factor and a temperature threshold of the nuclear power generating unit;

[0022] determining the initial power corresponding to the correction factor based on the temperature difference value, a rated power generation of the nuclear power generating unit and an actual power generation of the nuclear power generating unit;

[0023] The power adjustment function is specifically as follows:

[0024]

[0025] wherein, the P 初始 is the initial power corresponding to the correction factor; the P is the actual power generation of the nuclear power generating unit; the P 额 is the rated power generation of the nuclear power generating unit; the T est is the expected maximum temperature corresponding to the correction factor; the T limit is the temperature threshold of the nuclear power generating unit; the [T est -T limit ] is the temperature difference value.

[0026] In a possible implementation manner of the first aspect, the determining the correction factor corresponding to the relationship curve based on the maximum deviation step number comprises:

[0027] inputting an expected rod position corresponding to the maximum deviation step number and an actual rod position corresponding to the maximum deviation step number into a preset reactivity algorithm to determine a reactivity difference value corresponding to the maximum deviation step number;

[0028] determining the correction factor corresponding to the relationship curve based on the reactivity difference value and a power coefficient of the nuclear power generating unit.

[0029] In a possible implementation manner of the first aspect, the determining the correction factor corresponding to the relationship curve based on the maximum deviation step number comprises:

[0030] determining a maximum deviation rod position corresponding to each expected rod position of the power control rod based on the maximum deviation step number;

[0031] for any expected rod position of the power control rod, determining a power difference value between the any expected rod position and the maximum deviation rod position corresponding to the any expected rod position based on the relationship curve;

[0032] The maximum value of all the power difference values is taken as the correction factor.

[0033] In a possible implementation manner of the first aspect, after the maximum deviation step number is input into a preset correction algorithm to generate a correction factor corresponding to the relationship curve, the method further includes:

[0034] If the correction factor does not satisfy a power adjustment condition, a preset maximum power value is taken as the initial power.

[0035] In a possible implementation manner of the first aspect, after the correction factor is input into a preset power adjustment function to determine an initial power corresponding to the correction factor, the method further includes:

[0036] If the initial power is greater than or equal to a preset power threshold value, the curve calibration experiment is performed based on the initial power, the correction factor and the relationship curve.

[0037] If the initial power is less than the power threshold value, first alarm information is generated; the first alarm information is used to prompt that the user cannot perform the curve calibration experiment.

[0038] The second aspect of the embodiment of the present application provides an execution device of a curve calibration experiment, including:

[0039] A step number determination module is configured to determine a maximum deviation step number corresponding to a power control rod based on a deviation step number of the power control rod at at least one expected rod position, if a step deviation event is identified at any moment of performing a curve calibration experiment; the curve calibration experiment is used to perform curve calibration on a relationship curve between the power control rod and a load.

[0040] A correction factor determination module is configured to determine a correction factor corresponding to the relationship curve according to the maximum deviation step number.

[0041] A power adjustment module is configured to input the correction factor into a preset power adjustment function to determine an initial power corresponding to a nuclear power generating unit in which the power control rod is located, if the correction factor satisfies a power adjustment condition.

[0042] An experiment execution module is configured to perform the curve calibration experiment based on the initial power, the correction factor and the relationship curve.

[0043] The third aspect of the embodiment of the present application provides an electronic device, including a memory, a processor and a computer program stored in the memory and executable on the processor, and the processor implements the execution method of the curve calibration experiment according to the first aspect when executing the computer program.

[0044] The fourth aspect of the embodiment of the present application provides a computer readable storage medium, which stores a computer program, and the computer program is executed by a processor to implement the execution method of the curve calibration experiment according to the first aspect.

[0045] The fifth aspect of the embodiment of the present application provides a computer program product, which, when running on a computer, causes the computer to execute the execution method of the curve calibration experiment according to the first aspect.

[0046] Compared with the prior art, the embodiment of the present application has the following advantages:

[0047] In the embodiment of the present application, after the electronic device identifies the step deviation event, the correction factor can be determined according to the maximum deviation step number of the power control rod, and the curve calibration experiment is performed in combination with the correction factor and the relationship curve, that is, in the process of performing the curve calibration experiment, the electronic device can drive the power control rod to operate according to the correction factor, and since the correction factor is determined based on the maximum deviation step number of the power control rod, the method provided in the embodiment can make the power control rod be located within the rod position threshold of the power control rod even when the power control rod moves to the rod position corresponding to the maximum deviation step number, thereby improving the safety of the nuclear power unit in performing the curve calibration experiment in the case of step deviation.

[0048] Further, since the electronic device can determine whether the current situation meets the power adjustment condition according to the correction factor corresponding to the maximum deviation step number, and adjust the initial power of the nuclear power unit in performing the curve calibration experiment through the correction factor and the power adjustment function when the power adjustment condition is met, the method provided in the embodiment can reduce the probability of overheating caused by the initial power being too high when the nuclear power unit performs the curve calibration experiment based on the correction factor, and further improve the safety of performing the curve calibration experiment in the case of step deviation. BRIEF DESCRIPTION OF DRAWINGS

[0049] In order to more clearly illustrate the technical solutions in the embodiments of the present application, the following will briefly introduce the drawings needed to be used in the embodiments or the prior art description. Obviously, the drawings in the following description are only some embodiments of the present application, and those skilled in the art can obtain other drawings according to these drawings without creative labor.

