Daily periodic power range coefficient calibration method, storage medium and electronic equipment

Abstract

The invention relates to a daily periodic power range coefficient calibration method, a storage medium and electronic equipment. The method comprises the following steps: S1, acquiring operation data of a nuclear power unit; s2, determining whether the nuclear power unit is in a stable working condition or not according to the operation data; s3, when the nuclear power unit is in a stable working condition, obtaining the current reactor core power of the nuclear power unit, the current alpha coefficient of the range measurement channel and the response current of an upper detector and the response current of a lower detector of the range measurement channel; s4, calculating an axial power deviation according to the response current of the upper detector and the response current of the lower detector; and S5, calculating KU and KL of the range measurement channel according to the current reactor core power, the axial power deviation, the current alpha coefficient and a set formula. Under the condition that xenon oscillation is not caused, calibration of the power range coefficient can be achieved, and great economic and safety benefits are generated for a nuclear power plant.

Description

Technical Field

[0001] The invention relates to the technical field of nuclear power instrument measurement, and in particular to a daily periodic power range coefficient calibration method, a storage medium and an electronic device. Background Art

[0002] In nuclear power plants, a power range coefficient calibration test of the nuclear instrument system (RPN system) is usually performed every 90 equivalent full power days (EFPD) to ensure the accuracy of the RPN system in measuring core power (or nuclear power) and axial power deviation.

[0003] In the related art, the xenon oscillation test method is usually used to realize the calibration of the power range coefficient, and the xenon oscillation test method has the following defects: 1. It is necessary to actively introduce power disturbance into the core, resulting in high risk; 2. It is necessary to collect a large amount of core power and axial power deviation data, and usually 6 to 8 groups of core power and axial power deviation data under different power distribution states need to be collected to realize calibration, which has the defects of long calibration period and low efficiency; 3. Long-term disturbance of the core will lead to a large amount of radioactive waste liquid discharge, which is very environmentally unfriendly. Summary of the invention

[0004] The technical problem to be solved by the present invention is to provide a daily periodic power range coefficient calibration method, storage medium and electronic equipment.

[0005] The technical solution adopted by the present invention to solve the technical problem is: construct a daily periodic power range coefficient calibration method for calibrating the power range coefficient of the range measurement channel in the RPN system, wherein the power range coefficient includes α, K U and K L , the daily periodic power range coefficient calibration method includes:

[0006] S1. Obtaining the operating data of the nuclear power unit;

[0007] S2. determining whether the nuclear power unit is in a stable operating condition according to the operating data;

[0008] S3, when the nuclear power unit is in a stable operating condition, obtaining the current core power of the nuclear power unit, the current α coefficient of the range measurement channel, and the upper detector response current and the lower detector response current of the range measurement channel;

[0009] S4, calculating the axial power deviation according to the upper detector response current and the lower detector response current;

[0010] S5. Calculate the K of the range measurement channel according to the current core power, the axial power deviation, the current α coefficient and the set formula. U and KL ;

[0011] Wherein, the setting formula is expressed as:

[0012] ΔI represents the axial power deviation, α(k) represents the current α coefficient, W represents the current core power, I U represents the upper detector response current, I L represents the lower detector response current.

[0013] Preferably, the operation data includes unit power variation data, turbine operation mode, power control rod group position data and set stability condition data;

[0014] The S2 includes:

[0015] S21, judging whether the duration of the nuclear power unit remaining within the allowable power range corresponding to the current set power is greater than a first set time according to the unit power change data, and if so, executing S22;

[0016] S22, determining whether the steam turbine is in automatic control mode according to the steam turbine operating mode, and if so, executing S23;

[0017] S23, determining whether the positions of all power control rods in the power control rod group are at the maximum step limit value according to the power control rod group position data, and if so, executing S24;

[0018] S24. Determine whether the nuclear power unit meets the set stability condition within the second set time according to the set stability condition data. If so, it is determined that the nuclear power unit is in a stable operating condition.

