CN115586762A

CN115586762A - Method, device, equipment and medium for overhauling equipment fault of nuclear power plant

Info

Publication number: CN115586762A
Application number: CN202211370480.1A
Authority: CN
Inventors: 魏盛辉; 吴爱民; 张桥; 杨晓冰; 张瑜; 张伟斌
Original assignee: Shandong Nuclear Power Co Ltd
Current assignee: Shandong Nuclear Power Co Ltd
Priority date: 2022-11-03
Filing date: 2022-11-03
Publication date: 2023-01-10

Abstract

The invention discloses a method, a device, equipment and a medium for overhauling equipment faults of a nuclear power plant. The method comprises the following steps: when a fault maintenance request of nuclear power plant equipment is detected, controlling a nuclear reactor to enter a thermal shutdown state, and controlling a main pump to be in a shutdown state; maintaining the nuclear reactor in a thermal shutdown state based on the passive natural circulation of a loop system, and executing maintenance work; and after the maintenance work is finished, controlling the main pump to be switched from the shutdown state to the start state, and controlling the nuclear reactor to be switched from the hot shutdown state to the running state. According to the technical scheme, after the nuclear power plant is shut down, the nuclear reactor is maintained in a hot shutdown state by utilizing the passive natural circulation capacity of the primary loop system, the temporary shutdown time during equipment fault maintenance of the nuclear power plant can be shortened, and the power generation benefit of a nuclear power unit can be improved.

Description

Method, device, equipment and medium for overhauling equipment fault of nuclear power plant

Technical Field

The invention relates to the technical field of nuclear power, in particular to a method, a device, equipment and a medium for overhauling equipment faults of a nuclear power plant.

Background

When the nuclear power plant is continuously operated, an operation transient state such as equipment failure may occur, thereby causing operation deviation or possibly deviating from the specification. In response to this situation, the nuclear power plant is typically shut down temporarily and subjected to equipment maintenance and troubleshooting to prevent the initiation of more severe accident conditions. Wherein, most of the maintenance work only needs a short time, so the hot shutdown state of the unit system can be maintained, and a great amount of shutdown time can be saved.

At present, the existing method for maintaining the hot shutdown state generally adopts a main pump of a loop to rotate to generate heat and generate forced convection to maintain the temperature and the pressure of the system. However, in the prior art, the continuous operation of the main pump consumes a large amount of energy, thereby seriously affecting the economy of the power plant; in addition, when the maintenance work of the main pump is required during shutdown, the main pump cannot operate, and at the moment, the reactor needs to be retreated to a cold shutdown state, so that the power generation benefit of the unit can be seriously influenced.

Disclosure of Invention

The invention provides a nuclear power plant equipment fault overhauling method, device, equipment and medium, which can shorten the temporary shutdown time in the nuclear power plant equipment fault overhauling process and improve the power generation benefit of a nuclear power unit.

According to an aspect of the present invention, there is provided a method for repairing a fault of a nuclear power plant, including:

when a fault maintenance request of nuclear power plant equipment is detected, controlling a nuclear reactor to enter a thermal shutdown state, and controlling a main pump to be in a shutdown state;

based on the passive natural circulation of a loop system, maintaining the nuclear reactor in a hot shutdown state, and executing maintenance work;

and after the maintenance work is finished, controlling the main pump to be switched from the shutdown state to the start state, and controlling the nuclear reactor to be switched from the hot shutdown state to the operating state.

According to another aspect of the present invention, there is provided a nuclear power plant equipment fault repairing apparatus including:

the first state control module is used for controlling the nuclear reactor to enter a thermal shutdown state and controlling a main pump to be in a shutdown state when a fault maintenance request of the nuclear power plant equipment is detected;

the system comprises a thermal shutdown state maintaining module, a control module and a maintenance module, wherein the thermal shutdown state maintaining module is used for maintaining the nuclear reactor in a thermal shutdown state and executing maintenance work based on the passive natural circulation of a loop system;

and the second state control module is used for controlling the main pump to be switched from the shutdown state to the start state and controlling the nuclear reactor to be switched from the hot shutdown state to the operating state after the maintenance work is finished.