[0050] Figure 1 is a schematic diagram of a step sequence of a power control rod provided by the embodiment of the present application;

[0051] Figure 2 is a schematic diagram of an execution method of a curve calibration experiment provided by the embodiment of the present application;

[0052] Figure 3 is a motion logic schematic diagram of a power control rod provided by an embodiment of the present application;

[0053] Figure 4 is a schematic diagram of another execution method of a curve calibration experiment provided by an embodiment of the present application;

[0054] Figure 5 is an implementation flow schematic diagram of a curve calibration experiment provided by an embodiment of the present application;

[0055] Figure 6 is a schematic diagram of an execution device of a curve calibration experiment provided by an embodiment of the present application;

[0056] Figure 7 is a schematic diagram of an electronic device provided by an embodiment of the present application. DETAILED DESCRIPTION

[0057] In the following description, specific details are set forth, such as particular system configurations, techniques, etc., in order to provide a thorough understanding of the present application. However, persons skilled in the art will understand that the present application can be practiced in other embodiments that depart from these specific details. In other instances, detailed descriptions of well-known systems, apparatuses, circuits, and methods are omitted in order to not obscure the description of the present application with unnecessary detail.

[0058] In a nuclear power unit of a nuclear reactor type of a pressurized water reactor type, the nuclear power unit is usually operated in a "G" mode. In a base load state of the "G" mode operation, a power control rod is a key tool for controlling the power of the nuclear reactor. Through the power control rod, the staff can quickly and efficiently adjust the power of the nuclear reactor, thereby improving the flexibility and stability of the power regulation during the operation of the nuclear power unit, so that the power output by the nuclear power unit can meet the power demand that changes over time.

[0059] Referring to Figure 1 , a step sequence schematic diagram of a power control rod provided by an embodiment of the present application is shown. As Figure 1As shown, when the power control rod is located at the bottom of the reactor, the corresponding extraction step number thereof can be 5; when the power control rod is located at the top of the reactor, the corresponding extraction step number of the power control rod can be 225. Since the action sequences of different power control rods are different, the extraction step numbers of the power control rods can be different at different rod positions. The extraction step number can represent the number of steps that the power control rod is extracted outward from the initial position, and the extraction step number can be used to reflect the degree of movement of the power control rod outside the core. The N2 rod can be gradually extracted from the rod position of 0, the N1 rod can be gradually extracted from the rod position of 135, the G2 rod can be gradually extracted from the rod position of 270, and the G1 rod can be gradually extracted from the rod position of 405. When the rod position is 625, that is, all the power control rods have been extracted, at this time, all the power control rods are located at the top of the reactor.

[0060] In the operation of the nuclear power unit, the R&D personnel can first set the G9 curve corresponding to the nuclear power unit on the control device of the nuclear power unit, and then the control device can automatically control the operation of the power control rod in the nuclear power unit according to the real-time power demand and the G9 curve, so that the power output by the nuclear power unit can effectively respond to the change of the power demand of the power grid. The G9 curve is a curve used to represent the relationship between the rod position of the power control rod and the load of the steam turbine. The load of the steam turbine generally refers to the power load borne by the steam turbine in the nuclear power unit, that is, the size of the power that the steam turbine needs to generate. On the G9 curve, the rod position of each power control rod corresponds to a specific steam turbine load (or output power). For example, when the power demand of the power grid increases, the control device can automatically control the power control rod to move to the rod position corresponding to the current power demand according to the G9 curve, thereby increasing the power output by the nuclear power unit.

[0061] The power control rods in the nuclear power unit can include G1 rods, G2 rods, N1 rods and N2 rods. Specifically, the G1 rods and the G2 rods are mainly used for fine adjustment of the reactor power. In the stable operation stage of the nuclear power unit, when the staff needs to make a small and accurate adjustment to the reactor power, the G1 rods and the G2 rods can be used for adjustment. The N1 rods and the N2 rods are mainly used for compensating for the change of the reactor reactivity. During the operation of the reactor, the reactivity will change due to various factors, such as fuel burnup, change of coolant temperature, etc. At this time, in order to maintain the stable operation of the reactor, the staff can compensate for the change of the reactor reactivity by using the N1 rods and the N2 rods. In the process of adjusting the reactor power, different power adjustment rods can act in a certain sequence and overlapping relationship to achieve accurate and stable power control.

[0062] However, in the actual operation of the nuclear power unit, due to the factors such as reactor refueling and reactor burnup change, the power distribution of the reactor will change, that is, the reactor power caused by the power control rod at the same position may change, thereby causing the power generated by the nuclear power unit at the same position of the power control rod to change. Therefore, in order to improve the accuracy of the G9 curve, the staff of the nuclear power unit needs to perform a curve calibration experiment on the G9 curve regularly. However, during the process of performing a curve calibration experiment by the staff at a certain time, it is found that there is a 2-step deviation between the actual rod position of a certain power control rod and the expected rod position corresponding to the power control rod, that is, a step deviation event occurs for a certain power control rod. After the staff investigates and studies the deviation of the control rod in detail, it is confirmed that the step deviation event is caused by the defect of the logic configuration of the power control rod, and the staff cannot correct the logic configuration in a short time, and needs to upgrade the logic configuration in cooperation with the manufacturer of the power control rod to solve the problem.

[0063] Further, if the curve calibration experiment cannot be performed, the accuracy of the G9 curve will be low. Controlling the nuclear power unit to run through the G9 curve with low accuracy is easy to cause the power generated by the nuclear power unit to be unmatched with the power demand of the power grid. For example, when the power needs to be increased, according to the inaccurate G9 curve, the rod position of the power control rod is inaccurate. If the rod position of the power control rod moves too much, the reactor power will rise too fast, exceed the target power, and may cause the nuclear power unit to run in excess power; if the rod position of the power control rod moves too little, the expected power increase effect cannot be achieved, and the power grows slowly, which cannot meet the power demand of the power grid.

[0064] Therefore, the researchers need to propose a method capable of performing a curve calibration experiment in the step deviation state of the power control rod. The technical solutions of the present application are described below through specific embodiments.