[0019] Preferably, the set stability condition data includes at least one of the temperature control rod group position data, primary circuit pressure change data, coolant temperature change data, boron dilution history data and axial power deviation change data;

[0020] In S24, determining whether the nuclear power unit meets the stability condition within the second set time according to the set stability condition data includes:

[0021] Perform at least one of the following judgments:

[0022] Determine whether the position change of the temperature control rod group complies with the set change law within the latest second set time according to the temperature control rod group position data, determine whether the pressure of the first circuit is kept within the set pressure range within the latest second set time according to the first circuit pressure change data, determine whether the error value of the coolant average temperature is kept within the set temperature range within the latest second set time according to the coolant temperature change data, determine whether the nuclear power unit has active boron dilution work within the latest second set time according to the boron dilution history data, and determine whether the axial power deviation change rate is less than the set change rate within the latest second set time according to the axial power deviation change data;

[0023] When the results of all the judgments performed are yes, it is determined that the nuclear power unit meets the stability condition within the second set time.

[0024] Preferably, the temperature control rod group position data includes historical position change data of the adjustment belt and the temperature control rod group;

[0025] The step of determining whether the position change of the temperature control rod group conforms to the set change rule within the latest second set time according to the position data of the temperature control rod group comprises:

[0026] determining an allowable adjustment range of the control rod based on the adjustment band;

[0027] determining, based on the temperature control rod group position data, whether the position of the temperature control rod group remains within the allowable adjustment range of the control rods within a recent second set time;

[0028] When the position of the temperature control rod group remains within the allowable adjustment range of the control rods within the latest second set time, it is determined that the position change of the temperature control rod group complies with the set change law within the latest second set time.

[0029] Preferably, the step of determining whether the position change of the temperature control rod group conforms to a set change rule within the latest second set time according to the position data of the temperature control rod group further includes:

[0030] further determining, based on the temperature control rod group position data, whether the number of steps of continuous change in one direction of the position of the temperature control rod group is not greater than a set number of steps within a recent second set time;

[0031] When the position of the temperature control rod group remains within the allowable adjustment range of the control rod within the most recent second set time and the number of continuous changes in the position of the temperature control rod group in one direction is not greater than the set number of steps within the most recent second set time, it is determined that the position change of the temperature control rod group complies with the set change law within the most recent second set time.

[0032] Preferably, the set pressure range is 153 bar.g to 155 bar.g, the set temperature range is 0°C to 0.5°C, the set change rate range is 0% FP / hour to 0.3% FP / hour, the set number of steps is 2 steps, and the control rod allows an adjustment range of mid-6 steps to mid+6 steps, where mid represents the middle rod position of the adjustment band.

[0033] Preferably, the first set time is not less than 48 hours, and the second set time is not less than 6 hours.

[0034] Preferably, the lower limit value of the allowable power range is 0.985 times the current set power, and the upper limit value of the allowable power range is 1.015 times the current set power.

[0035] The present invention also constructs a computer storage medium storing a computer program, which implements the steps of the daily periodic power range coefficient calibration method described above when the computer program is executed.

[0036] The present invention also constructs an electronic device, including a memory, a processor, and a computer program stored in the memory and executable on the processor. When the processor executes the computer program, the steps of the daily periodic power range coefficient calibration method described above are implemented.

[0037] The technical solution of the present invention can realize the calibration of the power range coefficient without causing xenon oscillation and without collecting 6 to 8 groups of core power and axial power deviation data under different power distribution states, which significantly improves the safety of nuclear power plants, shortens the calibration time, reduces the discharge of radioactive waste liquid, and produces greater economic and safety benefits for nuclear power plants. BRIEF DESCRIPTION OF THE DRAWINGS

[0038] The present invention will be further described below with reference to the accompanying drawings and embodiments, in which:

[0039] Figure 1 is a flowchart of a method for calibrating a daily periodic power range coefficient in some embodiments of the present invention;

[0040] Figure 2 is a flowchart of step S2 in some embodiments of the present invention;

[0041] Figure 3 is a circuit structure block diagram of an electronic device in some embodiments of the present invention. DETAILED DESCRIPTION

[0042] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, specific embodiments of the present invention are now described in detail with reference to the accompanying drawings.

