CN115312226A - Nuclear power equipment fault load shedding control method and device and storage medium - Google Patents

Abstract

The utility model provides a nuclear power plant fault load shedding control method, a device and a storage medium, which relate to the technical field of nuclear power plant control, and the method comprises the following steps: under the condition that nuclear power plant equipment fails, acquiring fault information, and determining a target fault type according to the fault information, wherein the target fault type comprises any one of the following items: the method comprises the following steps of partial reactor shutdown, all reactor shutdown, partial water feed pump shutdown, all water feed pumps shutdown, steam turbine fault shutdown and external power grid fault tripping, and executes a control process corresponding to a target fault type to carry out load reduction control on the nuclear power plant, and can carry out load reduction control on the nuclear power plant under the condition that equipment of the nuclear power plant fails, so that safe and efficient operation of a nuclear power unit can be guaranteed.

Description

Nuclear power equipment fault load shedding control method and device and storage medium

Technical Field

The disclosure relates to the technical field of nuclear power plant control, in particular to a nuclear power equipment fault load shedding control method, a nuclear power equipment fault load shedding control device and a storage medium.

Background

The high-temperature gas cooled reactor engineering adopts a working mode of two reactors with one reactor and adopts a running mode of 'machine-to-reactor'. When partial equipment of the reactor breaks down, whether the equipment can be normally put into operation or not directly influences the safe and economic operation of the reactor unit, and the method is an important index for checking the control performance of the unit. Therefore, the RB control function of the high-temperature gas cooled reactor is analyzed and researched, the safe and reliable operation of the unit is guaranteed, and the method has very important significance for popularization and optimization of the high-temperature gas cooled reactor.

Disclosure of Invention

The present disclosure provides a nuclear power plant fault load shedding control method, apparatus and storage medium, which aim to solve at least one of the technical problems in the related art to a certain extent.

An embodiment of the first aspect of the disclosure provides a nuclear power equipment fault load shedding control method, which includes: acquiring fault information under the condition that the nuclear power plant equipment fails; determining a target fault type according to the fault information, wherein the target fault type comprises any one of the following items: partial reactor shutdown, all reactor shutdown, partial water supply pump shutdown, all water supply pump shutdown, steam turbine fault shutdown and external power grid fault trip; and executing a control process corresponding to the target fault type to carry out load reduction control on the nuclear power plant.

An embodiment of a second aspect of the present disclosure provides a nuclear power plant fault load reduction control device, including: the acquisition module is used for acquiring fault information under the condition that the nuclear power plant equipment fails; a determining module, configured to determine a target fault type according to the fault information, where the target fault type includes any one of: partial reactor shutdown, all reactor shutdown, partial water supply pump shutdown, all water supply pump shutdown, steam turbine fault shutdown and external power grid fault trip; and the control module is used for executing a control process corresponding to the target fault type so as to carry out load reduction control on the nuclear power plant.

An embodiment of a third aspect of the present disclosure provides an electronic device, including: at least one processor; and a memory communicatively coupled to the at least one processor; wherein the memory stores instructions executable by the at least one processor to enable the at least one processor to perform the nuclear power plant fault unloading control method of the disclosed embodiments.

A fourth aspect of the present disclosure provides a non-transitory computer-readable storage medium storing computer instructions for causing a computer to execute a nuclear power plant fault load reduction control method disclosed in an embodiment of the present disclosure.

In this embodiment, fault information of the nuclear power plant equipment is acquired, and a target fault type is determined according to the fault information, where the target fault type includes any one of: the method comprises the following steps of partial reactor shutdown, all reactor shutdown, partial water feed pump shutdown, all water feed pumps shutdown, steam turbine fault shutdown and external power grid fault tripping, and executes a control process corresponding to a target fault type to carry out load reduction control on the nuclear power plant, and can carry out load reduction control on the nuclear power plant under the condition that equipment of the nuclear power plant fails, so that safe and efficient operation of a nuclear power unit can be guaranteed.

Additional aspects and advantages of the disclosure will be set forth in part in the description which follows and, in part, will be obvious from the description, or may be learned by practice of the disclosure.

