Reactor core reactivity control method, computer storage medium, control equipment and nuclear power plant rod control and rod position system

Abstract

The invention relates to a reactor core reactivity control method, a computer storage medium, control equipment and a nuclear power plant rod control and rod position system. The method comprises the following steps: S1, acquiring a current coolant comprehensive temperature deviation and an R rod control dead zone; s2, judging whether the coolant comprehensive temperature deviation is in an R rod control dead zone or not, if yes, executing S3, and if not, executing S4; s3, boron adjustment is carried out according to the obtained boron adjustment operation signal, and the step S1 is carried out until the G rod position correction value returns to zero; and S4, acquiring a set operation signal, determining a G rod position correction value according to the set operation signal, adjusting the rod position of the G rod group according to the G rod position correction value, and returning to S1 after adjustment. According to the technical scheme, the technical effect of automatically compensating the rod position of the G rod group without manual intervention of a worker is achieved, the misoperation risk of manually adjusting the rod position of the G rod by the worker is reduced, and the flexibility of the reactivity control capability is further improved.

Description

Technical Field

[0001] The present invention relates to the technical field of rod control and rod position systems in nuclear power plants, and particularly to a core reactivity control method, a computer storage medium, a control device, and a rod control and rod position system for a nuclear power plant. Background Art

[0002] In the prior art, when facing the transient of large-scale load increase or decrease of the unit, since the power control rod (abbreviation: G rod) belongs to open-loop control, it brings inaccuracy to the core reactivity, and the change of core power will cause the accumulation of xenon poison, thus resulting in a large reactivity deviation. Also, because the adjustment ability of the temperature control rod (abbreviation: R rod) is limited, and the timeliness of boron adjustment is poor, during the actual operation of the unit, the operator can only manually adjust the power correction factor to correct the position of the G rod, so as to quickly compensate for the reactivity. However, the actual effect of manual adjustment extremely depends on the operator's practical experience and real-time judgment and response ability. If the operation is improper, it may cause the deterioration of the unit state and bring adverse effects to the unit. Summary of the Invention

[0003] The technical problem to be solved by the present invention is to provide a core reactivity control method, a computer storage medium, a control device, and a rod control and rod position system for a nuclear power plant.

[0004] The technical solution adopted by the present invention to solve its technical problem is: to construct a core reactivity control method, including the following steps:

[0005] S1. Obtain the current comprehensive coolant temperature deviation and the R rod control dead zone;

[0006] S2. Judge whether the comprehensive coolant temperature deviation is within the R rod control dead zone. If so, execute S3; otherwise, execute S4;

[0007] S3. Reset the G rod position correction value, and perform boron adjustment according to the obtained boron adjustment operation signal during the reset process until the G rod position correction value returns to zero, and then return to S1; wherein, the boron adjustment operation signal is a boron adjustment operation signal adaptively input by the staff based on the real-time state of the control rod group during the reset process of the core;

[0008] S4. Obtain the set operation signal, determine the G rod position correction value according to the set operation signal, and also adjust the rod position of the G rod group according to the G rod position correction value, and then return to S1 after the adjustment.

[0009] Preferably, the set operation signal includes an axial power deviation signal, an operation limit range, a coolant average temperature signal, and an R rod position signal;

[0010] In S4, the step of determining the G rod position correction value according to the set operation signal includes:

[0011] Determine whether the axial power deviation signal exceeds the operating limit range. If so, keep the G-rod position correction value unchanged; otherwise, adjust the G-rod position correction value according to the average coolant temperature signal and the R-rod position signal.

[0012] Preferably, the step of determining whether the axial power deviation signal exceeds the operating limit range includes:

[0013] Determine whether a C21 pre-alarm signal output by the rod control and position system is obtained;

[0014] When the C21 pre-alarm signal is obtained, determine that the axial power deviation signal exceeds the operating limit range.

[0015] Preferably, the step of adjusting the G-rod position correction value according to the average coolant temperature signal and the R-rod position signal includes:

[0016] Determine whether the average coolant temperature signal is less than a set temperature threshold. If so, gradually increase the G-rod position correction value.