[0043] It should be noted that the flowcharts shown in the accompanying drawings are only exemplary and do not necessarily include all the contents and operations / steps, nor do they have to be executed in the order described. For example, some operations / steps can be decomposed, while some operations / steps can be combined or partially combined, so the actual execution order may change according to actual conditions.

[0044] The block diagrams shown in the accompanying drawings are merely functional entities and do not necessarily correspond to physically independent entities. That is, these functional entities may be implemented in software form, or in one or more hardware modules or integrated circuits, or in different networks and / or processor devices and / or microcontroller devices.

[0045] Figure 1 The flowchart of the method for calibrating the daily periodic power range coefficient in some embodiments of the present invention is applicable to the Hualong One nuclear power unit, and can calibrate the power range coefficient of the range measurement channel in the RPN system, wherein the power range coefficient includes α, K U and K L .like Figure 1 As shown, the daily periodic power range coefficient calibration method may include step S1, step S2, step S3, step S4 and step S5.

[0046] Step S1, obtaining the operation data of the nuclear power unit. The operation data of the nuclear power unit may include the unit power change data, the turbine operating mode, the power control rod group position data and the set stability condition data. The set stability condition data refers to the relevant data that can indicate whether the nuclear power unit operating condition is stable, such as the primary circuit pressure, the coolant temperature, etc. Therefore, the set stability condition data may specifically include at least one of the temperature control rod group position data, the primary circuit pressure change data, the coolant temperature change data, the boron dilution history data and the axial power deviation change data.

[0047] It should be noted that the operating data are all information that needs to be monitored for daily operation of the nuclear power plant. Therefore, this step can obtain the operating data by communicating with relevant systems of the nuclear power plant (including digital instrumentation and control systems, rod control systems, etc.).

[0048] Step S2: determine whether the nuclear power unit is in a stable operating condition based on the operating data.

[0049] It should be noted that when the nuclear power unit is in a power disturbance condition, it will affect the measurement of the range measurement channel, resulting in a decrease in the coefficient calibration accuracy. Therefore, it is necessary to perform subsequent coefficient calibration steps after the nuclear power unit is in a stable condition.

[0050] In some embodiments, by executing Figure 2 Steps S21 to S24 shown implement step S2.

[0051] Step S21, judging whether the duration of the nuclear power unit remaining within the allowable power range corresponding to the current set power is greater than a first set time according to the unit power change data, if so, executing S22. The first set time is not less than 48 hours.

[0052] In one embodiment, the allowable power range can be determined according to the current target power, specifically including: determining the product of the current target power and the set lower limit coefficient as the lower limit value of the allowable power range, and determining the product of the target power and the set upper limit coefficient as the upper limit value of the allowable power range. Among them, the current target power can be obtained from the digital instrumentation and control system, the set lower limit coefficient can be equal to 0.985, and the set upper limit coefficient can be equal to 1.015. That is, the lower limit value of the allowable power range is 0.985 times the current set power, and the upper limit value of the allowable power range is 1.015 times the current set power.

[0053] It can be understood that the judgment criteria of this step are prerequisites for determining whether the nuclear power unit is in a stable operating condition. If the judgment result of step S21 is no, there is no need to continue to perform the subsequent steps, and it is necessary to wait for the nuclear power unit operating condition to meet the requirements of step S21 (that is, the judgment result of step S21 is yes) before continuing to perform the subsequent steps. In addition, the specific operations for making the nuclear power unit meet the requirements of step S21 include but are not limited to: waiting for the nuclear power unit to gradually stabilize in the automatic control mode, and manually operating the relevant equipment of the nuclear power unit to stabilize the nuclear power unit operating condition.

[0054] Step S22, determine whether the steam turbine is in automatic control mode according to the steam turbine working mode, if so, execute S23. The steam turbine working mode can include automatic control mode and manual control mode. In the automatic control mode, the system will operate the steam turbine according to the preset power, which has the advantage of high stability and is one of the basic conditions for the nuclear power unit to enter a stable operating condition.