Drawings

The foregoing and/or additional aspects and advantages of the present disclosure will become apparent and readily appreciated from the following description of the embodiments, taken in conjunction with the accompanying drawings of which:

fig. 1 is a schematic flow chart of a nuclear power plant fault load reduction control method according to an embodiment of the present disclosure;

FIG. 2 is a schematic diagram of a nuclear power plant fault unloading control apparatus provided in accordance with another embodiment of the present disclosure;

FIG. 3 illustrates a block diagram of an exemplary electronic device suitable for use in implementing embodiments of the present disclosure.

Detailed Description

Reference will now be made in detail to the embodiments of the present disclosure, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the drawings are exemplary only for the purpose of illustrating the present disclosure and should not be construed as limiting the same. On the contrary, the embodiments of the disclosure include all changes, modifications and equivalents coming within the spirit and terms of the claims appended hereto.

It should be noted that the main execution body of the nuclear power equipment fault load shedding control method of this embodiment may be a nuclear power equipment fault load shedding control device, which may be implemented in a software and/or hardware manner, and may be configured in an electronic device, and the electronic device may include, but is not limited to, a terminal, a server, and the like.

Fig. 1 is a schematic flow chart of a nuclear power plant fault load reduction control method according to an embodiment of the present disclosure, and as shown in fig. 1, the method includes:

s101: and acquiring fault information under the condition that the nuclear power plant equipment has faults.

The nuclear power plant equipment may include, for example, a reactor feedwater pump, a steam turbine, an external grid, and any other possible equipment, without limitation.

In practical application, the embodiment can monitor the operation state of equipment in the nuclear power plant in real time, and when any equipment is monitored to have a fault, fault information is obtained, and the fault information may be in the form of a signal, for example.

In some embodiments, the fault information (fault signal) of the equipment may be obtained by different systems, such as a digital electro-hydraulic control system (DEH), a nuclear power plant unit DCS control system, and the like, that is, the nuclear power equipment fault load reduction control method of this embodiment may be executed by different systems, for example.

For example, when a reactor and a feed pump have faults, the unit DCS control system can send fault information to the DEH system, and the DEH system performs load shedding control; for example, when the steam turbine and the external power grid fail, the DEH system may transmit failure information to the plant DCS control system, and the plant DCS control system may perform load shedding control, which is not limited.

The reactor of the nuclear power plant according to the embodiment of the present disclosure may be a high temperature gas cooled reactor, which may be configured with a plurality of reactors, for example, the high temperature gas cooled reactor of the embodiment adopts a "two reactors with one machine" operating mode, that is, the embodiment may be configured with two reactors, which are divided into a # 1 reactor and a # 2 reactor, and correspondingly, the feed pump includes a # 1 reactor feed pump and a # 2 reactor feed pump.

S102: determining a target fault type according to the fault information, wherein the target fault type comprises any one of the following items: partial reactor shutdown, all reactor shutdown, partial feed pump shutdown, all feed pump shutdown, turbine fault shutdown, and external power grid fault trip.

The fault type of this embodiment may also be referred to as a load shedding policy type, that is: RB policy, which is used to describe device failures, the failures of different devices may correspond to different failure types (i.e., RB policy), for example: the method comprises the following steps of partial reactor shutdown, all reactor shutdown, partial feed pump shutdown, all feed pump shutdown, steam turbine fault shutdown, external power grid fault trip and any other possible fault types, wherein the partial reactor shutdown can be further divided into 1# reactor shutdown and 2# reactor shutdown, and similarly, the partial feed pump shutdown can be divided into 1# reactor feed pump shutdown and 2# reactor feed pump shutdown without limitation. Also, different RB strategies may correspond to different RB control procedures.

Here, the fault type corresponding to the fault information (signal) may be referred to as a target fault type, that is, the present embodiment may determine the fault type (RB policy) according to the fault information.

S103: and executing a control process corresponding to the target fault type to carry out load shedding control on the nuclear power plant.