[0065] Reference Figure 2 , a schematic diagram of a curve calibration experiment execution method provided by an embodiment of the present application is shown, which can specifically include the following steps:

[0066] S201, if a step deviation event is identified at any time during the execution of the curve calibration experiment, the maximum deviation step number corresponding to the power control rod is determined based on the deviation step number of the power control rod at at least one expected rod position.

[0067] In this embodiment, during the execution of the curve calibration experiment, the electronic device can continuously detect whether a step deviation event occurs in each power control rod in the nuclear power unit. If the electronic device does not detect a step deviation event during the execution of the curve calibration experiment, the electronic device can continue to execute the curve calibration experiment. If the electronic device identifies a step deviation event in any one of the power control rods in the nuclear power unit at any time during the execution of the curve calibration experiment, the electronic device can execute the method in embodiments S201-S204 to safely execute the curve calibration experiment in the step deviation state. For example, the electronic device can identify a step deviation event in the preparation stage of the curve calibration experiment, or identify a step deviation event during the execution of the curve calibration experiment. When the electronic device identifies a step deviation event during the execution of the curve calibration experiment, in order to prevent a safety event from occurring in the nuclear power unit, the electronic device can send a stop instruction to the nuclear power unit to control the nuclear power unit to stop executing the curve calibration experiment. The electronic device can also generate first alarm information and display the first alarm information through the display device to inform the staff that a step deviation event has occurred in a power control rod in the nuclear power unit. After identifying a step deviation event, in order to improve the safety of the nuclear power unit in the step deviation state of the power control rod, the electronic device can execute the method in embodiments S201-S204 to safely execute the curve calibration experiment in the step deviation state.

[0068] Specifically, the electronic device can first obtain the deviation step numbers corresponding to each expected rod position of the power control rod that has a step deviation event. Then, the electronic device can determine the maximum deviation step number corresponding to the power control rod according to the deviation step numbers of the power control rod at all expected rod positions. When only one power control rod in the nuclear power unit has a step deviation event, the electronic device can determine the maximum value of all deviation step numbers corresponding to the power control rod as the maximum deviation step number. When two or more power control rods in the nuclear power unit have a step deviation event, the electronic device can obtain the deviation step numbers corresponding to each expected rod position of all power control rods, and determine the maximum value of all obtained deviation step numbers as the maximum deviation step number.

[0069] The expected rod position can be a rod position value in the down insertion instruction sent by the electronic device to the driving mechanism of the power control rod when controlling the operation of the power control rod, i.e., the rod position value that the power control rod needs to be inserted when the electronic device controls the operation of the power control rod. The deviation step number can be the difference between the actual rod position at which the driving mechanism of the power control rod drives the power control rod to be inserted and the expected rod position in the down insertion instruction after the driving mechanism receives the down insertion instruction. The actual rod position can be the rod position value at which the driving mechanism of the power control rod actually drives the power control rod to be inserted after receiving the down insertion instruction.

[0070] In a possible implementation, during the process of performing the curve calibration experiment, the electronic device can continuously detect the actual rod position of each power control rod in the nuclear power unit through the step counter. For any one power control rod in the nuclear power unit, if the electronic device determines that the actual rod position fed back by the step counter is not equal to the expected rod position that the power control rod should currently reach, the electronic device can determine that the power control rod has a step deviation event. For any one power control rod in the nuclear power unit, if the electronic device determines that the actual rod position fed back by the step counter is equal to the expected rod position that the power control rod should currently reach, the electronic device can determine that the power control rod has no step deviation event.

[0071] S202, determining a correction factor corresponding to the relationship curve according to the maximum deviation step number.

[0072] In this embodiment, after the electronic device determines the maximum deviation step number, the electronic device can determine the correction factor corresponding to the relationship curve according to the maximum deviation step number. After the electronic device determines the maximum deviation step number, the electronic device can calculate the correction factor corresponding to the relationship curve by two different methods.

[0073] Method one: calculating the correction factor through the reactivity difference corresponding to the maximum deviation step number.

[0074] In a possible implementation, after the electronic device determines the maximum deviation step number, when the power control rod is moved to the rod position corresponding to the maximum deviation step number, the electronic device can input the expected rod position corresponding to the power control rod and the actual rod position of the power control rod into a preset reactivity algorithm, so as to calculate the first reactivity corresponding to the expected rod position and the second reactivity corresponding to the actual rod position through the reactivity algorithm. Then, the electronic device can take the difference between the first reactivity and the second reactivity as the reactivity difference between the expected rod position and the actual rod position. The reactivity algorithm in the electronic device can be any algorithm capable of calculating the reactivity of the reactor, such as a point reactor kinetics equation algorithm, a reactivity coefficient algorithm, a Monte Carlo algorithm, etc.

[0075] After determining the reactivity difference, the electronic device can input the reactivity difference and the power coefficient corresponding to the nuclear power unit into a preset correction factor function to determine a correction factor corresponding to the relationship curve through the correction factor function. The power coefficient is a coefficient representing the rate of change of the reactivity of the reactor with the thermal power of the reactor, that is, the value representing the change in reactivity when the thermal power of the reactor changes by one percent. The unit of the power coefficient can be per centimeter per one percent of power (pcm / % power). The power coefficient can be calculated by the electronic device according to the reactor physics model (such as the neutron transport model) preset by the research personnel to analyze and calculate the information of the fuel, coolant, boron concentration, burnup value, etc. of the reactor core. The correction factor function can be specifically as follows.

[0076]

[0077] Wherein, ΔP can be a correction factor. Δp can be a reactivity difference. may be the power coefficient of the nuclear power unit.

[0078] In this embodiment, since the electronic device can calculate the correction factor according to the reactivity difference, that is, the calculation of the power correction factor considers the influence of the step deviation on the reactivity of the reactor. Therefore, the method provided in this embodiment can improve the accuracy of the calculated correction factor.

[0079] Method two, calculating the correction factor through the relationship curve.