[0017] Preferably, the step of determining whether the average coolant temperature signal is less than the set temperature threshold includes:

[0018] Determine whether a C22 pre-alarm signal output by the rod control and position system is obtained;

[0019] When the C22 pre-alarm signal is obtained, determine that the average coolant temperature signal is less than the set temperature threshold.

[0020] Preferably, the step of adjusting the G-rod position correction value according to the average coolant temperature signal and the R-rod position signal further includes:

[0021] Determine whether the R-rod position signal is less than a set rod position threshold. If so, gradually decrease the G-rod position correction value.

[0022] Preferably, in the step of adjusting the G-rod position correction value according to the average coolant temperature signal and the R-rod position signal, the G-rod position correction value is gradually increased or gradually decreased at a set rate.

[0023] Preferably, in S4, the step of adjusting the rod position of the G-rod group according to the G-rod position correction value includes:

[0024] Obtain the target rod position and the actual rod position of the G-rod group;

[0025] Subtract the actual rod position from the target rod position to obtain a rod position deviation;

[0026] Compensate the rod position deviation according to the G rod position correction value to obtain the compensated rod position deviation;

[0027] Adjust the rod position of the G rod group according to the compensated rod position deviation.

[0028] Preferably, in the step S1, the step of obtaining the current comprehensive coolant temperature deviation includes:

[0029] Obtain the set value of the average coolant temperature, the measured value of the average coolant temperature, the nuclear power, and the turbine power;

[0030] Calculate the comprehensive coolant temperature deviation according to the set expression.

[0031] Preferably, the set expression is expressed as: where e represents the comprehensive coolant temperature deviation, T ref represents the set value of the average coolant temperature, T av represents the measured value of the average coolant temperature, K1 represents the variable gain, K2 represents the non-linear gain, P1 represents the nuclear power, and P2 represents the turbine power.

[0032] Preferably, in the step S3, the step of the staff adaptively inputting the boron adjustment operation signal based on the real-time state of the control rod group during the reset process of the reactor core includes:

[0033] Observe the real-time state of the control rod group and judge whether the real-time state of the control rod group meets the set requirements;

[0034] When the real-time state of the control rod group does not meet the set requirements, input the boron adjustment operation signal adaptively according to the real-time working conditions. When the real-time state of the control rod group meets the set requirements, do not input the boron adjustment operation signal.

[0035] Preferably, in the step S3, the step of resetting the G rod position correction value includes:

[0036] Gradually reset the G rod position correction value based on the set zeroing rate.

[0037] In addition, the present invention also constructs a computer storage medium storing a computer program, and when the computer program runs, it implements the steps of the above-mentioned reactor core reactivity control method.

[0038] In addition, the present invention also constructs a control 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, it implements the steps of the above-mentioned reactor core reactivity control method.

[0039] In addition, the present invention also constructs a rod control and position system for a nuclear power plant, including the control device described above.

[0040] Implementing the present invention has the following beneficial effects: providing a core reactivity control method, by obtaining the current comprehensive coolant temperature deviation and the R-rod control dead zone to determine whether it is necessary to compensate for the core reactivity. When compensation is required, the G-rod position correction value is determined according to the set operation signal, and the rod positions of the G-rod group are adjusted according to the G-rod position correction value, achieving the technical effect of automatically compensating the rod positions of the G-rod group without manual intervention by staff. This not only reduces the risk of misoperation in manually adjusting the rod positions of the G-rods by staff, but also significantly improves the flexibility of the reactivity control ability of the original rod control and rod group system. It also has the advantages of easy implementation of the optimization scheme and good effect in improving the core stability. BRIEF DESCRIPTION OF THE DRAWINGS

[0041] The present invention will be further described below in conjunction with the drawings and embodiments. In the drawings:

[0042] Figure 1 is the program flow chart of the core reactivity control method in some embodiments of the present invention;

[0043] Figure 2 is the program flow chart of adjusting the rod positions of the G-rod group in some embodiments of the present invention;

[0044] Figure 3 is the circuit structure block diagram of the control device in some embodiments of the present invention. DETAILED DESCRIPTION OF THE EMBODIMENTS

[0045] In order to have a clearer understanding of the technical features, objectives, and effects of the present invention, the specific embodiments of the present invention will now be described in detail with reference to the drawings.

