A method, system, device and readable storage medium for matching control of a power of a stacker

Abstract

The present application relates to a kind of reactor power matching control method, control system, equipment and readable storage medium.The reactor power matching control method includes the following steps:S1, the operating state of coolant pump is detected, whether single trip occurs is judged, if occurs, then execute S2;S2, whether the reactor power is greater than the first predetermined value P1 is judged, if greater, execute step S3;S3, whether the reactor power is greater than the second predetermined value P2 is judged, P2>P1, if greater, enter step S4;If not greater, execute step S4;S4, reduce the core power;S5, control steam turbine power to reduce to the fourth predetermined value P targ , wait for delay;S6, whether the reactor power is less than P1 is judged, if not less than, execute step S7;S7, trigger reactor emergency shutdown;S8, end.The technical scheme of the present application can be realized in the premise of guaranteeing the safety of core, reduce unplanned shutdown, improve the continuity and economy of nuclear power plant operation.

Description

Technical Field

[0001] This invention relates to the field of nuclear power plant operation control technology, and in particular to a reactor power matching control method, control system, equipment and readable storage medium. Background Technology

[0002] During the operation of a nuclear power plant, the reactor coolant pump (RCP) drives the coolant to circulate within the primary loop system, which consists of the reactor pressure vessel, primary loop piping, and steam generator. The heat power Pcore generated by nuclear fission in the reactor core is absorbed by the coolant, which then transfers the heat to the steam generator to heat the secondary loop working fluid to generate steam, which in turn drives the turbine generator set to produce electricity.

[0003] When a single RCP trips, the primary coolant flow rate will decrease significantly. If the core power remains at the original level, the decrease in primary coolant flow rate due to the tripped pump will cause thermal safety issues such as an increase in the average coolant temperature and localized heat transfer deterioration.

[0004] In existing technologies, reactor control systems typically do not proactively regulate power in response to a single RCP trip. Instead, they rely on a conservative strategy of the protection system: when the coolant flow rate falls below a set threshold or the pump speed drops significantly, an emergency reactor shutdown is triggered to avoid risks such as deviating from nucleation boiling or fuel cladding overheating. However, while this conservative strategy ensures nuclear safety, it significantly increases the probability of unplanned shutdowns, severely impacting the continuity and economic efficiency of nuclear power plant operations. Summary of the Invention

[0005] To address the aforementioned problems in the prior art, this invention proposes a reactor power matching control method, control system, equipment, and readable storage medium. When a single reactor coolant pump trips, this method reduces unplanned shutdowns while ensuring core safety, thereby improving the continuity and economy of nuclear power plant operation.

[0006] Specifically, this invention proposes a reactor power matching control method, applied to a reactor, comprising the following steps:

[0007] S1, Detect the operating status of the coolant pumps of the reactor and determine whether a single coolant pump has tripped. If not, proceed to step S8; if so, execute step S2.

[0008] S2, determine whether the reactor power is greater than the first predetermined value P1. If the reactor power is less than or equal to P1, proceed to step S8; if the reactor power is greater than P1, execute step S3.

[0009] S3. Determine whether the reactor power is greater than a second predetermined value P2, where P2 > P1. If the reactor power > P2, proceed to step S4; if P1 < reactor power ≤ P2, execute step S5;

[0010] S4. Reduce the core power at a predetermined rate;

[0011] S5. Control the steam turbine to reduce the turbine power from the current value to a fourth predetermined value P at a third predetermined load reduction rate r; targ and wait for a delay time of a fifth predetermined value t; delay ;

[0012] S6. Determine whether the reactor power is less than the first predetermined value P1. If the reactor power < P1, transfer to step S8; if the reactor power ≥ P1, transfer to step S7;

[0013] S7. Trigger an emergency reactor shutdown;

[0014] S8. End.

[0015] According to an embodiment of the present invention, the setting range of the first predetermined value P1 is 40% - 60% of the maximum reactor power.

[0016] According to an embodiment of the present invention, the setting range of the second predetermined value P2 is 60% - 80% of the maximum reactor power.

[0017] According to an embodiment of the present invention, the setting range of the third predetermined value r is 50% / min - 200% / min of the maximum steam turbine power; the fourth predetermined value P targ matches the thermal power of the reactor at a low power level, and the setting range of the fourth predetermined value P targ is 40% - 60% of the maximum steam turbine power.

[0018] According to an embodiment of the present invention, the fifth predetermined value t delay is used to provide a time margin for the steam turbine load reduction and the core power response, and the setting range of the fifth predetermined value t delay is 5s - 15s.