[0055] Step S23: Determine whether all power control rod positions in the power control rod group are at the maximum step limit value according to the power control rod group position data, and if so, execute S24. Taking the Hualong One nuclear power unit as an example, the maximum step limit value is 225 steps, so that all power control rod positions in the power control rod group are at 225 steps, which can prevent the power control rod group from participating in the core power control, thereby ensuring the stable operating condition of the nuclear power unit.

[0056] Step S24: determine whether the nuclear power unit meets the set stability condition within the second set time according to the set stability condition data, and if so, determine that the nuclear power unit is in a stable operating condition. The second set time is not less than 6 hours.

[0057] Further, in some embodiments, in S24, determining whether the nuclear power unit meets the stability condition within the second set time according to the set stability condition data includes:

[0058] Perform at least one of the following judgments:

[0059] Judgment A: determining whether the position change of the temperature control rod group conforms to the set change rule within the latest second set time according to the position data of the temperature control rod group;

[0060] Judgment B: Determine whether the pressure of the first circuit is kept within the set pressure range within the second set time according to the pressure change data of the first circuit;

[0061] Decision C: determining whether the error value of the coolant average temperature is within the set temperature range within the latest second set time according to the coolant temperature change data;

[0062] Decision D: Determine whether the nuclear power unit has undergone active boron dilution work within the most recent second set time based on the boron dilution history data;

[0063] Decision E: determining whether the axial power deviation change rate is less than the set change rate within the most recent second set time according to the axial power deviation change data;

[0064] When the results of all the judgments performed are yes, it is determined that the nuclear power unit meets the stability condition within the second set time.

[0065] In some embodiments, the temperature control rod group position data in judgment A may include the adjustment band and the historical position change data of the temperature control rod group. Accordingly, the specific steps of implementing judgment A may include: determining the control rod allowable adjustment range based on the adjustment band; determining whether the position of the temperature control rod group remains within the control rod allowable adjustment range within the latest second set time according to the temperature control rod group position data; when the position of the temperature control rod group remains within the control rod allowable adjustment range within the latest second set time, determining that the position change of the temperature control rod group complies with the set change law within the latest second set time.

[0066] In this embodiment, the adjustment band refers to the operable range of the temperature control rod, and the span range is 24 steps. The adjustment band will automatically follow the temperature change of the primary circuit, which can be obtained from the rod control system, and is mid-6 steps to mid+6 steps, and mid represents the middle rod position of the adjustment band. It can be understood that since the temperature control rod will affect the primary circuit coolant temperature, the heat exchange efficiency, and then the power in the reactor, when the position control of the temperature control rod exceeds the allowable adjustment range of the control rod, it will be considered that the temperature control rod has a large span, and the nuclear power unit operating condition is at risk of instability.

[0067] Furthermore, in one embodiment, the specific steps for implementing judgment A may also include: determining whether the number of continuous changes in the position of the temperature control rod group in one direction is not greater than the set number of steps within the most recent second set time based on the position data of the temperature control rod group; when the position of the temperature control rod group remains within the allowable adjustment range of the control rod within the most recent second set time and the number of continuous changes in the position of the temperature control rod group in one direction is not greater than the set number of steps within the most recent second set time, it is determined that the position change of the temperature control rod group complies with the set change law within the most recent second set time.

[0068] In this embodiment, the set number of steps can be 2 steps. The continuous change in the number of steps in one direction refers to the situation where the temperature control rod is continuously lifted for 2 steps or more or continuously inserted for 2 steps or more. Since the continuous lifting and insertion of the temperature control rod for more than 2 steps will cause a significant change in the temperature of the coolant in a single circuit, it will also cause the risk of unstable operating conditions in the nuclear power unit.