[0046] It should be noted that the flow charts shown in the drawings are only illustrative and do not necessarily include all the contents and operations / steps, nor do they necessarily need to be executed in the described order. For example, some operations / steps can be decomposed, and some operations / steps can be combined or partially combined. Therefore, the actual execution order may be changed according to the actual situation.

[0047] The block diagrams shown in the drawings are only functional entities and do not necessarily correspond to physically independent entities. That is, these functional entities can be implemented in software form, or implemented in one or more hardware modules or integrated circuits, or implemented in different networks and / or processor devices and / or microcontroller devices.

[0048] Figure 1It is a program flowchart of the core reactivity control method in some embodiments of the present invention. This core reactivity control method is used to assist the staff in adjusting the G rod position when the unit experiences a large transient change in load, can quickly compensate for the reactivity change of the core, and improve the stability of the core operating conditions.

[0049] Please refer to Figure 1 , this core reactivity control method may include step S1, step S2, step S3 and step S4.

[0050] Step S1 includes: obtaining the current coolant comprehensive temperature deviation and the R rod control dead zone.

[0051] In some embodiments, the coolant comprehensive temperature deviation can be determined in the following way: obtaining the coolant average temperature set value, the coolant average temperature measured value, the nuclear power and the turbine power; calculating the coolant comprehensive temperature deviation according to the set expression. Among them, the set expression is expressed as: Wherein, e represents the coolant comprehensive temperature deviation, T ref represents the coolant average temperature set value, T av represents the coolant average temperature measured value, K1 represents the variable gain, K2 represents the non - linear gain, P1 represents the nuclear power, and P2 represents the turbine power. The coolant average temperature set value, the coolant average temperature measured value, the nuclear power and the turbine power can be obtained by communicating with the relevant systems of the nuclear power plant (including the reactor coolant system, the rod control and position system, the operation monitoring system, etc.), and the variable gain and the non - linear gain are fixed values or adaptively set by the staff according to the actual operating conditions of the unit.

[0052] It should be noted that the method for determining the R rod control dead zone and related definitions can be referred to the book "Nuclear Reactor Control" by Zhang Jianmin, which will not be elaborated here. Moreover, the R rod control dead zone is a parameter that needs to be monitored during the operation of the existing rod control and position system, so it can be obtained by communicating with the rod control and position system.

[0053] Step S2 includes: judging whether the coolant comprehensive temperature deviation is within the R rod control dead zone. If so, execute step S3; otherwise, execute step S4.

[0054] Step S3 includes: resetting the G rod position correction value, and performing boron adjustment according to the obtained boron adjustment operation signal during the resetting process until the G rod position correction value returns to zero and then returning to S1; wherein, the boron adjustment operation signal is a boron adjustment operation signal adaptively input by the staff based on the real - time state of the control rod group during the resetting process of the core.

[0055] It should be noted that since the correction value of the G-rod position affects the control of the G-rod group by the rod control and position system of the nuclear power plant, which is not conducive to the stable operation of the reactor core under normal conditions. Therefore, when the comprehensive coolant temperature deviation is within the control dead zone of the R-rod, the correction value of the G-rod position is not required to participate in the control process of the G-rod group. Therefore, it is necessary to reset the correction value of the G-rod position to zero to restore the regulation margin of the rod control.

[0056] It should be noted that if the correction value of the G-rod position is suddenly reset to zero after the comprehensive coolant temperature deviation returns to the control dead zone of the R-rod, it will cause a disturbance in the core power. To avoid this situation, the influence of the reset process of the G-rod position correction value can be compensated by boron adjustment operation, so that the core power can remain stable during the entire reset process of compensating the G-rod position correction value.