In practical application, an RB policy function table may be configured in advance, and the function table may record a corresponding relationship between a fault type (RB policy) and an RB control procedure, where the RB policy function table is shown in table 1:

TABLE 1

After the target fault type is determined, a control process corresponding to the target fault type may be determined according to the RB policy function table, that is: RB control process; further, the RB control process is executed, the power of a steam turbine or a reactor can be reduced under the condition that nuclear power plant equipment fails, and load reduction control of the nuclear power plant is achieved.

In some embodiments, in the case where the target failure type is partial reactor trip, the RB control procedure performed by the DEH system may be: and controlling the reactor which is not shut down to keep the current power unchanged to continue to operate, and controlling the steam turbine to reduce the maximum load shedding speed to the power matched with the reactor which is not shut down to continue to operate.

For example, if the # 1 reactor is scrammed and the # 2 reactor is normally operated, the reactor which is not scrammed in the embodiment is the # 2 reactor scrammed. Under the condition, the 2# reactor is controlled to maintain the current power to be unchanged and continue to operate, and the steam turbine is controlled to reduce the power to the power level matched with the 2# reactor according to the maximum load shedding speed and continue to operate;

for another example, if the # 2 reactor is scrammed and the # 1 reactor is normally operated, the reactor without shutdown in this embodiment is the # 1 reactor scrammed. In this case, the 1# reactor is controlled to continuously operate with the current power maintained, and the turbine is controlled to continuously operate with the power reduced to the power level matched with the 1# reactor at the maximum load shedding speed.

In other embodiments, in the case that the target failure type is a total reactor shutdown, the RB control process performed by the DEH system is to control the turbine to be shutdown, that is, to control the turbine to be shutdown if the reactor # 1 and the reactor # 2 are all scram.

In other embodiments, in the case where the target failure type is partial feedwater pump shut down, the RB control process performed by the DEH system may be: and controlling the reactor corresponding to the water feeding pump which is shut down to be shut down, controlling the reactor corresponding to the water feeding pump which is not shut down to keep the current power unchanged and continuously operating, and controlling the steam turbine to be reduced to the power matched with the reactor corresponding to the water feeding pump which is not shut down at the maximum load shedding speed and continuously operating.

For example, the reactor corresponding to the # 1 reactor feed pump is the # 1 reactor, and the reactor corresponding to the # 2 reactor feed pump is the # 2 reactor. If the 1# reactor feed pump is shut down and the 2# reactor feed pump is not shut down, the method can control the 1# reactor to shut down, control the 2# reactor to keep the current power unchanged and continue to operate, and control the steam turbine to reduce the maximum load shedding speed to the power matched with the 2# reactor and continue to operate; for another example, if the 2# reactor feed pump is shut down and the 1# reactor feed pump is not shut down, this embodiment can control the 2# reactor to shut down, control the 1# reactor to continue to operate with the current power unchanged, and control the turbine to continue to operate with the maximum load shedding speed reduced to the power level matching with the 1# reactor.

In other embodiments, in the case where the target failure type is all feedwater pump shut down, the DEH system performs the RB control procedure of: and (5) controlling all reactors to stop and controlling the steam turbine to stop. That is, if the # 1 reactor feed pump and the # 2 reactor feed pump are all shut down, the present embodiment controls all reactor shut downs (the # 1 reactor and the # 2 reactor) and controls the turbine to be shut down.

Therefore, under the condition that part of reactors or feed pumps have faults, the DEH system can realize the function of 'stopping the reactors and not stopping the reactors' by adopting a steam turbine to dump loads, and the economic benefit of a unit is ensured; in addition, under the condition that all reactors or feed pumps have faults, a steam turbine can be adopted to stop working in cooperation with the two reactors to stop the reactors, and the safety of a nuclear power unit is ensured.

In another embodiment, when the target fault type is a turbine fault shutdown, the RB control process executed by the DCS system is: controlling an atmospheric release valve to be opened, and controlling all reactors to stop when a bypass of a condenser is unavailable; or, when the condenser bypass is available and the current power of all reactors exceeds the set power by 50%, the condenser bypass is opened, the power of all reactors is controlled to be reduced to 50% of the set power, and the atmospheric release valve is controlled to be closed.