[0080] In one possible implementation, after determining the maximum deviation step number, the electronic device can calculate the maximum deviation rod position corresponding to each expected rod position of the power control rod according to the maximum deviation step number. Wherein, the maximum deviation rod position can be the sum of the expected rod position and the maximum deviation step number. For example, when the maximum deviation step number is 4, for the expected rod position with a step number value of 200 in the G9 curve, the corresponding maximum deviation rod position can be 204. Then, the electronic device can determine the power difference value between each expected rod position and the maximum deviation rod position corresponding to the expected rod position according to the G9 curve. Specifically, for any expected rod position, the electronic device can query the G9 curve according to the expected rod position to determine the first working load value of the steam turbine corresponding to the rod position value of the expected rod position in the G9 curve. The electronic device can also query the G9 curve according to the maximum deviation rod position corresponding to the expected rod position to determine the second working load value of the steam turbine corresponding to the rod position value of the maximum deviation rod position in the G9 curve. Then, the electronic device can take the difference between the first working load value and the second working load value as the power difference value. The electronic device can calculate the power difference value corresponding to all expected rod positions of the power control rod respectively, and take the maximum value of all calculated power difference values as the correction factor.

[0081] In this embodiment, after determining the maximum deviation step number, the electronic device can directly determine the correction factor according to the maximum deviation step number and the relationship curve, without the need to combine the reactor model and other data for calculation. Therefore, the method provided in this embodiment has a smaller amount of calculation and higher usability.

[0082] In S203, if the correction factor meets the power adjustment condition, the correction factor is input into a preset power adjustment function to determine the initial power of the nuclear power generating unit corresponding to the power control rod.

[0083] In this embodiment, during the actual curve calibration experiment of the nuclear power generating unit, the addition of the correction factor can cause the action change of the power control rod to lag behind the change of the electric power output by the nuclear power generating unit, and further cause the problem of overheating of the nuclear power generating unit during the experiment. When the nuclear power generating unit is overheated, the bypass discharge system in the nuclear power generating unit is opened to discharge the excess steam generated in the steam generator through the bypass discharge system, so as to avoid the temperature and pressure in the steam generator exceeding the protection threshold, and ensure the safety of the nuclear power generating unit. Since a large amount of steam will be discharged after the bypass discharge system is opened, this can cause the temperature field around the nuclear power generating unit to change. However, in the curve calibration experiment, the temperature is a key parameter for evaluating the thermal performance and reactivity of the nuclear power generating unit. The high-temperature steam discharged by the bypass discharge system can cause the ambient temperature to rise, and further affect the accuracy of the temperature measurement probe in the experiment, so that the measured temperature value deviates from the true value, and the judgment of the experimental result is affected. Therefore, after the correction factor is introduced, in order to reduce the probability of overheating of the nuclear power generating unit and further cause the bypass discharge system to be opened, the electronic device can adjust the initial power of any loop component in the nuclear power generating unit according to the correction factor before the experiment.

[0084] Specifically, the electronic device can determine whether the correction factor meets the power adjustment condition preset by the R&D personnel. If the electronic device determines that the correction factor meets the power adjustment condition, the electronic device can input the correction factor into the power adjustment function preset by the R&D personnel, so as to calculate the initial power of the nuclear power generating unit corresponding to the power control rod through the power adjustment function.

[0085] In a possible implementation, if the electronic device determines that the correction factor does not meet the power adjustment condition, the maximum power preset by the R&D personnel can be used as the initial power of the nuclear power generating unit.

[0086] The nuclear power unit can include a primary loop assembly and a secondary loop assembly. The primary loop assembly is mainly composed of a reactor pressure vessel, a steam generator, a main pump, a pressurizer, and connecting pipelines, etc., and is used to take out the heat energy released by the nuclear reactor during the nuclear fission reaction and transfer the heat energy to the secondary loop assembly. The secondary loop assembly is mainly composed of a steam turbine generator set, a steam generator, a generator, and a cooling system. The secondary loop assembly can convert the heat energy transferred from the primary loop assembly into steam through a heat exchanger, drive the steam turbine to generate mechanical energy, and then drive the generator to generate electricity through the mechanical energy. The initial power determined by the electronic device can be the power of the secondary loop assembly of the nuclear power unit when the curve calibration experiment starts to be performed.

[0087] In S204, the curve calibration experiment is performed based on the initial power, the correction factor, and the relationship curve.

[0088] In this embodiment, after determining the initial power and the correction factor, the electronic device can control the nuclear power unit to perform the curve calibration experiment according to the initial power, the correction factor, and the relationship curve. Specifically, the electronic device can first adjust the power of the secondary loop assembly of the nuclear power unit to the initial power.

[0089] Through the method provided in this embodiment, in the case of a step deviation event, the electronic device can determine the correction factor according to the maximum deviation step number, and adjust the driving strategy of the power control rod of the control rod drive mechanism in combination with the power correction in the curve correction experiment. Therefore, the method provided in this embodiment can reduce the probability that the actual insertion position of the power control rod exceeds the rod position threshold, and thus improve the accuracy of performing the curve calibration experiment in the step deviation state.

[0090] In addition, since the electronic device can determine whether the current situation satisfies the power adjustment condition according to the correction factor corresponding to the maximum deviation step number, and adjust the initial power of the nuclear power unit when performing the curve calibration experiment through the correction factor and the power adjustment function when the power adjustment condition is satisfied, the method provided in this embodiment can reduce the probability of overheating of the nuclear power unit due to the initial power being too high when performing the curve calibration experiment based on the correction factor, and further improve the safety of performing the curve calibration experiment in the step deviation state.