According to another aspect of the present invention, there is provided an electronic apparatus including:

at least one processor; and

a memory communicatively coupled to the at least one processor; wherein, the first and the second end of the pipe are connected with each other,

the memory stores a computer program executable by the at least one processor, the computer program being executable by the at least one processor to enable the at least one processor to perform a method of troubleshooting a plant equipment failure as described in any of the embodiments of the invention.

According to another aspect of the invention, a computer-readable storage medium is provided, storing computer instructions for causing a processor to perform a method for troubleshooting a plant equipment fault according to any one of the embodiments of the invention when the computer instructions are executed.

According to the technical scheme of the embodiment of the invention, when a fault maintenance request of nuclear power plant equipment is detected, a nuclear reactor is controlled to enter a thermal shutdown state, and a main pump is controlled to be in a shutdown state; then, based on the passive natural circulation of a loop system, maintaining the nuclear reactor in a hot shutdown state, and executing maintenance work; after the maintenance work is finished, controlling the main pump to be switched from the shutdown state to the start state, and controlling the nuclear reactor to be switched from the hot shutdown state to the running state; after the nuclear power plant is shut down, the passive natural circulation capacity of the primary loop system is utilized to maintain the nuclear reactor in a hot shut-down state, so that the temporary shut-down time during the fault maintenance of the nuclear power plant equipment can be shortened, and the power generation benefit of a nuclear power unit can be improved.

It should be understood that the statements in this section do not necessarily identify key or critical features of the embodiments of the present invention, nor do they necessarily limit the scope of the invention. Other features of the present invention will become apparent from the following description.

Drawings

In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings required to be used in the description of the embodiments are briefly introduced below, and it is obvious that the drawings in the description below are only some embodiments of the present invention, and it is obvious for those skilled in the art that other drawings can be obtained according to the drawings without creative efforts.

FIG. 1A is a flow chart of a method for troubleshooting a nuclear power plant equipment fault according to an embodiment of the invention;

FIG. 1B is a schematic flow chart of a method for troubleshooting a nuclear power plant equipment fault according to an embodiment of the invention;

FIG. 2 is a schematic structural diagram of a nuclear power plant equipment fault maintenance device according to a second embodiment of the present invention;

fig. 3 is a schematic structural diagram of an electronic device for implementing a nuclear power plant equipment fault repairing method according to an embodiment of the present invention.

Detailed Description

In order to make the technical solutions of the present invention better understood, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.

It should be noted that the terms "first," "second," "target," and the like in the description and claims of the present invention and in the above-described drawings are used for distinguishing between similar elements and not necessarily for describing a particular sequential or chronological order. It is to be understood that the data so used is interchangeable under appropriate circumstances such that the embodiments of the invention described herein are capable of operation in sequences other than those illustrated or described herein. Furthermore, the terms "comprises," "comprising," and "having," and any variations thereof, are intended to cover a non-exclusive inclusion, such that a process, method, system, article, or apparatus that comprises a list of steps or elements is not necessarily limited to those steps or elements expressly listed, but may include other steps or elements not expressly listed or inherent to such process, method, article, or apparatus.

Example one

Fig. 1A is a flowchart of a method for repairing a nuclear power plant equipment fault according to an embodiment of the present invention, where the embodiment is applicable to a situation where a nuclear power plant equipment fault occurs and a temporary shutdown is required for equipment fault repair, and the method may be performed by a nuclear power plant equipment fault repairing device, where the nuclear power plant equipment fault repairing device may be implemented in a form of hardware and/or software, and the nuclear power plant equipment fault repairing device may be configured in an electronic device, and typically, the electronic device may be a computer device or a server. As shown in fig. 1A, the method includes:

s110, when a fault maintenance request of the nuclear power plant equipment is detected, controlling the nuclear reactor to enter a thermal shutdown state, and controlling a main pump to be in a shutdown state.

The fault maintenance request of the nuclear power plant equipment can be input by nuclear power plant workers when the nuclear power plant workers observe that the equipment operates abnormally, and can also be automatically generated by a monitoring system when the equipment parameter abnormity is detected. Optionally, the fault repair request of the nuclear power plant equipment may include contents such as an abnormal part and an abnormal index. When a fault maintenance request of the nuclear power plant equipment is detected, the condition that the nuclear reactor needs to be temporarily shut down currently is indicated, so that the nuclear power plant equipment is maintained and treated with faults.