Specifically, if the steam turbine is in a fault shutdown state, the embodiment firstly controls to open the atmospheric relief valve; further, judging whether the condenser bypass is available, if not, controlling all reactors (a 1# reactor and a 2# reactor) to rapidly reduce power until shutdown; if the condenser bypass is available, the condenser bypass is opened and it is determined whether the total reactor current power exceeds 50% (50% RFP) of the set power, wherein it can be determined whether the current power of each reactor (1 # reactor and 2# reactor) exceeds 50% of its set power, respectively; and if the current power of all reactors exceeds 50% of the set power, controlling the power of all reactors to be reduced to 50% of the set power, namely: controlling the 1# reactor and the 2# reactor to rapidly reduce power at a set speed at the same time until the power of each reactor reaches 50% of the set power; further, the atmospheric release valve is closed, so that the reactor can stably run in cooperation with the bypass. And if the current power of the whole reactor does not exceed 50% of the set power, the power is maintained to be unchanged and the operation is continued.

In other embodiments, in the case that the target fault type is an external grid fault trip, the RB control process performed by the DCS system is: and controlling an atmospheric release valve to be opened, controlling all reactors to be shut down and a steam turbine to be shut down under the condition that a condenser bypass is unavailable, and opening the condenser bypass and controlling the power of all reactors to be reduced to 50% of the set power under the condition that the condenser bypass is available and the current power of all reactors exceeds 50% of the set power.

Specifically, if the external grid fails to trip, the embodiment first controls to open the atmospheric relief valve; further, judging whether the condenser bypass is available, if the condenser bypass is unavailable, controlling all reactors (a 1# reactor and a 2# reactor) to rapidly reduce power until the reactors are shut down, and controlling the steam turbine to shut down; if the condenser bypass is available, the condenser bypass is opened and it is determined whether the total reactor current power exceeds 50% (50% RFP) of the set power, wherein it can be determined whether the current power of each reactor (1 # reactor and 2# reactor) exceeds 50% of its set power, respectively; and if the current power of all reactors exceeds 50% of the set power, controlling the power of all reactors to be reduced to 50% of the set power, namely: and controlling the 1# reactor and the 2# reactor to rapidly reduce power at a set speed simultaneously until the power of each reactor is 50% of the set power, so that the steam turbine continues to operate with service load, and the bypass is matched to maintain the power of the steam turbine. And if the current power of all reactors does not exceed 50% of the set power, the power is kept unchanged and the reactor continues to operate. Thus, a "shutdown without shutdown" function may be implemented.

In this embodiment, when a nuclear power plant equipment fails, fault information is acquired, and a target fault type is determined according to the fault information, where the target fault type includes any one of: the method comprises the following steps of partial reactor shutdown, all reactor shutdown, partial water feed pump shutdown, all water feed pumps shutdown, steam turbine fault shutdown and external power grid fault tripping, and executes a control process corresponding to a target fault type to carry out load reduction control on the nuclear power plant, and can carry out load reduction control on the nuclear power plant under the condition that equipment of the nuclear power plant fails, so that safe and efficient operation of a nuclear power unit can be guaranteed.

In order to realize the embodiment, the disclosure further provides a nuclear power equipment fault load reduction control device.

FIG. 2 is a schematic diagram of a nuclear power plant fault unloading control apparatus provided in accordance with another embodiment of the present disclosure.

As shown in fig. 2, the nuclear power plant fault unloading control device 20 includes:

an obtaining module 201, configured to obtain fault information when a nuclear power plant equipment fails;

a determining module 202, configured to determine a target fault type according to the fault information, where the target fault type includes any one of: partial reactor shutdown, all reactor shutdown, partial water supply pump shutdown, all water supply pump shutdown, steam turbine fault shutdown and external power grid fault tripping;

and the control module 203 is used for executing a control process corresponding to the target fault type so as to carry out load reduction control on the nuclear power plant.