[0057] Furthermore, the staff can input the boron adjustment operation signal based on the following steps: observe the real-time state of the control rod group and judge whether the real-time state of the control rod group meets the set requirements; when the real-time state of the control rod group does not meet the set requirements, input the boron adjustment operation signal adaptively according to the real-time working conditions, and when the real-time state of the control rod group (including the real-time states of the R-rod and G-rod) meets the set requirements, do not input the boron adjustment operation signal. Specifically, the correction value of the G-rod position will cause changes in the core working conditions, resulting in automatic adjustment of the R-rod, leading to the risk that the R-rod deviates from the adjustment band, and at the same time, the G-rod also has the risk of deviating from the established position. Therefore, the staff can judge that the real-time state of the control rod group does not meet the set requirements by observing the real-time state of the control rod group, and when it is found that the R-rod has the risk of deviating from the adjustment band and the G-rod has the risk of deviating from the established position, etc., then input the boron adjustment operation signal adaptively to stabilize the control rod group within the set position. Of course, if the real-time state of the control rod group meets the set requirements, there is no need to input the boron adjustment operation signal. Before the correction value of the G-rod position is reset to zero, even if no boron adjustment operation signal is obtained, the correction value of the G-rod position will still continue to be reset to zero. It should be noted that the risks of over-adjustment and under-adjustment in automatic boron adjustment are relatively large. Therefore, the boron adjustment process needs to rely on the staff to manually adjust according to the real-time state of the control rod group to meet the requirements of stabilizing the core working conditions.

[0058] In some embodiments, step S3 may further include: when the comprehensive coolant temperature deviation returns from outside the control dead zone of the R-rod to within the control dead zone of the R-rod, a prompt signal is also output to remind the staff to input the boron adjustment operation signal according to the real-time core working conditions as required. Since the correction value of the G-rod position needs to be reset after the comprehensive coolant temperature deviation returns to the control dead zone of the R-rod, and the reset process may require boron adjustment, and the purpose of this embodiment is to remind the staff to pay attention to the real-time core working conditions after the comprehensive coolant temperature deviation returns to the control dead zone of the R-rod, so as to input the boron adjustment operation signal as required.

[0059] It should be noted that since the boron adjustment intensity required by the core at different operating powers is different, in order to ensure safety and reliability, the boron adjustment operation needs to be manually controlled by the staff according to the actual situation. In addition, for the specific method of manually adjusting boron by the staff inputting boron adjustment operation signals through the man-machine interaction device, please refer to the existing technology and will not be elaborated here.

[0060] In order to further ensure that the core power can remain stable during the reset process of the G-rod position correction value, in some embodiments, the G-rod position correction value can be reset in the following manner: gradually zero the G-rod position correction value based on the set zeroing rate. Among them, the set zeroing rate is a value that can be set, which can be adaptively set by the staff according to the core power.

[0061] Step S4 includes: obtaining a set operation signal, determining the G-rod position correction value according to the set operation signal, adjusting the rod positions of the G-rod group according to the G-rod position correction value, and returning to step S1 after the adjustment.

[0062] It should be noted that adjusting the rod positions of the G-rod group according to the G-rod position correction value may not be able to immediately bring the comprehensive coolant temperature deviation back to the R-rod control dead zone. Therefore, it is necessary to return to step S1 to determine whether to reset the G-rod position correction value or adjust the G-rod position correction value according to the real-time comprehensive coolant temperature deviation, the R-rod control dead zone and the set operation signal. It is easy to understand that during the core reactivity compensation process, the G-rod position correction value will be iteratively adjusted based on the real-time set operation signal, so that a more suitable G-rod position correction value can be obtained based on the real-time conditions of the core, which helps to improve the compensation efficiency and the stability of the core conditions.

[0063] In some embodiments, the set operation signal includes an axial power deviation signal, an operating limit range, a coolant average temperature signal, and an R-rod position signal. Correspondingly, the G-rod position correction value can be determined by performing the following steps: determining whether the axial power deviation signal exceeds the operating limit range, if so, keeping the G-rod position correction value unchanged, otherwise adjusting the G-rod position correction value according to the coolant average temperature signal and the R-rod position signal.