[0069] In judgment B, the set pressure range can be 153 bar.g to 155 bar.g. It is easy to understand that the primary circuit pressure is closely related to the core power. When the primary circuit pressure fluctuates greatly, it means that the core power is disturbed, that is, the nuclear power unit is in an unstable operating condition.

[0070] In judgment C, the set temperature range can be 0°C to 0.5°C. In addition, the coolant temperature change data includes the coolant real-time temperature and the coolant target temperature, and the error value of the coolant average temperature is equal to the absolute value of the difference between the coolant real-time temperature and the coolant target temperature. When the coolant average temperature exceeds the set temperature range, it means that the core power or the secondary circuit load has changed, that is, the nuclear power unit is in an unstable condition.

[0071] In judgment D, the automatic boron dilution operation (i.e., boration or dilution operation) can stabilize the core power and help stabilize the operating conditions of the nuclear power unit. Usually, the boron dilution operation will be performed manually only when the core or the unit urgently needs cooling and an abnormal situation occurs. However, no matter what kind of abnormality it is, it means that the nuclear power unit has an unstable operating condition within a short period of time (the second set time), and it is not suitable to perform coefficient calibration.

[0072] In judgment E, the set change rate can range from 0% FP / hour to 0.3% FP / hour. It can be understood that the axial power deviation can reflect the uniformity of the axial power distribution in the core, and is one of the important indicators of whether the operating condition of the nuclear power unit is stable. Therefore, when the hourly change rate of the axial power deviation exceeds the set change rate, it will be judged that the nuclear power unit is in an unstable condition.

[0073] Step S3, when the nuclear power unit is in a stable operating condition, obtain the current core power of the nuclear power unit, the current α coefficient of the range measurement channel, and the upper detector response current and the lower detector response current of the range measurement channel.

[0074] In this step, the upper detector response current and the lower detector response current correspond to the current signals output by the range measurement channel when monitoring the core power, wherein the upper detector response current is used to characterize the power of the upper part of the core, and the lower detector response current is used to characterize the power of the lower part of the core. The current α coefficient refers to the α coefficient currently normally applied by the range measurement channel. It can be understood that the present invention is equivalent to setting α to be fixed, so as to adjust K on this basis. U and K L In addition, the upper detector response current, the lower detector response current and the current core power can be obtained from the core measurement system.

[0075] It should be noted that in the past, the power range coefficient was calibrated by the xenon oscillation test method. It was found that the α in the power range coefficient usually does not change much within a cycle. Therefore, α can be fixed to a known value. Even so, it will not lead to obvious deviation in the calibration effect. Therefore, the other two coefficients K are obtained. U and K L The coefficient calibration is now complete.

[0076] Step S4, calculating the axial power deviation according to the upper detector response current and the lower detector response current. In this step, the magnitude of the axial power deviation can be characterized by the difference between the upper detector response current and the lower detector response current. After the difference between the upper detector response current and the lower detector response current is processed by the core monitoring cabinet in the core measurement system, the axial power deviation can be obtained.

[0077] Step S5: Calculate the K of the range measurement channel according to the current core power, axial power deviation, current α coefficient and the set formula. U and K L .

[0078] Among them, the setting formula can be expressed as:

[0079] ΔI represents the axial power deviation, α(k) represents the current α coefficient, W represents the current core power, I U represents the upper detector response current, I L Indicates the lower detector response current.

[0080] In the example of using the present invention to realize power range coefficient calibration on the Hualong One nuclear power unit, it was found that the test period was shortened from 6-9 hours to less than 1 hour, and there was no need to actively cause core disturbance, which is of great significance to improving core safety.

[0081] It should be noted that in a nuclear power plant, there are mainly three types of range measurement channels, namely source range measurement channel (set number is 3), intermediate range measurement channel (set number is 3) and power range measurement channel (set number is 4). Although the power range coefficients corresponding to each range measurement channel may be different, the working principles of each range measurement channel are similar. Therefore, the calibration method provided by the present invention is applicable to all types of range measurement channels, and each range measurement channel can be executed synchronously, which helps to improve the calibration efficiency.