In some embodiments, the target fault type is a partial reactor trip, and the control module 203 is specifically configured to:

controlling the reactor which is not stopped to keep the current power unchanged and continuously operating; and

and controlling the steam turbine to continue operating at the maximum load shedding speed reduced to the power matched with the reactor which is not stopped.

In some embodiments, the target fault type is an all reactor trip, and the control module 203 is specifically configured to: and controlling the steam turbine to stop.

In some embodiments, the target fault type is partial feedwater pump shut-down, and the control module 203 is specifically configured to:

controlling the reactor corresponding to the shutdown feed pump to be shut down;

controlling the reactor corresponding to the water feeding pump which is not shut down to keep the current power unchanged and continuously operating; and

and controlling the steam turbine to continue operating at the maximum load shedding speed reduced to the power matched with the reactor corresponding to the non-shutdown feed water pump.

In some embodiments, the target failure type is all feedwater pump shut-down, and the control module 203 is specifically configured to:

controlling all reactors to stop; and

and controlling the steam turbine to stop.

In some embodiments, the target fault type is a turbine shutdown, and the control module is specifically configured to:

controlling an atmospheric release valve to be opened, and controlling all reactors to stop when a bypass of a condenser is unavailable;

or

And controlling the opening of the atmospheric release valve, opening the condenser bypass under the condition that the condenser bypass is available and the current power of all the reactors exceeds 50% of the set power, controlling the power of all the reactors to be reduced to 50% of the set power, and controlling the closing of the atmospheric release valve.

In some embodiments, the target fault type is an external grid fault trip, and the control module is specifically configured to:

controlling the opening of an atmospheric release valve;

under the condition that a bypass of a condenser is unavailable, all reactors are controlled to be shut down and a steam turbine is controlled to be shut down;

and when the condenser bypass is available and the current power of all the reactors exceeds 50% of the set power, the condenser bypass is opened, and the power of all the reactors is controlled to be reduced to 50% of the set power.

In this embodiment, when a nuclear power plant equipment fails, fault information is acquired, and a target fault type is determined according to the fault information, where the target fault type includes any one of: the method comprises the following steps of partial reactor shutdown, all reactor shutdown, partial water feed pump shutdown, all water feed pumps shutdown, steam turbine fault shutdown and external power grid fault tripping, and executes a control process corresponding to a target fault type to carry out load reduction control on the nuclear power plant, and can carry out load reduction control on the nuclear power plant under the condition that equipment of the nuclear power plant fails, so that safe and efficient operation of a nuclear power unit can be guaranteed.

The present disclosure also provides an electronic device, a readable storage medium, and a computer program product according to embodiments of the present disclosure.

In order to implement the foregoing embodiments, the present disclosure also proposes a computer program product, which when executed by an instruction processor in the computer program product, executes the nuclear power plant fault unloading control method proposed by the foregoing embodiments of the present disclosure.

FIG. 3 illustrates a block diagram of an exemplary electronic device suitable for use in implementing embodiments of the present disclosure. The electronic device 12 shown in fig. 3 is only an example and should not bring any limitations to the functionality and scope of use of the disclosed embodiments.

As shown in FIG. 3, electronic device 12 is in the form of a general purpose computing device. The components of the electronic device 12 may include, but are not limited to: one or more processors or processing units 16, a system memory 28, and a bus 18 that couples various system components including the system memory 28 and the processing unit 16.

Bus 18 represents one or more of any of several types of bus structures, including a memory bus or memory controller, a peripheral bus, an accelerated graphics port, a processor, or a local bus using any of a variety of bus architectures. These architectures include, but are not limited to, industry Standard Architecture (ISA) bus, micro Channel Architecture (MAC) bus, enhanced ISA bus, video Electronics Standards Association (VESA) local bus, and Peripheral Component Interconnect (PCI) bus, to name a few.

Electronic device 12 typically includes a variety of computer system readable media. Such media may be any available media that is accessible by electronic device 12 and includes both volatile and nonvolatile media, removable and non-removable media.