Specifically, when a fault repair request of the nuclear power plant equipment is received, the power of the nuclear reactor can be gradually reduced to control the nuclear reactor to enter a thermal shutdown state, and the main pump can be controlled to stop running to enter a shutdown state. The main pump can be a primary loop system main pump and is used for pumping hot water into the steam generator so as to transfer heat energy to cooling water in the secondary loop system through the steam generator. The hot shutdown state can be the operating temperature and pressure when the coolant system maintains the hot zero power load, and the two-loop system is in a hot standby state and can be in a reactor state with load operation at any time.

In an optional implementation manner of this embodiment, the controlling the nuclear reactor to enter the thermal shutdown state may include:

and controlling the nuclear reactor to insert a control rod downwards until the control rod is detected to be completely inserted into the bottom of the nuclear reactor, and determining that the nuclear reactor enters a thermal shutdown state.

Specifically, the control rod can be controlled to be inserted under the nuclear reactor so as to gradually reduce the unit power; and after the control rods are completely inserted into the bottom of the nuclear reactor, determining that the nuclear reactor enters a thermal shutdown state until the detected unit power reaches the power in the thermal shutdown state.

And S120, maintaining the nuclear reactor in a thermal shutdown state based on the passive natural circulation of a loop system, and executing maintenance work.

It should be noted that the reactor core may generate huge heat energy due to fission of nuclear fuel, water pumped into the core by the main pump may be heated into high temperature and high pressure water, the high temperature and high pressure water may flow through the heat transfer U-shaped tube in the steam generator, may transfer heat energy to the cooling water of the two-circuit system outside the U-shaped tube through the tube wall, and may be returned to the core by the main pump for reheating after releasing heat energy. Therefore, the loop system can be a closed loop in which water in the nuclear reactor is continuously circulated.

In this embodiment, after the nuclear reactor enters the thermal shutdown state, the passive natural circulation capability of the primary loop system may be utilized to transfer heat in the primary loop system to the steam generator and maintain the state of the primary loop system to maintain the nuclear reactor in the thermal shutdown state. The passive natural circulation capability may be a capability of driving a coolant (e.g., water) to flow by using a driving force generated by the density difference. In one particular example, in a primary loop system, coolant is heated at the core, and for some coolant, the density will decrease due to expansion and contraction, while other coolant locations will be denser due to unheated coolant. At this time, a natural circulation driving force is generated by the density difference, and coolant at the core flows into the steam generator to transfer heat to the steam generator and then to the two-circuit system coolant to maintain the hot standby state of the two-circuit system.

Then, when the loop system of the unit maintains the thermal shutdown state, the fault part can be automatically overhauled according to the fault overhaul request of the nuclear power plant equipment; or, the maintenance task may be generated and sent to a preset maintenance person, so that the maintenance person performs maintenance work.

S130, after the maintenance work is finished, controlling the main pump to be switched from a shutdown state to a startup state, and controlling the nuclear reactor to be switched from a hot shutdown state to an operating state.

Specifically, when the automatic maintenance is detected to be completed or a maintenance completion message fed back by a maintenance worker is received, it is determined that the maintenance work is completed. At this time, the main pump is controlled to start to establish a forced flow of the primary circuit system to switch from the off state to the on state. And simultaneously, lifting the control rod to gradually increase the unit power until the unit power reaches the set power in the operating state, and determining that the nuclear reactor is switched from the thermal shutdown state to the operating state.

According to the technical scheme of the embodiment of the invention, when a fault maintenance request of nuclear power plant equipment is detected, a nuclear reactor is controlled to enter a thermal shutdown state, and a main pump is controlled to be in a shutdown state; then, based on the passive natural circulation of a loop system, maintaining the nuclear reactor in a hot shutdown state, and executing maintenance work; after the maintenance work is finished, controlling the main pump to be switched from the shutdown state to the start state, and controlling the nuclear reactor to be switched from the hot shutdown state to the running state; after the nuclear power plant is shut down, the passive natural circulation capacity of a loop system is utilized to maintain the nuclear reactor in a hot shutdown state, so that the temporary shutdown time during the fault maintenance of the nuclear power plant equipment can be shortened, and the power generation benefit of a nuclear power unit can be improved.