[0082] It can be understood that the technical solution of the present invention defines α as a fixed value. When the nuclear power unit is in a stable operating condition, the current core power of the nuclear power unit, the current α coefficient of the range measurement channel, and the upper detector response current and the lower detector response current of the range measurement channel are obtained. Then, in combination with the set formula, the other two power range coefficients K can be calculated. U and K L The size of the reactor can be reduced without causing xenon oscillations or collecting 6 to 8 sets of core power and axial power deviation data under different power distribution states, which significantly improves the safety of nuclear power plants, shortens the calibration time, and reduces the discharge of radioactive waste liquid, generating greater economic and safety benefits for nuclear power plants.

[0083] In addition, the present invention also provides a computer storage medium storing a computer program, which implements the steps of the daily periodic power range coefficient calibration method provided in an embodiment of the present invention when the computer program is running.

[0084] In addition, if Figure 3 As shown, the present invention also provides an electronic device, including a memory, a processor, and a computer program stored in the memory and executable on the processor. When the processor executes the computer program, the steps of the daily periodic power range coefficient calibration method provided in an embodiment of the present invention are implemented.

[0085] In this specification, each embodiment is described in a progressive manner, and each embodiment focuses on the differences from other embodiments. The same or similar parts between the embodiments can be referred to each other. For the device disclosed in the embodiment, since it corresponds to the method disclosed in the embodiment, the description is relatively simple, and the relevant parts can be referred to the method part.

[0086] Professionals may further appreciate that the units and algorithm steps of each example described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, computer software, or a combination of the two. In order to clearly illustrate the interchangeability of hardware and software, the composition and steps of each example have been generally described in the above description according to function. Whether these functions are performed in hardware or software depends on the specific application and design constraints of the technical solution. Professionals and technicians may use different methods to implement the described functions for each specific application, but such implementation should not be considered to be beyond the scope of the present invention.

[0087] The steps of the method or algorithm described in conjunction with the embodiments disclosed herein may be implemented directly using hardware, a software module executed by a processor, or a combination of the two. The software module may be placed in a random access memory (RAM), a memory, a read-only memory (ROM), an electrically programmable ROM, an electrically erasable programmable ROM, a register, a hard disk, a removable disk, a CD-ROM, or any other form of storage medium known in the art.

[0088] It can be understood that the above embodiments only express the preferred implementation modes of the present invention, and the descriptions thereof are relatively specific and detailed, but they cannot be understood as limiting the patent scope of the present invention. It should be pointed out that, for ordinary technicians in this field, the above technical features can be freely combined without departing from the concept of the present invention, and several deformations and improvements can be made, which all belong to the protection scope of the present invention. Therefore, all equivalent changes and modifications made to the scope of the claims of the present invention should belong to the coverage of the claims of the present invention.

Claims

1. A daily periodic power range coefficient calibration method, used to calibrate the power range coefficient of the range measurement channel in the RPN system, the power range coefficient includes α, K U and K L , characterized in that, The daily periodic power range coefficient calibration method comprises: S1. Obtaining the operating data of the nuclear power unit; S2. determining whether the nuclear power unit is in a stable operating condition according to the operating data; S3, when the nuclear power unit is in a stable operating condition, obtaining the current core power of the nuclear power unit, the current α coefficient of the range measurement channel, and the upper detector response current and the lower detector response current of the range measurement channel; S4, calculating the axial power deviation according to the upper detector response current and the lower detector response current; S5. Calculate the K of the range measurement channel according to the current core power, the axial power deviation, the current α coefficient and the set formula. U and K L ; Wherein, the setting formula is expressed as: ΔI represents the axial power deviation, α(k) represents the current α coefficient, W represents the current core power, I U represents the upper detector response current, I L represents the lower detector response current.