[0019] According to an embodiment of the present invention, in step S3, the core power is reduced at a predetermined rate by using boron injection or control rod insertion.

[0020] The present invention also provides a reactor - turbine power matching control system, including:

[0021] An RCP status detection unit for detecting the operating status of the coolant pumps of the reactor and determining whether a single coolant pump trips;

[0022] The reactor power determination unit is used to determine the relationship between the reactor power and the first predetermined value P1 and the second predetermined value P2.

[0023] The power reduction triggering unit is used to trigger a reduction in core power at a predetermined rate when the reactor power > P2 and a single coolant pump trips.

[0024] The turbine load regulation unit is used to control the turbine to reduce the load at a third predetermined value r to a fourth predetermined value P when P1 < reactor power ≤ P2, or after triggering a reduction in core power at a predetermined rate. targ ;

[0025] A delay waiting unit is used when the steam turbine reduces its load at a third predetermined value r to a fourth predetermined value P. targ Then, wait for the fifth predetermined value t. delay The delay time;

[0026] The stop trigger unit is used to wait for the fifth predetermined value t. delay Then, it is determined whether the reactor power is less than P1, and an emergency reactor shutdown is triggered when the reactor power is ≥ P1.

[0027] According to one embodiment of the present invention, the reactor power matching control system further includes a logic operation unit, which is used to perform AND and NOT logic operations on the reactor power status signal obtained by the RCP status detection unit and the single coolant trip signal to generate a trigger signal for reducing the core power at a predetermined rate, a turbine load reduction command signal, or a reactor emergency shutdown trigger signal.

[0028] According to one embodiment of the present invention, the reactor power matching control system further includes a parameter switching unit, which includes a turbine power target value switching switch and a turbine load reduction rate switching switch, respectively used to select a fourth predetermined value P after receiving a turbine load reduction command. targ The third predetermined value r is selected as the target value for the turbine power reduction rate.

[0029] The present invention also provides a stacker power matching control device, including a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the processor executes the computer program to implement the steps of any of the aforementioned stacker power matching control methods.

[0030] The present invention also provides a computer-readable storage medium having a computer program stored thereon, wherein the computer program, when executed by a processor, implements the steps of the stacker power matching control method described in any of the preceding claims.

[0031] This invention provides a reactor power matching control method, control system, equipment, and readable storage medium. When a single reactor coolant pump trips, it actively coordinates the power of the reactor and the turbine to rematch the core thermal power, turbine power, and the reduced coolant flow rate. This reduces unplanned outages and improves the continuity and economy of nuclear power plant operation while ensuring core safety.

[0032] It should be understood that the above general description and the following detailed description of the present invention are exemplary and illustrative, and are intended to provide further explanation of the present invention. Attached Figure Description

[0033] The accompanying drawings are included to provide further explanation of the invention; they are incorporated into and constitute a part of this application. The drawings illustrate embodiments of the invention and, together with this specification, serve to explain the principles of the invention. In the drawings:

[0034] Figure 1 A flowchart of a stacker power matching control method according to an embodiment of the present invention is shown.

[0035] Figure 2 A schematic diagram of the stacker power matching control system according to an embodiment of the present invention is shown.

[0036] Figure 3 The diagram shows the reactor matching control principle of a nuclear power plant.

[0037] Figure 4 A system block diagram of a stacker power matching control device according to an embodiment of the present invention is shown. Detailed Implementation

[0038] It should be noted that, unless otherwise specified, the embodiments and features described in this application can be combined with each other.

[0039] The technical solutions of the embodiments of this application will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of this application, and not all embodiments. The following description of at least one exemplary embodiment is merely illustrative and is in no way intended to limit this application or its application or use. All other embodiments obtained by those skilled in the art based on the embodiments of this application without creative effort are within the scope of protection of this application.

[0040] It should be noted that the terminology used herein is for the purpose of describing particular embodiments only and is not intended to limit the exemplary embodiments according to this application. As used herein, the singular form is intended to include the plural form as well, unless the context clearly indicates otherwise. Furthermore, it should be understood that when the terms "comprising" and / or "including" are used in this specification, they indicate the presence of features, steps, operations, devices, components, and / or combinations thereof.