In another optional implementation manner of this embodiment, the maintaining the nuclear reactor in the thermal shutdown state based on the passive natural circulation of the primary loop system may include:

the reactor core decay heat is used as input heat of a primary system, and the input heat is transferred to heat transfer tubes of a steam generator based on passive natural circulation of the primary system so as to maintain the nuclear reactor in a hot shutdown state.

The core decay heat may be heat released by decay of a large amount of radioactive substances generated by delayed fission radiation after the nuclear reactor is shut down.

Specifically, after the nuclear reactor reaches a thermal shutdown state and a primary loop system main pump stops operating, core decay heat can be supplied as a heat source of a loop system of the unit, and input heat can be transferred to heat transfer pipes (for example, heat transfer U-shaped pipes) of a steam generator through the passive natural circulation capacity of the loop system, so that the thermal shutdown state of the nuclear reactor is maintained.

In the embodiment, a main pump is not used, and the unit is maintained in a hot shutdown state only by means of the passive natural circulation capacity of a loop system, so that the running energy consumption of the main pump can be obviously reduced; meanwhile, the execution process of the unit from hot to cold and from cold to hot can be avoided, and the reactor shutdown time can be shortened, so that the power generation benefit of the unit can be improved, and the waste of resources and the discharge of waste water can be reduced.

In another optional implementation manner of this embodiment, after transferring the input heat to the heat transfer pipe of the steam generator based on the passive natural circulation of the loop system, the method may further include: and maintaining the state of the loop system unchanged.

The state of the loop system may include temperature, pressure, boron concentration, hydrogen concentration, ph value, and the like. In this embodiment, the system state of the primary loop system can be maintained while the input heat is transferred based on the passive natural circulation of the primary loop system.

The advantage of above-mentioned setting lies in, after the nuclear reactor restarts, need not to adjust the system state of a loop system, can promote the restart efficiency of nuclear reactor.

Maintaining the state of the loop system unchanged may include:

and maintaining the corresponding temperature value and pressure value of the loop system unchanged by adjusting the opening of a steam bypass valve of the steam generator.

In a specific example, the steam generator may be used as a heat sink, and the opening of the steam bypass valve is adjusted to maintain the corresponding temperature and pressure values of the primary circuit system constant.

In another optional implementation manner of this embodiment, after maintaining the state of the loop system unchanged, the method may further include:

establishing a long cycle between the condensed water and the main feed water by maintaining the deaerator in a hot state;

based on the long circulation between the condensed water and the main water supply, the water quality of the main water supply is controlled to meet the water quality requirement corresponding to the steam generator by adding chemicals into the condensed water.

The deaerator can be used for removing non-condensation gases such as oxygen, carbon dioxide and the like in condensed water. The condensed water can be water condensed by steam after releasing heat; the main water supply may be a water supply of the steam generator. In this embodiment, by maintaining the deaerator in a hot state, a long cycle between the condensed water and the main feed water can be maintained, i.e., the condensed water can reach the steam generator as the main feed water after being treated, and the steam converted from the main feed water in the steam generator releases heat and is converted into the condensed water.

Secondly, in order to ensure that the quality of the main feed water can meet the corresponding water quality requirement of the steam generator, the quality of the main feed water can be adjusted by adding chemicals (such as ammonia, hydrazine and the like) to the condensed water based on long circulation between the condensed water and the main feed water, so that the main feed water meets the water feeding condition of the steam generator.

In another alternative embodiment of this embodiment, controlling the nuclear reactor to switch from the thermal shutdown state to the operating state may include:

and controlling the nuclear reactor to lift the control rod to a preset critical value, and lifting the unit power of the nuclear reactor until the unit power is detected to be equal to the preset power, and determining that the nuclear reactor is switched from a thermal shutdown state to an operating state.