[0091] In a possible implementation, after determining the initial power corresponding to the correction factor by the power adjustment function, the electronic device can determine whether the initial power is greater than or equal to the power threshold set by the R&D personnel in advance. If the electronic device determines that the initial power is greater than or equal to the power threshold, the electronic device can determine that the adjusted initial power can meet the most basic power requirement of the curve calibration experiment. At this time, the electronic device can perform the curve calibration experiment according to the adjusted initial power, the correction factor, and the relationship curve. If the electronic device determines that the initial power is less than the power threshold, the electronic device can determine that the adjusted initial power cannot meet the most basic power requirement of the curve calibration experiment, that is, the curve calibration experiment performed at the initial power does not have practical significance. At this time, the electronic device can generate first warning information and display the first warning information through the display device to prompt the user that the curve calibration experiment cannot be performed.

[0092] By the method provided in this embodiment, after determining the initial power, the electronic device can determine whether the initial power meets the basic requirement of the curve calibration experiment according to the power threshold, and perform the curve calibration experiment only when the initial power is greater than or equal to the power threshold. Therefore, the method provided in this embodiment can improve the usability of the curve calibration experiment performed in the step deviation state.

[0093] Specifically, before the curve calibration experiment is performed, the electronic device can first adjust the power of the secondary loop component in the nuclear power unit to the initial power. Then, the electronic device can start the nuclear power unit to perform the curve calibration experiment. After the curve calibration experiment starts, the electronic device can gradually change the output electric power required by the secondary loop component in the nuclear power unit at a specific rate, and initiate a power control signal containing the output electric power to the control rod drive mechanism to drive the power control rod to operate. In this process, the electronic device can continuously record the key parameters such as the reactor power, the coolant temperature, the pressure, and the actual rod position of the power control rod, so that the researchers can determine the new G9 curve according to all the recorded data after the experiment is completed. For example, the electronic device can reduce the output electric power of the secondary loop component at a certain megawatt per minute, gradually from a high power level to a predetermined low power value, such as from 984 MW to 880 MW, and continuously record the key parameters such as the reactor power, the coolant temperature, the pressure, and the actual rod position of the power control rod in the process.

[0094] Referring to Figure 3 , a motion logic diagram of a power control rod is shown. As Figure 3As shown, the control rod drive mechanism can mainly be composed of a secondary circuit power selection module, a power calculation module, a first function generator, a second function generator, a step counter and a drive device. During the curve calibration experiment, the control device can input a power control signal to the secondary circuit power selection module in the control rod drive mechanism, the power control module can determine the output electric power required by the secondary circuit component of the current nuclear power unit according to the received power control signal, and input the output electric power to the power calculation module. Then, the power calculation module can determine the power setting value according to the correction factor and the output electric power preset by the research and development personnel, and input the power setting value to the function generator module. The function generator module can determine the expected rod position corresponding to the current output electric power according to the power setting value, and input the expected rod position to the second function generator. Then, the second function generator can generate a drive signal according to the expected rod position and the actual rod position of the power control rod fed back by the step counter. The second function generator can transmit the drive signal to the drive device to adjust the power control rod through the drive device.

[0095] Figure 4 A specific implementation flowchart of the execution method S203 of the curve calibration experiment provided by the second embodiment of the present application is shown. Referring to Figure 4 , compared with Figure 2 the embodiment, the execution method of the curve calibration experiment provided by the embodiment comprises S2031-S2033, which are specifically described as follows:

[0096] S2031, input the correction factor into the preset temperature estimation function to determine the expected maximum temperature corresponding to the correction factor.

[0097] In this embodiment, after the electronic device determines the correction factor corresponding to the relationship curve, the correction factor can be input into the temperature estimation function preset by the research and development personnel, so as to determine the expected maximum temperature corresponding to the correction factor through the temperature estimation function.

[0098] In a possible implementation, the specific process in which the electronic device calculates the expected maximum temperature through the temperature estimation function can be as follows: the electronic device can determine a temperature change value corresponding to the correction factor according to the correction factor, the rated power of the nuclear power unit in which the power control rod is located, the actual power of the nuclear power unit, the power coefficient of the nuclear power unit, and the temperature coefficient. The temperature change value calculated by the electronic device can be the change in the reactor temperature between the reactor temperature before adjustment and the reactor temperature in the same environment after adjustment when the nuclear power unit performs the curve calibration experiment, which is caused by the adjustment of the control logic of the power control rod through the correction factor. After determining the temperature change value corresponding to the correction factor, the electronic device can determine an expected maximum temperature corresponding to the correction factor according to the temperature change value and the historical maximum temperature of the nuclear power unit. Specifically, the electronic device can determine the sum of the temperature change value and the historical maximum temperature as the expected maximum temperature. The historical maximum temperature can be the maximum value of the overheating temperature of the reactor in all historical data of the nuclear power unit performing the curve calibration experiment.

[0099] In a possible implementation, the temperature estimation function can be specifically as follows:

[0100]

[0101] Specifically, P can be the actual power of the nuclear power unit. P 额 may be the rated power of the nuclear power unit. ΔP can be the correction factor. may be the power coefficient of the nuclear power unit. may be the temperature coefficient of the nuclear power unit. T max may be the historical maximum temperature of the nuclear power unit. T est may be the expected maximum temperature corresponding to the correction factor. may be the temperature change value corresponding to the correction factor. The units of the actual power and the rated power can both be megawatts. The temperature coefficient can represent the rate at which the reactivity of the reactor changes with temperature, that is, the value of the reactivity change when the temperature of the reactor changes by 1 degree Celsius. The unit of the temperature coefficient can be per centimeter per degree Celsius (pcm / ℃).

[0102] S2032, if the expected maximum temperature is greater than the preset temperature threshold, inputting the correction factor into the preset power adjustment function to determine an initial power corresponding to the correction factor.