[0041] Unless otherwise specifically stated, the relative arrangement, numerical expressions, and values ​​of the components and steps described in these embodiments do not limit the scope of this application. It should also be understood that, for ease of description, the dimensions of the various parts shown in the drawings are not drawn to actual scale. Techniques, methods, and devices known to those skilled in the art may not be discussed in detail, but where appropriate, such techniques, methods, and devices should be considered part of the specification. In all examples shown and discussed herein, any specific values ​​should be interpreted as merely exemplary and not as limitations. Therefore, other examples of exemplary embodiments may have different values. It should be noted that similar reference numerals and letters in the following drawings denote similar items; therefore, once an item is defined in one drawing, it need not be further discussed in subsequent drawings.

[0042] In the description of this application, it should be understood that the orientation or positional relationship indicated by directional terms such as "front, back, up, down, left, right", "horizontal, vertical, horizontal" and "top, bottom" is usually based on the orientation or positional relationship shown in the accompanying drawings, and is only for the convenience of describing this application and simplifying the description. Unless otherwise stated, these directional terms do not indicate or imply that the device or element referred to must have a specific orientation or be constructed and operated in a specific orientation, and therefore should not be construed as a limitation on the scope of protection of this application; the directional terms "inner" and "outer" refer to the inner and outer contours relative to the outline of each component itself.

[0043] Furthermore, it should be noted that the use of terms such as "first" and "second" to define components is merely for the purpose of distinguishing the corresponding components. Unless otherwise stated, these terms have no special meaning and therefore should not be construed as limiting the scope of protection of this application. In addition, although the terminology used in this application is selected from commonly known and used terms, some terms mentioned in this application's specification may have been chosen by the applicant according to his or her judgment, and their detailed meanings are explained in the relevant sections of this description. Moreover, this application should be understood not only through the actual terms used, but also through the meaning implied by each term.

[0044] Figure 1A flowchart of a reactor power matching control method according to an embodiment of the present invention is shown. As shown, the reactor power matching control method is applied to a reactor coolant pump trip scenario. Through various stages such as "trip detection - power judgment - tiered adjustment," it achieves coordinated matching of reactor power, reducing unplanned outages while ensuring core safety. The reactor power matching control method includes the following steps:

[0045] S1. Detect the operating status of the coolant pumps and determine if a single coolant pump trips. If no single coolant pump trip is detected, it indicates that the coolant circulation is not affected and the reactor power is still in a normal matching state, requiring no additional adjustment. Proceed to step S8, and the process ends. If a single coolant pump trips, it indicates that the coolant flow rate will decrease, which may cause core thermal safety issues. The subsequent power regulation process needs to be initiated, and step S2 is executed.

[0046] S2, determine whether the reactor power is greater than the first predetermined value P1. If the reactor power is ≤ P1, it means that even if the coolant flow rate decreases due to the tripping of a single coolant pump, the matching relationship between the core heat load and the coolant flow rate is still within an acceptable and safe range, and there will be no risk of heat transfer deterioration. Proceed to step S8, and the process ends. If the reactor power is > P1, it means that the current core heat load is high, and the power and flow rate mismatch is likely to occur after the coolant flow rate decreases. It is necessary to further determine the power level to determine the adjustment method. Proceed to step S3.

[0047] S3. Determine if the reactor power is greater than the second predetermined value P2, and set P2>P1. If the reactor power > P2, it indicates that the core heat load is already at a high level, and the risk of power-flow mismatch after a single coolant pump trips is obvious. It is necessary to quickly reduce the core power to reduce the core heat load and create safe conditions for subsequent turbine power regulation. Proceed to step S4. If P1 < reactor power ≤ P2, it indicates that although the core heat load is higher than the safety threshold, the risk of mismatch is relatively low. Proceed directly to step S5.

[0048] S4, reduce core power at a predetermined rate;

[0049] S5 controls the turbine to reduce its power from the current value to the fourth predetermined value P based on the load reduction rate of the third predetermined value r. targ Waiting for the fifth predetermined value t delay The delay time; among which, the setting of the third predetermined value r needs to take into account both adjustment efficiency and equipment stability, to avoid equipment shock caused by excessively rapid load reduction, and the fourth predetermined value P targ This needs to be matched with the thermal power of the reactor core at low power levels to ensure that the reactor power is rebalanced after adjustment, thus alleviating the thermal safety pressure caused by the decrease in coolant flow; the fifth predetermined value t delayThe purpose of this setting is to provide sufficient time margin for the core power response after the turbine load is reduced, and to avoid misoperation caused by making safety judgments before the power has stabilized.