The preset critical value can be the critical height of the control rod. The preset power may be a normal operating power of the nuclear reactor, for example, a maximum unit power.

In a specific example, after the maintenance work is completed, the control rod may be gradually raised to a preset critical value according to a preset unit adjustment value, and the unit power of the nuclear reactor is raised until a predetermined power, that is, a preset power, is reached, and it is determined that the nuclear reactor is switched from a thermal shutdown state to an operating state.

In a specific embodiment of this embodiment, a flow of a method for repairing a fault of a nuclear power plant equipment may be as shown in fig. 1B. First, control rods are inserted to reduce reactor power until the reactor is shut down and the main pump operation is stopped. Then, the thermal shutdown state of the nuclear reactor is passively maintained, and the maintenance work is performed. Specifically, the reactor core decay heat is supplied as a heat source of a primary circuit system, and the temperature and the pressure of the primary circuit system are maintained by adjusting the opening degree of a bypass valve; meanwhile, the boron concentration, the hydrogen concentration and the PH (potential hydrogen) value of the loop system can be maintained, and the deaerator is kept in a hot state to maintain long circulation between condensed water and main water.

And finally, after the maintenance work is finished, controlling the nuclear reactor to start. Specifically, the main pump is activated to establish a forced flow of coolant and lift the control rods to bring the nuclear reactor to criticality; and secondly, increasing the power of the unit to full power.

Example two

Fig. 2 is a schematic structural diagram of a nuclear power plant equipment fault maintenance device according to a second embodiment of the present invention. As shown in fig. 2, the apparatus may include: a first state control module 210, a hot trip state maintenance module 220, and a second state control module 230; wherein the content of the first and second substances,

the first state control module 210 is configured to, when a fault repair request of the nuclear power plant equipment is detected, control the nuclear reactor to enter a thermal shutdown state, and control a main pump to be in a shutdown state;

a hot shutdown state maintaining module 220, configured to maintain the nuclear reactor in a hot shutdown state and perform maintenance work based on passive natural circulation of a loop system;

and the second state control module 230 is configured to control the main pump to switch from a shutdown state to a startup state and control the nuclear reactor to switch from a hot shutdown state to an operating state after the maintenance operation is completed.

Optionally, the first state control module 210 is specifically configured to control the nuclear reactor to insert the control rod downward until it is detected that the control rod is completely inserted into the bottom of the nuclear reactor, and determine that the nuclear reactor enters a thermal shutdown state.

Optionally, the hot shutdown maintenance module 220 is specifically configured to use the core decay heat as input heat of the primary system, and transfer the input heat to heat transfer tubes of the steam generator based on passive natural circulation of the primary system, so as to maintain the nuclear reactor in a hot shutdown state.

Optionally, the hot trip status maintenance module 220 includes:

and the system state maintaining unit is used for maintaining the state of the loop system unchanged.

Optionally, the system state maintaining unit is specifically configured to maintain a temperature value and a pressure value corresponding to the loop system unchanged by adjusting an opening of a steam bypass valve of the steam generator.

Optionally, the hot trip status maintaining module 220 further includes:

a long cycle establishing unit for establishing a long cycle between the condensed water and the principal feedwater by maintaining the deaerator in a hot state;

and the water quality control unit is used for controlling the water quality of the main water supply to meet the corresponding water quality requirement of the steam generator by adding chemicals to the condensed water based on long circulation between the condensed water and the main water supply.

Optionally, the second state control module 230 is specifically configured to control the nuclear reactor to lift the control rod to a preset threshold, and lift the unit power of the nuclear reactor until it is detected that the unit power is equal to the preset power, and it is determined that the nuclear reactor is switched from a shutdown state to an operating state.

The nuclear power plant equipment fault overhauling device provided by the embodiment of the invention can execute the nuclear power plant equipment fault overhauling method provided by any embodiment of the invention, and has the corresponding functional modules and beneficial effects of the execution method.