Memory 28 may include computer system readable media in the form of volatile Memory, such as Random Access Memory (RAM) 30 and/or cache Memory 32. The electronic device 12 may further include other removable/non-removable, volatile/nonvolatile computer system storage media. By way of example only, storage system 34 may be used to read from and write to non-removable, nonvolatile magnetic media (not shown in FIG. 3, and commonly referred to as a "hard drive").

Although not shown in FIG. 3, a disk drive for reading from and writing to a removable, nonvolatile magnetic disk (e.g., a "floppy disk") and an optical disk drive for reading from or writing to a removable, nonvolatile optical disk (e.g., a Compact disk Read Only Memory (CD-ROM), a Digital versatile disk Read Only Memory (DVD-ROM), or other optical media) may be provided. In these cases, each drive may be connected to bus 18 by one or more data media interfaces. Memory 28 may include at least one program product having a set (e.g., at least one) of program modules that are configured to carry out the functions of embodiments of the disclosure.

A program/utility 40 having a set (at least one) of program modules 42 may be stored, for example, in memory 28, such program modules 42 including, but not limited to, an operating system, one or more application programs, other program modules, and program data, each of which examples or some combination thereof may comprise an implementation of a network environment. Program modules 42 generally perform the functions and/or methodologies of the embodiments described in this disclosure.

Electronic device 12 may also communicate with one or more external devices 14 (e.g., keyboard, pointing device, display 24, etc.), with one or more devices that enable a user to interact with electronic device 12, and/or with any devices (e.g., network card, modem, etc.) that enable electronic device 12 to communicate with one or more other computing devices. Such communication may be through an input/output (I/O) interface 22. Also, the electronic device 12 may communicate with one or more networks (e.g., a Local Area Network (LAN), a Wide Area Network (WAN), and/or a public Network such as the Internet) via the Network adapter 20. As shown, the network adapter 20 communicates with other modules of the electronic device 12 via the bus 18. It should be understood that although not shown in the figures, other hardware and/or software modules may be used in conjunction with electronic device 12, including but not limited to: microcode, device drivers, redundant processing units, external disk drive arrays, RAID systems, tape drives, and data backup storage systems, among others.

The processing unit 16 executes various functional applications, such as implementing the nuclear power plant fault unloading control method mentioned in the foregoing embodiments, by running a program stored in the system memory 28.

Other embodiments of the disclosure will be apparent to those skilled in the art from consideration of the specification and practice of the invention disclosed herein. This disclosure is intended to cover any variations, uses, or adaptations of the disclosure following, in general, the principles of the disclosure and including such departures from the present disclosure as come within known or customary practice within the art to which the disclosure pertains. It is intended that the specification and examples be considered as exemplary only, with a true scope and spirit of the disclosure being indicated by the following claims.

It will be understood that the present disclosure is not limited to the precise arrangements described above and shown in the drawings and that various modifications and changes may be made without departing from the scope thereof. The scope of the present disclosure is limited only by the appended claims.

It should be noted that, in the description of the present disclosure, the terms "first", "second", etc. are used for descriptive purposes only and are not to be construed as indicating or implying relative importance. Further, in the description of the present disclosure, "a plurality" means two or more unless otherwise specified.

Any process or method descriptions in flow charts or otherwise described herein may be understood as representing modules, segments, or portions of code which include one or more executable instructions for implementing specific logical functions or steps in the process, and alternate implementations are included within the scope of the preferred embodiment of the present disclosure in which functions may be executed out of order from that shown or discussed, including substantially concurrently or in reverse order, depending on the functionality involved, as would be understood by those reasonably skilled in the art of the embodiments of the present disclosure.

It should be understood that portions of the present disclosure may be implemented in hardware, software, firmware, or a combination thereof. In the above embodiments, various steps or methods may be implemented in software or firmware stored in a memory and executed by a suitable instruction execution system. For example, if implemented in hardware, as in another embodiment, any one or combination of the following techniques, which are known in the art, may be used: a discrete logic circuit having a logic gate circuit for implementing a logic function on a data signal, an application specific integrated circuit having an appropriate combinational logic gate circuit, a Programmable Gate Array (PGA), a Field Programmable Gate Array (FPGA), or the like.