[0050] S6. Then determine whether the reactor power is less than P1. If it is less, it means that the reactor power has achieved safe matching. Proceed to step S8 and end the process. If the reactor power is greater than or equal to P1, it means that the current adjustment measures have not achieved the expected effect and there is still a thermal safety risk in the reactor core. Therefore, proceed to step S7.

[0051] S7 triggers an emergency reactor shutdown, ensuring core safety through forced shutdown.

[0052] S8, End.

[0053] In some examples, the first predetermined value P1 is the core low-power safe operation threshold, providing a clear benchmark for judging the core safety status under the condition of a single reactor coolant pump tripping. When the reactor power is at or below P1, even if the coolant flow rate decreases due to a single pump trip, the matching relationship between the core heat load and the coolant flow rate can still be maintained within an acceptable safe range, without causing abnormal increases in the average coolant temperature or local heat transfer deterioration, thus eliminating the need to initiate additional power regulation procedures. From the perspective of practical application adaptability, the setting range of the first predetermined value P1 is 40% to 60% of the reactor's maximum power, preferably 50%. The setting range of the first predetermined value P1 can effectively balance "core safety" and "operational continuity" after a single reactor coolant pump trips, providing a reliable threshold basis for subsequent power judgment and regulation.

[0054] In some examples, the second predetermined value P2 is the trigger threshold for rapidly reducing core power, providing a boundary for the high-risk power range under single reactor coolant pump tripping conditions. When the reactor power exceeds P2, it means the core thermal load is already at a high level. At this point, the coolant flow rate decreases due to the tripping of a single coolant pump, significantly increasing the risk of mismatch between core thermal load and coolant flow rate. If only turbine load reduction is used for adjustment, it may not be able to alleviate the core thermal pressure in time. Therefore, it is necessary to prioritize the intervention of rapidly reducing core power to reduce core thermal load in advance and reduce safety risks. The setting range of the second predetermined value P2 is 60% to 80% of the reactor's maximum power, preferably 70%. The determination of this range is based on a comprehensive derivation of the nuclear power plant core thermal characteristics, coolant flow decay patterns, and the response efficiency of rapid power reduction methods (such as boron injection and rapid control rod insertion). On the one hand, it avoids delays in identifying high-risk power ranges due to excessively high P2 settings, preventing intervention from being initiated only after excessive heat load and accumulated mismatch risks, thus missing the safe control window. On the other hand, it also prevents the "requiring rapid core power reduction" range from being excessively expanded due to excessively low P2 settings, leading to unnecessary aggressive adjustments and affecting core operational stability. When the reactor power is between P1 and P2, the risk of core heat load and flow mismatch is moderate, and power matching can be achieved by reducing the turbine load. When the power exceeds P2, the risk escalates to a high level, requiring rapid core power reduction first, followed by turbine adjustment. This tiered triggering mechanism ensures precise matching between control measures and risk levels, guaranteeing core safety under high-power conditions while avoiding the impact of excessive control on operational continuity.

[0055] In some examples, the third predetermined value r and the fourth predetermined value P targ These parameters together constitute the turbine power regulation parameters. They are based on the regulation rate and regulation target, respectively, to ensure that the turbine power can quickly and accurately match the core thermal power after a single reactor coolant pump trips. The third predetermined value *r* is the turbine load reduction rate parameter, which controls the dynamic process of turbine power reduction. It must ensure that the load reduction rate is sufficient to respond to the core thermal power adaptation requirements caused by the decrease in coolant flow, avoiding prolonged power mismatch due to regulation lag; it must also consider the characteristics of the turbine equipment to prevent mechanical damage such as a sudden increase in internal thermal stress and excessive blade vibration caused by an excessively rapid load reduction rate. Based on a comprehensive consideration of the turbine's design tolerance, core power response speed, and coolant flow decay law, the setting range of the third predetermined value *r* is defined as 50% / min to 200% / min of the turbine's maximum power, preferably 100% / min. Within this range, the turbine can essentially complete the transition from current power to target power within one minute. This allows it to quickly adapt to changes in core power while simultaneously controlling transient shocks within a safe margin through smooth rate control, thus avoiding the risk of unplanned shutdowns. Fourth predetermined value Ptarg The target power for reducing the load on the steam turbine is matched to the thermal power of the reactor at a low power level. Based on the setting of the first predetermined value P1, the fourth predetermined value P... targ The setting range is 40% to 60% of the turbine's maximum power, preferably 50%. When the turbine power drops to P... targ At this time, the heat absorbed by the secondary loop can maintain a balance with the thermal power output of the reactor core below P1. This range avoids both the safety risks associated with excessively high power and the significant decline in the economic efficiency of the power plant due to excessively low power, thus achieving a balance between safety and economy.