EXAMPLE III

FIG. 3 shows a schematic block diagram of an electronic device 30 that may be used to implement an embodiment of the invention. Electronic devices are intended to represent various forms of digital computers, such as laptops, desktops, workstations, personal digital assistants, servers, blade servers, mainframes, and other appropriate computers. The electronic device may also represent various forms of mobile devices, such as personal digital assistants, cellular phones, smart phones, wearable devices (e.g., helmets, glasses, watches, etc.), and other similar computing devices. The components shown herein, their connections and relationships, and their functions, are meant to be exemplary only, and are not meant to limit implementations of the inventions described and/or claimed herein.

As shown in fig. 3, the electronic device 30 includes at least one processor 31, and a memory communicatively connected to the at least one processor 31, such as a Read Only Memory (ROM) 32, a Random Access Memory (RAM) 33, and the like, wherein the memory stores a computer program executable by the at least one processor, and the processor 31 may perform various suitable actions and processes according to the computer program stored in the Read Only Memory (ROM) 32 or the computer program loaded from the storage unit 38 into the Random Access Memory (RAM) 33. In the RAM 33, various programs and data necessary for the operation of the electronic apparatus 30 can also be stored. The processor 31, the ROM 32, and the RAM 33 are connected to each other through a bus 34. An input/output (I/O) interface 35 is also connected to bus 34.

A plurality of components in the electronic device 30 are connected to the I/O interface 35, including: an input unit 36 such as a keyboard, a mouse, etc.; an output unit 37 such as various types of displays, speakers, and the like; a storage unit 38 such as a magnetic disk, an optical disk, or the like; and a communication unit 39 such as a network card, modem, wireless communication transceiver, etc. The communication unit 39 allows the electronic device 30 to exchange information/data with other devices via a computer network such as the internet and/or various telecommunication networks.

The processor 31 may be a variety of general and/or special purpose processing components having processing and computing capabilities. Some examples of processor 31 include, but are not limited to, a Central Processing Unit (CPU), a Graphics Processing Unit (GPU), various specialized Artificial Intelligence (AI) computing chips, various processors running machine learning model algorithms, a Digital Signal Processor (DSP), and any suitable processor, controller, microcontroller, or the like. The processor 31 performs the various methods and processes described above, such as a method of troubleshooting a nuclear power plant equipment failure.

In some embodiments, the method of troubleshooting a nuclear power plant equipment fault may be implemented as a computer program tangibly embodied in a computer-readable storage medium, such as storage unit 38. In some embodiments, part or all of the computer program may be loaded and/or installed onto the electronic device 30 via the ROM 32 and/or the communication unit 39. When the computer program is loaded into RAM 33 and executed by processor 31, one or more steps of the nuclear power plant equipment fault troubleshooting method described above may be performed. Alternatively, in other embodiments, the processor 31 may be configured to perform a method of troubleshooting a plant equipment fault by any other suitable means (e.g., by way of firmware).

Various implementations of the systems and techniques described here above may be implemented in digital electronic circuitry, integrated circuitry, field Programmable Gate Arrays (FPGAs), application Specific Integrated Circuits (ASICs), application Specific Standard Products (ASSPs), system on a chip (SOCs), load programmable logic devices (CPLDs), computer hardware, firmware, software, and/or combinations thereof. These various embodiments may include: implemented in one or more computer programs that are executable and/or interpretable on a programmable system including at least one programmable processor, which may be special or general purpose, receiving data and instructions from, and transmitting data and instructions to, a storage system, at least one input device, and at least one output device.

A computer program for implementing the methods of the present invention may be written in any combination of one or more programming languages. These computer programs may be provided to a processor of a general purpose computer, special purpose computer, or other programmable data processing apparatus, such that the computer programs, when executed by the processor, cause the functions/acts specified in the flowchart and/or block diagram block or blocks to be performed. A computer program can execute entirely on a machine, partly on a machine, as a stand-alone software package partly on a machine and partly on a remote machine or entirely on a remote machine or server.

In the context of the present invention, a computer-readable storage medium may be a tangible medium that can contain, or store a computer program for use by or in connection with an instruction execution system, apparatus, or device. A computer readable storage medium may include, but is not limited to, an electronic, magnetic, optical, electromagnetic, infrared, or semiconductor system, apparatus, or device, or any suitable combination of the foregoing. Alternatively, the computer readable storage medium may be a machine readable signal medium. More specific examples of a machine-readable storage medium would include an electrical connection based on one or more wires, a portable computer diskette, a hard disk, a Random Access Memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber, a compact disc read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the foregoing.