[0103] In this embodiment, after determining the expected maximum temperature corresponding to the correction factor, the electronic device can determine whether the correction factor satisfies the power adjustment condition by judging whether the expected maximum temperature is greater than a temperature threshold preset by the R&D personnel. The temperature threshold can be a limit value of the overheating temperature of the reactor when the nuclear power unit performs the curve calibration experiment. If the electronic device determines that the expected maximum temperature corresponding to the correction factor is greater than the temperature threshold, that is, the correction factor satisfies the power adjustment condition, the electronic device can input the correction factor into the power adjustment function preset by the R&D personnel to calculate the initial power corresponding to the correction factor through the power adjustment function.

[0104] In a possible implementation, the specific process in which the electronic device calculates the initial power through the power adjustment function can be as follows. The electronic device can determine the expected maximum temperature corresponding to the correction factor according to the temperature estimation function. For the specific method in which the electronic device calculates the expected maximum temperature, please refer to the content in the embodiment S2031, which will not be repeated here. After determining the expected maximum temperature corresponding to the correction factor, the electronic device can determine a temperature difference value according to the expected maximum temperature and a temperature threshold of the nuclear power unit. Specifically, the electronic device can take the difference between the expected maximum temperature and the temperature threshold as the temperature difference value. Then, the electronic device can determine the initial power corresponding to the correction factor according to the temperature difference value, a rated power generation of the nuclear power unit, and an actual power generation of the nuclear power unit.

[0105] In a possible implementation, the power adjustment function can be as follows:

[0106]

[0107] wherein, P 初始 may be the initial power corresponding to the correction factor. P can be the actual power generation of the nuclear power unit. P 额 may be the rated power generation of the nuclear power unit. T est may be the expected maximum temperature corresponding to the correction factor. T limit may be the temperature threshold of the nuclear power unit.

[0108] S2033, if the expected maximum temperature is less than or equal to the preset temperature threshold, the preset maximum power is taken as the initial power.

[0109] In this embodiment, if the electronic device determines that the expected maximum temperature corresponding to the correction factor is less than or equal to the temperature threshold, that is, the correction factor does not satisfy the power adjustment condition, the electronic device can take the preset maximum power as the initial power. For example, the electronic device can determine the full power value of the secondary circuit component in the nuclear power unit as the initial power of the secondary circuit component.

[0110] In the embodiment, the electronic device can calculate the expected maximum temperature of the nuclear power unit after the correction factor is introduced according to the correction factor, and determine whether the correction factor meets the power adjustment condition according to the expected maximum temperature. Further, since the main purpose of the electronic device adjusting the initial power is to reduce the probability of overheating of the nuclear power unit, the method provided in the embodiment can improve the accuracy of the electronic device in determining whether the initial power needs to be adjusted, thereby improving the accuracy of the initial power.

[0111] Referring to Figure 5 , a flowchart of an implementation process of a curve calibration experiment is shown. As Figure 5 indicated, in the case of any power control rod of the nuclear power unit having a step deviation event, the electronic device can calculate the reactivity difference caused by the step deviation event according to the maximum deviation step number of the power control rod. The electronic device can also input the maximum deviation step number of the power control rod into a safety analysis algorithm preset by the R&D personnel to generate an evaluation result through the safety analysis algorithm. The safety analysis algorithm can be used to evaluate the safety of the nuclear power unit when the power control rod has the maximum deviation step number. The safety analysis algorithm in the electronic device can be any safety analysis algorithm known to those skilled in the art, such as a deterministic safety analysis algorithm, a probabilistic safety analysis algorithm, an optimal estimation plus uncertainty analysis algorithm, etc. The present embodiment is not intended to limit the safety analysis algorithm. If the evaluation result generated by the safety analysis algorithm does not meet the preset safety condition, the electronic device can generate a second alarm information and display the second alarm information through the display device to inform the R&D personnel that the safety is low and the curve calibration experiment cannot be performed.

[0112] If the evaluation result generated by the safety analysis algorithm meets the preset safety condition, the electronic device can calculate the correction factor corresponding to the relationship curve according to the reactivity difference. The specific method of the electronic device calculating the correction factor according to the reactivity difference is described in the first embodiment of the present application, which is not repeated here. After determining the correction factor, the electronic device can determine whether the correction factor meets the power adjustment condition. If the correction factor does not meet the power adjustment condition, the electronic device can determine the full power value as the initial power. If the correction factor meets the power adjustment condition, the electronic device can calculate the initial power corresponding to the correction factor through the power adjustment function. After determining the initial power, the electronic device can adjust the power of the secondary circuit component of the nuclear power unit to the initial power, and perform the curve calibration experiment according to the correction factor and the relationship curve.

[0113] It should be noted that the size of the serial number of each step in the above embodiment does not mean the order of execution, the execution order of each process should be determined according to its function and inherent logic, and should not constitute any limitation on the implementation process of the embodiment of the application.

[0114] Referring to Figure 6 , a schematic diagram of an execution device of a curve calibration experiment provided by an embodiment of the application is shown, which can specifically include a step number determination module 601, a correction factor determination module 602, a power adjustment module 603, and an experiment execution module 604, wherein:

[0115] The step number determination module 601 is configured to determine the maximum deviation step number of the power control rod based on the deviation step number of the power control rod at at least one expected rod position if a step deviation event is identified at any moment of executing the curve calibration experiment; the curve calibration experiment is used to calibrate the relationship curve between the power control rod and the load.

[0116] The correction factor determination module 602 is configured to determine the correction factor corresponding to the relationship curve according to the maximum deviation step number.

[0117] The power adjustment module 603 is configured to input the correction factor into a preset power adjustment function to determine the initial power corresponding to the nuclear power unit where the power control rod is located if the correction factor meets the power adjustment condition.

[0118] The experiment execution module 604 is configured to execute the curve calibration experiment based on the initial power, the correction factor, and the relationship curve.