[0056] In some examples, the fifth predetermined value t delay The delay time for determining power regulation provides a time margin for turbine load reduction and core power response, preventing accidental shutdowns or insufficient power matching caused by premature judgment before regulation is complete. This is a key redundancy design element ensuring the accuracy and safety of reactor power coordination control. Fifth predetermined value t delay The set range is 5s to 15s, preferably 9s. This duration fully covers the time required for the turbine to reduce its power from its current level to P. targ The physical process (calculated by r, even if it drops from full power to P) targ The process takes only about 0.5 minutes (5s to 15s ensures basic stability of the adjustment), and it also allows for a buffer time for the feedback response of the reactor core thermal power, avoiding judgment errors caused by the reactor core power lagging behind the turbine power. At the same time, this range avoids the problems of insufficient adjustment due to too short a delay (less than 5s) and increased risk of high power mismatch due to too long a delay (more than 15s), thus achieving a balance between "judgment accuracy" and "timely risk control".

[0057] In some examples, in step S3, boron injection or control rod insertion is used to reduce core power at a predetermined rate. Both methods intervene in the core nuclear fission reaction process to rapidly reduce core thermal power, providing a safety buffer for high-risk conditions after a single reactor coolant pump trips and before turbine power regulation. The core principle of boron injection is to utilize boron's strong neutron absorption properties. Injecting a boron-containing solution into the primary coolant reduces the effective neutron flux rate in the core, decreasing fission and achieving a rapid decrease in core power. This method is advantageous because it is gradual and controllable, avoiding thermal shock. Control rod insertion relies on the strong neutron absorption capacity of the control rods themselves to achieve power regulation. When the reactor power is significantly higher than P2 and the risk of core thermal load mismatch with coolant flow is high, the control rod drive mechanism rapidly inserts the control rods into the active region of the core. Through physical shielding and neutron absorption, the number of fission neutrons is drastically reduced, rapidly lowering core power. This method is advantageous because of its fast response and suitability for situations requiring urgent risk control.

[0058] Figure 2 A schematic diagram of a stacker power matching control system according to an embodiment of the present invention is shown. As shown in the figure, the stacker power matching control system 200 includes:

[0059] RCP status detection unit 201 is used to detect the operating status of the reactor coolant pumps and determine whether a single coolant pump trips.

[0060] The reactor power determination unit 202 receives the detection results from the RCP status detection unit 201 and uses them to determine the relationship between the reactor power and the first predetermined value P1 and the second predetermined value P2. When the reactor power is ≤ P1, no additional intervention is required; when the power is > P1, it further distinguishes whether it exceeds the second predetermined value P2, thereby determining whether to directly adjust the turbine power or to first rapidly reduce the core power and then adjust the turbine power, so as to ensure that the control measures are adapted to the risk level.

[0061] The power reduction trigger unit 203 is used to trigger a reduction in core power at a predetermined rate when the reactor power > P2 and a single coolant pump trips, so as to avoid the continuous mismatch between high power and low flow rate leading to the deterioration of thermal safety and to create a safe premise for subsequent turbine regulation.

[0062] The turbine load regulation unit 204 is used to control the turbine to reduce the load at a third predetermined value r to a fourth predetermined value P when P1 < reactor power ≤ P2, or after triggering a reduction in core power at a predetermined rate. targ This ensures that the turbine power matches the low power level of the reactor core, thus alleviating the thermal load pressure caused by the decrease in coolant flow from an energy balance perspective.

[0063] The delay waiting unit 205 is used to wait for the steam turbine to reduce its load at a rate of decrease of a third predetermined value r to a fourth predetermined value P. targ Then, wait for the fifth predetermined value t. delay The delay time;

[0064] The shutdown trigger unit 206 determines whether the reactor power is less than P1 after the turbine adjustment is completed, and triggers an emergency reactor shutdown when the reactor power is ≥ P1.