To provide for interaction with a user, the systems and techniques described here can be implemented on an electronic device having: a display device (e.g., a CRT (cathode ray tube) or LCD (liquid crystal display) monitor) for displaying information to a user; and a keyboard and a pointing device (e.g., a mouse or a trackball) by which a user can provide input to the electronic device. Other kinds of devices may also be used to provide for interaction with a user; for example, feedback provided to the user can be any form of sensory feedback (e.g., visual feedback, auditory feedback, or tactile feedback); and input from the user may be received in any form, including acoustic, speech, or tactile input.

The systems and techniques described here can be implemented in a computing system that includes a back-end component (e.g., as a data server), or that includes a middleware component (e.g., an application server), or that includes a front-end component (e.g., a user computer having a graphical user interface or a web browser through which a user can interact with an implementation of the systems and techniques described here), or any combination of such back-end, middleware, or front-end components. The components of the system can be interconnected by any form or medium of digital data communication (e.g., a communication network). Examples of communication networks include: local Area Networks (LANs), wide Area Networks (WANs), blockchain networks, and the Internet.

The computing system may include clients and servers. A client and server are generally remote from each other and typically interact through a communication network. The relationship of client and server arises by virtue of computer programs running on the respective computers and having a client-server relationship to each other. The server can be a cloud server, also called a cloud computing server or a cloud host, and is a host product in a cloud computing service system, so that the defects of high management difficulty and weak service expansibility in the traditional physical host and VPS service are overcome.

It should be understood that various forms of the flows shown above may be used, with steps reordered, added, or deleted. For example, the steps described in the present invention may be executed in parallel, sequentially, or in different orders, and are not limited herein as long as the desired results of the technical solution of the present invention can be achieved.

The above-described embodiments should not be construed as limiting the scope of the invention. It should be understood by those skilled in the art that various modifications, combinations, sub-combinations and substitutions may be made in accordance with design requirements and other factors. Any modification, equivalent replacement, and improvement made within the spirit and principle of the present invention should be included in the protection scope of the present invention.

Claims

1. A nuclear power plant equipment fault overhauling method is characterized by comprising the following steps:

maintaining the nuclear reactor in a hot shutdown state based on the passive natural circulation of a loop system, and executing maintenance work;

2. The method of claim 1, wherein controlling the nuclear reactor to enter a thermal shutdown state comprises:

3. The method of claim 1, wherein maintaining the nuclear reactor in a thermal shutdown state based on a passive natural circulation of a primary loop system comprises:

4. The method of claim 3, further comprising, after transferring the input heat to heat transfer tubes of a steam generator based on a passive natural circulation of a loop system:

and maintaining the state of the loop system unchanged.

5. The method of claim 4, wherein maintaining the state of the loop system unchanged comprises:

6. The method of claim 4, further comprising, after maintaining the state of the loop system unchanged:

based on the long circulation between the condensed water and the main water supply, the water quality of the main water supply is controlled to meet the water quality requirement corresponding to the steam generator by adding chemicals to the condensed water.

7. The method of claim 1, wherein controlling the nuclear reactor to switch from a thermal shutdown state to an operating state comprises:

8. A nuclear power plant equipment fault's maintenance device which characterized in that includes:

and the second state control module is used for controlling the main pump to be switched from a shutdown state to an activation state and controlling the nuclear reactor to be switched from a hot shutdown state to an operation state after the maintenance work is finished.

9. An electronic device, characterized in that the electronic device comprises:

at least one processor; and

a memory communicatively coupled to the at least one processor; wherein the content of the first and second substances,

the memory stores a computer program executable by the at least one processor to enable the at least one processor to perform the method of troubleshooting a nuclear power plant equipment fault of any one of claims 1-7.

10. A computer-readable storage medium, characterized in that it stores computer instructions for causing a processor to carry out a method of troubleshooting a nuclear power plant equipment fault as recited in any one of claims 1-7 when executed.