[0119] The power adjustment module can also be configured to input the correction factor into a preset temperature estimation function to determine the expected maximum temperature corresponding to the correction factor; if the expected maximum temperature corresponding to the correction factor is greater than a preset temperature threshold, the correction factor is input into a preset power adjustment function to determine the initial power corresponding to the correction factor.

[0120] The power adjustment module can also be configured to determine the temperature change value corresponding to the correction factor based on the correction factor, the rated power generation of the nuclear power unit, the actual power generation of the nuclear power unit, the power coefficient of the nuclear power unit, and the temperature coefficient of the nuclear power unit; and determine the expected maximum temperature corresponding to the correction factor based on the temperature change value corresponding to the correction factor and the historical maximum temperature of the nuclear power unit.

[0121] The temperature estimation function is specifically as follows:

[0122]

[0123] Wherein, P is the actual power generation of the nuclear power unit; P 额 is the rated power generation of the nuclear power unit; ΔP is the correction factor; a temperature coefficient of the nuclear power unit; a temperature coefficient of the nuclear power unit; max a historical maximum temperature of the nuclear power unit; est an expected maximum temperature corresponding to the correction factor; a temperature change value corresponding to the correction factor.

[0124] The power adjustment module can be further configured to determine a temperature difference value based on the expected maximum temperature corresponding to the correction factor and a temperature threshold of the nuclear power unit; determine an initial power corresponding to the correction factor based on the temperature difference value, a rated power generation of the nuclear power unit, and an actual power generation of the nuclear power unit.

[0125] The power adjustment function is specifically as follows:

[0126]

[0127] wherein, P 初始 is the initial power corresponding to the correction factor; P is the actual power generation of the nuclear power unit; P 额 is the rated power generation of the nuclear power unit; T est is the expected maximum temperature corresponding to the correction factor; T limit is the temperature threshold of the nuclear power unit; [T est -T limit ] is the temperature difference value.

[0128] The correction factor determination module can be further configured to input the expected rod position corresponding to the maximum deviation step number and the actual rod position corresponding to the maximum deviation step number into a preset reactivity algorithm to determine a reactivity difference value corresponding to the maximum deviation step number; and determine the correction factor corresponding to the relationship curve based on the reactivity difference value and the power coefficient of the nuclear power unit.

[0129] The correction factor determination module can be further configured to determine a maximum deviation rod position corresponding to each expected rod position of the power control rod based on the maximum deviation step number; determine, for any expected rod position of the power control rod, a power difference value between the any expected rod position and the maximum deviation rod position corresponding to the any expected rod position based on the relationship curve; and take a maximum value of all the power difference values as the correction factor.

[0130] The power adjustment module can be further configured to take a preset maximum power value as the initial power if the correction factor does not satisfy a power adjustment condition.

[0131] The power adjustment module can be further configured to perform a curve calibration experiment based on the initial power, the correction factor, and the relationship curve if the initial power is greater than or equal to a preset power threshold; and generate a first warning information if the initial power is less than the power threshold; the first warning information is used to prompt a user that the curve calibration experiment cannot be performed.

[0132] For the device embodiments, since they are basically similar to the method embodiments, they are described more simply, and the relevant parts refer to the description in the method embodiments.

[0133] Referring to Figure 7 , a schematic diagram of an electronic device is shown. As shown in Figure 7 , the electronic device 700 in the embodiment of the present application includes a processor 710, a memory 720, and a computer program 721 stored in the memory 720 and executable on the processor 710. The processor 710 implements the steps in each embodiment of the execution method of the curve calibration experiment when executing the computer program 721, such as steps S201 to S204 shown in Figure 2 . Alternatively, the processor 710 implements the functions of each module / unit in each of the above-described device embodiments when executing the computer program 721, such as the functions of the modules 601 to 604 shown in Figure 6 .

[0134] For example, the computer program 721 can be divided into one or more modules / units, which are stored in the memory 720 and executed by the processor 710 to complete the present application. The one or more modules / units can be a series of computer program instruction segments that can complete a specific function, which can be used to describe the execution process of the computer program 721 in the electronic device 700. For example, the computer program 721 can be divided into a step number determination module, a correction factor determination module, a power adjustment module, and an experiment execution module, and the specific functions of each module are as follows:

[0135] The step number determination module is configured to determine the maximum deviation step number of the power control rod based on the deviation step number of the power control rod at at least one desired rod position if a step deviation event is identified at any moment during the execution of the curve calibration experiment, and the curve calibration experiment is used to calibrate the relationship curve between the power control rod and the load.

[0136] The correction factor determination module is configured to determine the correction factor corresponding to the relationship curve based on the maximum deviation step number.

[0137] The power adjustment module is configured to input the correction factor into a preset power adjustment function to determine the initial power of the nuclear power generating unit corresponding to the power control rod if the correction factor satisfies the power adjustment condition.

[0138] The experiment execution module is configured to execute the curve calibration experiment based on the initial power, the correction factor, and the relationship curve.

[0139] The electronic device 700 can be a desktop computer, a cloud server, or the like computing device. The electronic device 700 can include, but is not limited to, a processor 710, a memory 720. Those skilled in the art can understand that Figure 7 The electronic device 700 is only an example and does not constitute a limitation on the electronic device 700, and can include more or fewer components than shown, or combine certain components, or different components, for example, the electronic device 700 can also include an input / output device, a network access device, a bus, and the like.

[0140] The processor 710 can be a central processing unit (CPU), and can also be other general-purpose processors, a digital signal processor (DSP), an application specific integrated circuit (ASIC), a field-programmable gate array (FPGA) or other programmable logic device, discrete gate or transistor logic, discrete hardware components, and the like. The general-purpose processor can be a microprocessor or the processor can also be any conventional processor.