[0065] In some examples, the reactor power matching control system 200 also includes a logic operation unit 207. The logic operation unit 207 performs AND and NOT logic operations on the reactor power status signal acquired by the RCP status detection unit 201 and the single coolant pump trip signal to generate a trigger signal for rapidly reducing core power, a turbine load reduction command signal, or a reactor emergency shutdown trigger signal. Specifically, the logic operation unit 207 receives the single coolant pump trip signal from the RCP status detection unit 201, as well as the power status signal reflecting the relationship between reactor power and P1 and P2, and performs comprehensive processing on these signals through basic logic operations such as AND and NOT. When a single coolant pump trip signal and a reactor power > P2 signal coexist, an AND operation is performed to generate a "rapid reduction of core power trigger signal," which drives the rapid power reduction trigger unit 203 to operate. When a single coolant pump trip signal and a P1 < reactor power ≤ P2 signal coexist, or after rapid power reduction, a turbine load reduction command signal is generated and transmitted to the turbine load regulation unit 204. During the delay judgment phase, if the delay completion signal and the reactor power ≥ P1 signal are satisfied simultaneously, an "emergency reactor shutdown trigger signal" is generated, triggering an emergency reactor shutdown.

[0066] In some examples, the reactor power matching control system 200 also includes a parameter switching unit 208, which includes a turbine power target value switching switch and a turbine load reduction rate switching switch, respectively used to select a fourth predetermined value P after receiving a turbine load reduction command. targ The turbine power target value is set as the target value, and a third predetermined value r is selected as the target value for the turbine load reduction rate. Specifically, when the system generates a turbine load reduction command and transmits it to the parameter switching unit 207, the two switches are activated in tandem. The turbine power target value switching switch is responsible for explicitly setting the turbine power regulation target to a fourth predetermined value P. targ This ensures that the final power output of the turbine can achieve a stable match with the thermal power of the reactor at low power levels, alleviating the thermal pressure caused by the decrease in coolant flow from an energy balance perspective. The turbine load reduction rate switching switch locks the adjustment rate to a third predetermined value r, controlling the dynamic process of turbine power reduction. This ensures that the response speed is sufficient to meet the core safety requirements while avoiding equipment shock caused by excessively rapid rate reduction.

[0067] Figure 3 This diagram illustrates the reactor-machine matching control principle of a nuclear power plant. As shown, taking a nuclear power plant with four reactor coolant pumps 301-304 and two steam generators 305 and 306 configured in reactor pressure vessel 300 as an example, the diagram, along with a signal interaction schematic, explains how the system units achieve matching control. The specific details are as follows:

[0068] RCP Status Detection and Power Judgment: The RCP status detection unit monitors the 4 reactor coolant pumps 301 - 304 in real time. When a single reactor coolant pump trip is detected, a trigger signal is sent to the reactor power judgment unit; the reactor power judgment unit simultaneously collects the core power signal and judges its relationship with P1 and P2;

[0069] Logic Operation and Trigger for Power Reduction: The logic operation unit performs AND and NOT operations on the signal of a single reactor coolant pump trip and the core power signal (the comparison result with P1 and P2). If "core power > P2" and "single reactor coolant trip", then a "power reduction trigger signal" is output to the power reduction trigger unit, and at the same time, a "steam turbine load reduction command signal" is output;

[0070] If "P1 < core power ≤ P2" and "single reactor coolant trip", then directly output a "steam turbine load reduction command signal";

[0071] Steam Turbine Parameter Switching and Load Reduction: After receiving the "steam turbine load reduction command signal", the parameter switching unit selects P targ as the target power, and the steam turbine load reduction rate switching unit selects r as the load reduction rate; the steam turbine load regulation unit controls the steam turbine load reduction accordingly;

[0072] Delay and Reactor Trip Protection: The delay waiting unit waits for a delay time of the fifth predetermined value t targ after the steam turbine reduces its load at a load reduction rate of the third predetermined value r to the fourth predetermined value P delay ; the reactor trip trigger unit waits for a delay time of the fifth predetermined value t delay and then judges again whether the core power is < P1. If not, it triggers an emergency reactor trip.

[0073] Figure 4A system block diagram of a stacker power matching control device according to an embodiment of the present invention is shown. As shown, the stacker power matching control device 400 may include an internal communication bus 401, a processor 402, a read-only memory (ROM) 403, a random access memory (RAM) 404, and a communication port 405. When applied to a personal computer, the simulation device 400 may also include a hard disk 406. The internal communication bus 401 enables data communication between the components of the simulation device 400. The processor 402 can perform judgments and issue prompts. In some embodiments, the processor 402 may consist of one or more processors. The communication port 405 enables data communication between the stacker power matching control device 400 and external devices. In some embodiments, the stacker power matching control device 400 can send and receive information and data from a network through the communication port 405. The stacker power matching control device 400 may also include different types of program storage units and data storage units, such as hard disk 406, read-only memory (ROM) 403, and random access memory (RAM) 404, capable of storing various data files used for computer processing and / or communication, as well as possible program instructions executed by processor 402. Processor 402 executes these instructions to implement the main parts of the method. The results processed by processor 402 are transmitted to user equipment via communication port 405 and displayed on the user interface.