[0064] In this embodiment, the axial power deviation signal can be obtained from the nuclear instrumentation system, and the R-rod position signal (used to represent the real-time position of the R-rod group) and the operating limit range can be obtained from the rod control and position system. The operating limit range is used to give an early warning of the change of the real-time axial power deviation. When the axial power deviation is less than the lower limit value (i.e., the left limit value) or greater than the upper limit value (i.e., the right limit value) of the operating limit range, it indicates that the reactor has a risk of exceeding the operating limit area. If the rod positions of the G-rod group are adjusted when it exceeds, it may exacerbate the adverse impact on the axial power distribution of the core. Therefore, when the axial power deviation signal exceeds the operating limit range, the G-rod position correction value needs to remain unchanged.

[0065] Since some existing operation monitoring systems will output a C21 pre-alarm signal when the axial power deviation signal exceeds the operation limit range, as a control instruction for the steam turbine to quickly reduce the load, in another embodiment, it is possible to communicate with the operation monitoring system to determine whether the C21 pre-alarm signal output by the rod control and rod position system is detected, and when the C21 pre-alarm signal is detected, it is determined that the axial power deviation signal exceeds the operation limit range.

[0066] Furthermore, the G rod position correction value can be adjusted according to the coolant average temperature signal and the R rod position signal by performing the following steps: determine whether the coolant average temperature signal is less than the set temperature threshold, and if so, gradually increase the G rod position correction value; determine whether the R rod position signal is less than the set rod position threshold, and if so, gradually decrease the G rod position correction value.

[0067] It should be noted that the present invention uniformly describes the change of the G rod position in terms of the proposed step angle. The G rod position correction value can be either positive or negative. When the G rod position correction value is positive, it will perform a positive compensation on the target rod position of the G rod, which is equivalent to increasing the target rod position. When the G rod position correction value is negative, it will perform a negative compensation on the target rod position of the G rod, which is equivalent to decreasing the target rod position.

[0068] During the daily operation of the reactor core, when the core temperature or power is too low, the R rods may have been fully withdrawn (i.e., at the maximum step position) or withdrawn to a relatively high position. At this time, the ability of the R rod group to adjust the core temperature or power has been lost or weakened. Therefore, it is necessary for the G rods to compensate for reactivity, increase the G rod position correction value, and accelerate the G rod withdrawal speed to achieve the purpose of quickly compensating for the core reactivity. When the core temperature or power is too high, the R rods may have been inserted to the predetermined minimum step position or the minimum step position allowed to be inserted. At this time, the ability of the R rod group to adjust the core temperature or power has been lost or weakened. Therefore, it is necessary for the G rods to compensate for reactivity, decrease the G rod position correction value, and accelerate the G rod insertion speed to achieve the purpose of quickly compensating for the core reactivity. It is easy to understand that gradually increasing or gradually decreasing the G rod position correction value can avoid unnecessary disturbances in the core power caused by too large a correction amplitude of the G rod position, which helps to improve the stability of the core operating conditions.

[0069] Since some existing rod control and rod position systems will output a C22 pre-alarm signal when the core temperature or power is too low, as a determination of the core subcooling state, in another embodiment, it is possible to communicate with the rod control and rod position system to determine whether the C22 pre-alarm signal output by the rod control and rod position system is detected, and when the C22 pre-alarm signal is detected, it is determined that the coolant average temperature signal is less than the set temperature threshold.

[0070] In order to further improve the stability of the core operating conditions, in some embodiments, in the step of adjusting the G-rod position correction value according to the average coolant temperature signal and the R-rod position signal, the G-rod position correction value is gradually increased or gradually decreased at a set rate. In this embodiment, since there are differences in the control rod groups of different units, the values of the set rate also vary. Therefore, the set rate can be adaptively set by the staff according to the actual situation of the unit, or the unit operating conditions can be simulated through the existing unit simulation model, and the transient process of the unit's large-scale load increase and decrease can be used for demonstration to determine the value of the set rate.

[0071] Figure 2 is the program flow chart for adjusting the positions of the G-rod group in some embodiments of the present invention. Please refer to Figure 2 , and the positions of the G-rod group can be adjusted according to the G-rod position correction value by executing step S41 to step S42.

[0072] Step S41 includes: obtaining the target rod position and the actual rod position of the G-rod group. In this step, the target rod position and the actual rod position of the G-rod group can be obtained by communicating with the rod control rod position system.