2. The daily periodic power range coefficient calibration method according to claim 1 is characterized in that: The operation data includes unit power change data, turbine operation mode, power control rod group position data and set stability condition data; The S2 includes: S21, judging whether the duration of the nuclear power unit remaining within the allowable power range corresponding to the current set power is greater than a first set time according to the unit power change data, and if so, executing S22; S22, determining whether the steam turbine is in automatic control mode according to the steam turbine operating mode, and if so, executing S23; S23, determining whether the positions of all power control rods in the power control rod group are at the maximum step limit value according to the power control rod group position data, and if so, executing S24; S24. Determine whether the nuclear power unit meets the set stability condition within the second set time according to the set stability condition data. If so, it is determined that the nuclear power unit is in a stable operating condition.

3. The daily periodic power range coefficient calibration method according to claim 2 is characterized in that: The set stability condition data includes at least one of the temperature control rod group position data, primary circuit pressure change data, coolant temperature change data, boron dilution history data and axial power deviation change data; In S24, determining whether the nuclear power unit meets the stability condition within the second set time according to the set stability condition data includes: Perform at least one of the following judgments: Determine whether the position change of the temperature control rod group complies with the set change law within the latest second set time according to the temperature control rod group position data, determine whether the pressure of the first circuit is kept within the set pressure range within the latest second set time according to the first circuit pressure change data, determine whether the error value of the coolant average temperature is kept within the set temperature range within the latest second set time according to the coolant temperature change data, determine whether the nuclear power unit has active boron dilution work within the latest second set time according to the boron dilution history data, and determine whether the axial power deviation change rate is less than the set change rate within the latest second set time according to the axial power deviation change data; When the results of all the judgments performed are yes, it is determined that the nuclear power unit meets the stability condition within the second set time.

4. The daily periodic power range coefficient calibration method according to claim 3 is characterized in that: The temperature control rod group position data includes historical position change data of the adjustment belt and the temperature control rod group; The step of determining whether the position change of the temperature control rod group conforms to the set change rule within the latest second set time according to the position data of the temperature control rod group comprises: determining an allowable adjustment range of the control rod based on the adjustment band; determining, based on the temperature control rod group position data, whether the position of the temperature control rod group remains within the allowable adjustment range of the control rods within a recent second set time; When the position of the temperature control rod group remains within the allowable adjustment range of the control rods within the latest second set time, it is determined that the position change of the temperature control rod group complies with the set change law within the latest second set time.

5. The daily periodic power range coefficient calibration method according to claim 4 is characterized in that: In the step of determining whether the position change of the temperature control rod group conforms to the set change rule within the latest second set time according to the temperature control rod group position data, it also includes: further determining, based on the temperature control rod group position data, whether the number of steps of continuous change in one direction of the position of the temperature control rod group is not greater than a set number of steps within a recent second set time; When the position of the temperature control rod group remains within the allowable adjustment range of the control rod within the most recent second set time and the number of continuous changes in the position of the temperature control rod group in one direction is not greater than the set number of steps within the most recent second set time, it is determined that the position change of the temperature control rod group complies with the set change law within the most recent second set time.

6. The daily periodic power range coefficient calibration method according to claim 5 is characterized in that: The set pressure range is 153 bar.g to 155 bar.g, the set temperature range is 0°C to 0.5°C, the set change rate range is 0% FP / hour to 0.3% FP / hour, the set number of steps is 2 steps, and the control rod allows an adjustment range of mid-6 steps to mid+6 steps, where mid represents the middle rod position of the adjustment band.

7. The daily periodic power range coefficient calibration method according to any one of claims 2 to 6, characterized in that: The first set time is not less than 48 hours, and the second set time is not less than 6 hours.

8. The daily periodic power range coefficient calibration method according to any one of claims 2 to 6, characterized in that: The lower limit of the allowable power range is 0.985 times the current set power, and the upper limit of the allowable power range is 1.015 times the current set power.

9. A computer storage medium, characterized in that A computer program is stored, and when the computer program is run, the steps of the daily periodic power range coefficient calibration method described in any one of claims 1 to 8 are implemented.

10. An electronic device comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, characterized in that: When the processor executes the computer program, the steps of the daily periodic power range coefficient calibration method described in any one of claims 1 to 8 are implemented.

Images