[0074] The aforementioned stacker power matching control method can be implemented as a computer program, stored in hard disk 406, and loaded into processor 402 for execution to implement the stacker power matching control method of this application.

[0075] The present invention also provides a computer-readable storage medium having a computer program stored thereon, wherein the computer program, when executed by a processor, implements the steps of any of the aforementioned stacker power matching control methods.

[0076] The specific implementation methods and technical effects of the stacker power matching control equipment and computer-readable storage medium can be found in the embodiments of the stacker power matching control method provided by the present invention, and will not be repeated here.

[0077] The present invention provides a stacker power matching control method, a stacker power matching control system, a stacker power matching control device, and a readable storage medium, the advantages of which are:

[0078] 1. Improve operational continuity and economy: By actively coordinating reactor power to match core thermal power, turbine power and coolant flow, the number of unplanned shutdowns can be significantly reduced, greatly improving the continuity and economy of nuclear power plant operation.

[0079] 2. Extend equipment life and reliability: Avoid transient conditions caused by reactor power mismatch after a single RCP trip, reduce thermal stress and mechanical shock to key equipment such as reactors and turbines, alleviate fatigue damage accumulation, extend the design service life of equipment, and improve the long-term reliability of the system.

[0080] 3. Ensure core safety redundancy: The redundant logic of "delayed judgment + emergency shutdown" ensures that if the power regulation strategy does not meet expectations, a shutdown can still be triggered in time, fundamentally ensuring the thermal safety of the core.

[0081] Those skilled in the art will further appreciate that the various illustrative logic blocks, modules, circuits, and algorithm steps described in conjunction with the embodiments disclosed herein can be implemented as electronic hardware, computer software, or a combination of both. To clearly illustrate this interchangeability between hardware and software, the various illustrative components, blocks, modules, circuits, and steps are described above in a generalized manner in terms of their functionality. Whether such functionality is implemented as hardware or software depends on the specific application and the design constraints imposed on the overall system. Those skilled in the art may implement the described functionality in different ways for each specific application, but such implementation decisions should not be construed as departing from the scope of the invention.

[0082] The various illustrative logic modules and circuits described in conjunction with the embodiments disclosed herein may be implemented or performed using a general-purpose processor, 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, or any combination thereof designed to perform the functions described herein. The general-purpose processor may be a microprocessor, but in alternatives, it may be any conventional processor, controller, microcontroller, or state machine. The processor may also be implemented as a combination of computing devices, such as a combination of a DSP and a microprocessor, multiple microprocessors, one or more microprocessors cooperating with a DSP core, or any other such configuration.

[0083] The steps of the methods or algorithms described in conjunction with the embodiments disclosed herein may be embodied directly in hardware, in a software module executed by a processor, or in a combination of both. The software module may reside in RAM memory, flash memory, ROM memory, EPROM memory, EEPROM memory, registers, hard disk, removable disk, CD-ROM, or any other form of storage medium known in the art. An exemplary storage medium is coupled to a processor such that the processor can read and write information to / from the storage medium. In an alternative, the storage medium may be integrated into the processor. The processor and storage medium may reside in an ASIC. The ASIC may reside in a user terminal. In an alternative, the processor and storage medium may reside as discrete components in the user terminal.

[0084] In one or more exemplary embodiments, the described functionality may be implemented in hardware, software, firmware, or any combination thereof. If implemented in software as a computer program product, the functionality may be stored or transmitted as one or more instructions or code on or through a computer-readable medium. A computer-readable medium includes both computer storage media and communication media, encompassing any medium that facilitates the transfer of a computer program from one location to another. A storage medium may be any available medium accessible to a computer. By way of example and not limitation, such a computer-readable medium may include RAM, ROM, EEPROM, CD-ROM or other optical disc storage, disk storage or other magnetic storage devices, or any other medium that can be used to carry or store desired program code in the form of instructions or data structures and is accessible to a computer. Any connection is also legitimately referred to as a computer-readable medium. For example, if the software is transmitted from a website, server, or other remote source using coaxial cable, fiber optic cable, twisted pair, digital subscriber line (DSL), or wireless technologies such as infrared, radio, and microwave, then the coaxial cable, fiber optic cable, twisted pair, DSL, or wireless technologies such as infrared, radio, and microwave are included in the definition of a medium. As used in this article, disk and disc include compact discs (CDs), laser discs, optical discs, digital multi-purpose discs (DVDs), floppy disks, and Blu-ray discs. Disks typically reproduce data magnetically, while discs reproduce data optically using lasers. Combinations of these should also be included within the scope of computer-readable media.