[0073] Step S42 includes: taking the difference between the target rod position and the actual rod position to obtain the rod position deviation.

[0074] Step S43 includes: compensating the rod position deviation according to the G-rod position correction value to obtain the compensated rod position deviation. In this step, the compensated rod position deviation can be obtained by summing the G-rod position correction value and the rod position deviation.

[0075] Step S44 includes: adjusting the positions of the G-rod group according to the compensated rod position deviation. It is easy to understand that the compensated rod position deviation can replace the (pre-compensation) rod position deviation and be input into the existing rod position control program to achieve the control of the positions of the G-rod group. The principle of the control of the positions of the G-rod group refers to the prior art and will not be elaborated here.

[0076] Implementing the technical solution of the present invention, by obtaining the current comprehensive coolant temperature deviation and the R-rod control dead zone to determine whether compensation for the core reactivity is required, and when compensation is required, determining the G-rod position correction value according to the set operation signal and adjusting the positions of the G-rod group according to the G-rod position correction value, the technical effect of automatically compensating the positions of the G-rod group without manual intervention by the staff is achieved. This not only reduces the risk of misoperation in manually adjusting the positions of the G-rods by the staff, but also significantly improves the flexibility of the reactivity control ability of the original rod control rod group system. It is easy to understand that the present invention can achieve the above beneficial effects by optimizing the software program. Implementing this technical solution requires easy optimization and improvement of the technology, and can significantly improve the core stability.

[0077] The present invention also provides a computer storage medium storing a computer program, and when the computer program runs, the steps of the core reactivity control method provided by the embodiments of the present invention are implemented.

[0078] As Figure 3 shown, the present invention also provides a control 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 core reactivity control method provided by the embodiments of the present invention are implemented.

[0079] The present invention also provides a rod control and rod position system for a nuclear power plant, including the control device provided by the embodiments of the present invention.

[0080] In the present specification, the various embodiments are described in a progressive manner. Each embodiment focuses on the differences from other embodiments. For the same or similar parts among the various embodiments, reference can be made to each other. For the devices disclosed in the embodiments, since they correspond to the methods disclosed in the embodiments, the description is relatively simple, and reference can be made to the description of the method part for the relevant parts.

[0081] Those skilled in the art can further realize that the units and algorithm steps of the examples described in combination with the embodiments disclosed herein can be implemented by electronic hardware, computer software, or a combination of the two. To clearly illustrate the interchangeability of hardware and software, the composition and steps of the examples have been generally described according to functions in the above description. Whether these functions are executed in a hardware or software manner depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementation should not be considered to exceed the scope of the present invention.

[0082] The steps of the methods or algorithms described in combination with the embodiments disclosed herein can be directly implemented by hardware, software modules executed by a processor, or a combination of the two. The software modules can be placed in a random access memory (RAM), internal memory, read-only memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, removable disk, CD-ROM, or any other form of storage medium known in the technical field.

[0083] It can be understood that the above embodiments only represent the preferred embodiments of the present invention, and the description is relatively specific and detailed, but it should not be construed as a limitation on the scope of the patent of the present invention. It should be noted that for those of ordinary skill in the art, without departing from the concept of the present invention, the above technical features can be freely combined, and several modifications and improvements can also be made, which all belong to the protection scope of the present invention. Therefore, all equivalent transformations and modifications made to the scope of the claims of the present invention should fall within the scope covered by the claims of the present invention.

Claims

1. A core reactivity control method, characterized in that: The following steps are involved: S1. Obtain the current coolant comprehensive temperature deviation and R rod control dead zone; S2, determining whether the coolant comprehensive temperature deviation is within the R-rod control dead zone, if so, executing S3, otherwise executing S4; S3, resetting the G-rod position correction value, and performing boron adjustment according to the obtained boron adjustment operation signal during the resetting process, until the G-rod position correction value returns to zero and then returns to S1; wherein the boron adjustment operation signal is a boron adjustment operation signal adaptively input by the staff based on the real-time state of the control rod group of the core during the resetting process; S4, obtaining a set operation signal, determining a G-rod position correction value according to the set operation signal, adjusting the rod position of the G-rod group according to the G-rod position correction value, and returning to S1 after the adjustment.