[0141] The memory 720 can be an internal storage unit of the electronic device 700, such as a hard disk or a memory of the electronic device 700. The memory 720 can also be an external storage device of the electronic device 700, such as a plug-in hard disk, a smart media card (SMC), a secure digital (SD) card, a flash card, and the like provided on the electronic device 700. Further, the memory 720 can include both the internal storage unit and the external storage device of the electronic device 700. The memory 720 is used to store the computer program 721 and other programs and data required by the electronic device 700. The memory 720 can also be used to temporarily store data that has been output or will be output.

[0142] The embodiments of the present application also disclose an electronic device, including a memory, a processor, and a computer program stored in the memory and executable on the processor, and the processor executes the computer program to implement the execution method of the curve calibration experiment as described in the foregoing embodiments.

[0143] The embodiment of the present application further discloses a computer readable storage medium, which stores a computer program, and the computer program is executed by a processor to implement the execution method of the curve calibration experiment.

[0144] The embodiment of the present application further discloses a computer program product, which, when running on a computer, enables the computer to execute the execution method of the curve calibration experiment.

[0145] The above-mentioned embodiments are only used to illustrate the technical solutions of the present application, rather than limit them. Although the present application is described in detail with reference to the foregoing embodiments, those skilled in the art should understand that the technical solutions recorded in the foregoing embodiments can be modified, or some technical features can be replaced by equivalent ones, and these modifications or replacements do not make the essence of the corresponding technical solutions deviate from the spirit and scope of the technical solutions of the embodiments of the present application, and should be included in the protection scope of the present application.

Claims

1. A method of performing a curve calibration experiment, characterized by, The method comprises: If a deviation step event is identified at any time during the execution of the curve calibration experiment, determining a maximum deviation step number corresponding to the power control rod based on the deviation step number of the power control rod at at least one expected rod position; the curve calibration experiment is used to calibrate the relationship curve between the power control rod and the load; According to the maximum deviation step number, determine the correction factor corresponding to the relationship curve; If the correction factor meets the power adjustment condition, input the correction factor into the preset power adjustment function to determine the initial power corresponding to the nuclear power unit where the power control rod is located; Based on the initial power, the correction factor and the relationship curve, the curve calibration experiment is executed.

2. The method of claim 1, wherein, If the correction factor meets the power adjustment condition, input the correction factor into the preset power adjustment function to determine the initial power corresponding to the nuclear power unit where the power control rod is located, comprising: Input the correction factor into the preset temperature estimation function to determine the expected maximum temperature corresponding to the correction factor; If the expected maximum temperature corresponding to the correction factor is greater than the preset temperature threshold, input the correction factor into the preset power adjustment function to determine the initial power corresponding to the correction factor.

3. The method of claim 2, wherein, The method comprises: Based on the correction factor, the rated power generation of the nuclear power unit, the actual power generation of the nuclear power unit, the power coefficient of the nuclear power unit and the temperature coefficient of the nuclear power unit, determine the temperature change value corresponding to the correction factor; Based on the temperature change value corresponding to the correction factor and the historical maximum temperature of the nuclear power unit, determine the expected maximum temperature corresponding to the correction factor; The temperature estimation function is specifically as follows: Wherein, the is the actual power generation of the nuclear power unit; the is the rated power generation of the nuclear power unit; the is the correction factor; the is the power coefficient of the nuclear power unit; the is the temperature coefficient of the nuclear power unit; the is the historical maximum temperature of the nuclear power unit; the is the expected maximum temperature corresponding to the correction factor; the is the temperature change value corresponding to the correction factor.

4. The method of claim 1, wherein, The method comprises: Based on the expected maximum temperature corresponding to the correction factor and the temperature threshold of the nuclear power unit, determine the temperature difference value; Based on the temperature difference value, the rated power generation of the nuclear power unit and the actual power generation of the nuclear power unit, determine the initial power corresponding to the correction factor; The power adjustment function is specifically as follows: Among them, the The initial power corresponding to the correction factor; The actual power generation capacity of the nuclear power unit; The rated power output of the nuclear power unit; The expected maximum temperature corresponding to the correction factor; The temperature threshold of the nuclear power unit; The temperature difference value is mentioned.

5. The method of claim 1, wherein, The method comprises: Input the expected rod position corresponding to the maximum deviation step number and the actual rod position corresponding to the maximum deviation step number into the preset reactivity algorithm to determine the reactivity difference value corresponding to the maximum deviation step number; Based on the reactivity difference value and the power coefficient of the nuclear power unit, determine the correction factor corresponding to the relationship curve.

6. The method of claim 1, wherein, The method comprises: Based on the maximum deviation step number, determine the maximum deviation rod position corresponding to each expected rod position of the power control rod; For any expected rod position of the power control rod, determine the power difference value between the any expected rod position and the maximum deviation rod position corresponding to the any expected rod position based on the relationship curve; Taking a maximum value of all the power difference values as the correction factor.

7. The method according to any one of claims 1 to 6, characterized in that, After inputting the maximum deviation step number into a preset correction algorithm to generate a correction factor corresponding to a relationship curve, the method further includes: If the correction factor does not satisfy a power adjustment condition, taking a preset maximum power value as the initial power.

8. The method according to any one of claims 1 to 6, characterized in that, After inputting the correction factor into a preset power adjustment function to determine an initial power corresponding to the correction factor, the method further includes: If the initial power is greater than or equal to a preset power threshold value, performing the curve calibration experiment based on the initial power, the correction factor and the relationship curve; If the initial power is less than the power threshold value, generating a first warning information; the first warning information is used to prompt a user that the curve calibration experiment cannot be performed.

9. An electronic device, comprising: An electronic device includes a processor, a memory, and a computer program stored in the memory and executable on the processor, and when the processor executes the computer program, the electronic device implements the execution method of the curve calibration experiment according to any one of claims 1-8.

10. A computer program product, characterised in that, A computer program is executed to cause the execution method of the curve calibration experiment according to any one of claims 1-8 to be executed.

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