[0085] It will be apparent to those skilled in the art that various modifications and variations can be made to the exemplary embodiments described above without departing from the spirit and scope of the invention. Therefore, it is intended that this invention cover modifications and variations falling within the scope of the appended claims and their equivalents.

Claims

1. A power matching control method for a reactor, applied to a nuclear reactor, comprising the steps: S1, detecting the operating state of the coolant pump of the nuclear reactor, judging whether a single coolant pump trips. If not, proceeding to step S8; if so, executing step S2; S2, judging whether the reactor power is greater than a first predetermined value P1. If the reactor power ≤ P1, proceeding to step S8; if the reactor power > P1, executing step S3; S3, judging whether the reactor power is greater than a second predetermined value P2, where P2 > P1. If the reactor power > P2, entering step S4; if P1 < reactor power ≤ P2, executing step S5; S4, reducing the core power at a predetermined rate; S5, control the steam turbine to reduce the turbine power from the current value to the fourth predetermined value P at a load reduction rate of the third predetermined value r. targ And wait for the fifth predetermined value t delay The delay time; S6, judging whether the reactor power is less than the first predetermined value P1. If the reactor power < P1, proceeding to step S8; if the reactor power ≥ P1, proceeding to step S7; S7, triggering an emergency reactor shutdown; S8, ending.

2. The reactor power matching control method as described in claim 1, characterized in that, The setting range of the first predetermined value P1 is 40% - 60% of the maximum reactor power.

3. The reactor power matching control method as described in claim 1, characterized in that, The setting range of the second predetermined value P2 is 60% - 80% of the maximum reactor power.

4. The reactor power matching control method as described in claim 1, characterized in that, The third predetermined value r is set within the range of 50% / min to 200% / min of the turbine's maximum power; the fourth predetermined value P targ The fourth predetermined value P is to match the thermal power of the reactor at low power levels. targ The setting range is 40% to 60% of the turbine's maximum power.

5. The reactor power matching control method as described in claim 1, characterized in that, The fifth predetermined value t delay The fifth predetermined value t is used to provide time margin for turbine load reduction and core power response. delay The setting range is 5s to 15s.

6. The reactor power matching control method as described in claim 1, characterized in that, In step S4, the core power is reduced at a predetermined rate by means of boron injection or control rod insertion.

7. A power matching control system for a reactor, comprising: An RCP state detection unit for detecting the operating state of the coolant pump of the nuclear reactor and judging whether a single coolant pump trips; A reactor power judgment unit for judging the magnitude relationship between the reactor power and the first predetermined value P1 and the second predetermined value P2; A power reduction trigger unit for triggering the reduction of the core power at a predetermined rate when the reactor power > P2 and a single coolant pump trips; The turbine load regulation unit is used to control the turbine to reduce the load at a third predetermined value r to a fourth predetermined value P after triggering a reduction in core power at a predetermined rate when P1 < reactor power ≤ P2. targ ; A delay waiting unit is used when the steam turbine reduces its load at a third predetermined value r to a fourth predetermined value P. targ Then, wait for the fifth predetermined value t. delay The delay time; The stop trigger unit is used to wait for the fifth predetermined value t. delay Then, it is determined whether the reactor power is less than P1, and an emergency reactor shutdown is triggered when the reactor power is ≥ P1.

8. The stacker power matching control system as described in claim 7, characterized in that, It further includes a logic operation unit, which is used to perform AND and NOT logic operations on the reactor power state signal and the single coolant pump trip signal obtained by the RCP state detection unit to generate a trigger signal for reducing the core power at a predetermined rate, a steam turbine load reduction command signal or a reactor emergency shutdown trigger signal.

9. The stacker power matching control system as described in claim 8, characterized in that, It also includes a parameter switching unit, which comprises a turbine power target value switching switch and a turbine load reduction rate switching switch, respectively used to select a fourth predetermined value P after receiving a turbine load reduction command. targ The third predetermined value r is selected as the target value for the turbine power reduction rate.

10. A stacker power matching 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 power matching control method for a reactor as described in any one of claims 1 - 5 are implemented.

11. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by the processor, the steps of the power matching control method for a reactor as described in any one of claims 1 - 5 are implemented.

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