2. The core reactivity control method according to claim 1, characterized in that: The set operation signal includes an axial power deviation signal, an operation limit range, a coolant average temperature signal and an R rod position signal; In said S4, the step of determining the G-rod position correction value according to said set operation signal comprises: Determine whether the axial power deviation signal exceeds the operating limit range. If so, keep the G-rod position correction value unchanged; otherwise, adjust the G-rod position correction value according to the coolant average temperature signal and the R-rod position signal.

3. The core reactivity control method according to claim 2, characterized in that: The step of determining whether the axial power deviation signal exceeds an operating limit range comprises: Determine whether the C21 pre-alarm signal output by the rod control rod position system is obtained; When the C21 pre-alarm signal is obtained, it is determined that the axial power deviation signal exceeds the operating limit range.

4. The core reactivity control method according to claim 2, characterized in that: The step of adjusting the G rod position correction value according to the coolant average temperature signal and the R rod position signal comprises: Determine whether the coolant average temperature signal is less than a set temperature threshold, and if so, gradually increase the G-rod position correction value.

5. The core reactivity control method according to claim 4, characterized in that: The step of determining whether the coolant average temperature signal is less than a set temperature threshold comprises: Determine whether the C22 pre-alarm signal output by the rod control rod position system is obtained; When the C22 pre-alarm signal is obtained, it is determined that the coolant average temperature signal is less than the set temperature threshold.

6. The core reactivity control method according to claim 4, characterized in that: The step of adjusting the G rod position correction value according to the coolant average temperature signal and the R rod position signal further includes: Determine whether the R rod position signal is less than a set rod position threshold, and if so, gradually reduce the G rod position correction value.

7. The core reactivity control method according to claim 6, characterized in that: In the step of adjusting the G-rod position correction value according to the coolant average temperature signal and the R-rod position signal, the G-rod position correction value is gradually increased or decreased at a set rate.

8. The core reactivity control method according to claim 1, characterized in that: In said S4, the step of adjusting the rod position of the G rod group according to the G rod position correction value comprises: Obtaining a target rod position and an actual rod position of the G rod group; Calculating the difference between the target stick position and the actual stick position to obtain a stick position deviation; Compensating the rod position deviation according to the G rod position correction value to obtain a compensated rod position deviation; The rod positions of the G rod group are adjusted according to the compensated rod position deviation.

9. The core reactivity control method according to claim 1, characterized in that: In S1, the step of obtaining the current coolant comprehensive temperature deviation includes: Obtain coolant average temperature set value, coolant average temperature measurement value, nuclear power and turbine power; The coolant comprehensive temperature deviation is calculated according to a set expression.

10. The core reactivity control method according to claim 9, characterized in that: The setting expression is expressed as: Wherein, e represents the comprehensive temperature deviation of the coolant, T ref represents the coolant average temperature setting value, T av represents the measured value of the average coolant temperature, K1 represents the variable gain, K2 represents the nonlinear gain, P1 represents the nuclear power, and P2 represents the turbine power.

11. The core reactivity control method according to claim 1, characterized in that: In said S3, the step of the staff adaptively inputting the boron adjustment operation signal based on the real-time status of the control rod group during the core reset process includes: Observe the real-time state of the control rod group and determine whether the real-time state of the control rod group meets the set requirements; When the real-time state of the control rod group does not meet the set requirements, the boron adjustment operation signal is adaptively input according to the real-time operating conditions; when the real-time state of the control rod group meets the set requirements, the boron adjustment operation signal is not input.

12. The core reactivity control method according to any one of claims 1 to 11, characterized in that: In said S3, the step of resetting the G-stick position correction value comprises: The G-bar position correction value is gradually returned to zero based on a set zeroing rate.

13. A computer storage medium, characterized in that: A computer program is stored, and when the computer program is executed, the steps of the core reactivity control method according to any one of claims 1 to 11 are implemented.

14. A control 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 core reactivity control method according to any one of claims 1 to 11 are implemented.

15. A rod position control system for a nuclear power plant, characterized in that: Comprising a control device as claimed in claim 14.

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