It will be understood by those skilled in the art that all or part of the steps carried out in the method of implementing the above embodiments may be implemented by hardware related to instructions of a program, which may be stored in a computer readable storage medium, and the program, when executed, includes one or a combination of the steps of the method embodiments.

In addition, functional units in the embodiments of the present disclosure may be integrated into one processing module, or each unit may exist alone physically, or two or more units are integrated into one module. The integrated module can be realized in a hardware mode, and can also be realized in a software functional module mode. The integrated module, if implemented in the form of a software functional module and sold or used as a stand-alone product, may also be stored in a computer readable storage medium.

The storage medium mentioned above may be a read-only memory, a magnetic or optical disk, etc.

In the description herein, references to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present disclosure. In this specification, the schematic representations of the terms used above do not necessarily refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples.

Although embodiments of the present disclosure have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present disclosure, and that changes, modifications, substitutions and alterations may be made to the above embodiments by those of ordinary skill in the art within the scope of the present disclosure.

Claims (10)

1. A nuclear power equipment fault load shedding control method is characterized by comprising the following steps:

acquiring fault information under the condition that the nuclear power plant equipment fails;

determining a target fault type according to the fault information, wherein the target fault type comprises any one of the following items: partial reactor shutdown, all reactor shutdown, partial water supply pump shutdown, all water supply pump shutdown, steam turbine fault shutdown and external power grid fault trip;

and executing a control process corresponding to the target fault type to carry out load shedding control on the nuclear power plant.

2. The method of claim 1, wherein the target fault type is a partial reactor trip, and wherein executing the control process corresponding to the target fault type comprises:

controlling the reactor which is not stopped to keep the current power unchanged and continuously operating; and

and controlling the steam turbine to continue operating at the maximum load shedding speed reduced to the power matched with the reactor which is not stopped.

3. The method of claim 1, wherein the target fault type is an all reactor trip, and wherein executing the control process corresponding to the target fault type comprises:

and controlling the steam turbine to stop.

4. The method of claim 1, wherein the target fault type is partial feedwater pump shut-down, and wherein executing the control process corresponding to the target fault type comprises:

controlling reactor shutdown corresponding to the shutdown feed pump;

controlling the reactor corresponding to the water feeding pump which is not shut down to keep the current power unchanged and continuously operating; and

and controlling the steam turbine to continue operating at the maximum load shedding speed reduced to the power matched with the reactor corresponding to the non-shutdown feed water pump.

5. The method of claim 1, wherein the target fault type is total feedwater pump shut-down, and wherein performing the control process corresponding to the target fault type comprises:

controlling all reactors to stop; and

and controlling the steam turbine to stop.

6. The method of claim 1, wherein the target fault type is a turbine outage, and wherein executing the control process corresponding to the target fault type comprises:

controlling an atmospheric release valve to be opened, and controlling all reactors to stop when a bypass of a condenser is unavailable;

or

And controlling the opening of the atmospheric release valve, opening the condenser bypass under the condition that the condenser bypass is available and the current power of all reactors exceeds 50% of the set power, controlling the power of all reactors to be reduced to 50% of the set power, and controlling the closing of the atmospheric release valve.

7. The method of claim 1, wherein the target fault type is an external grid fault trip, and wherein executing the control process corresponding to the target fault type comprises:

controlling the opening of an atmospheric release valve;

under the condition that a bypass of a condenser is unavailable, all reactors are controlled to be shut down and a steam turbine is controlled to be shut down;

and when the condenser bypass is available and the current power of all reactors exceeds 50% of the set power, the condenser bypass is opened, and the power of all reactors is controlled to be reduced to 50% of the set power.

8. A nuclear power equipment fault load reduction control device is characterized by comprising:

the acquisition module is used for acquiring fault information under the condition that the nuclear power plant equipment fails;

a determining module, configured to determine a target fault type according to the fault information, where the target fault type includes any one of: partial reactor shutdown, all reactor shutdown, partial water supply pump shutdown, all water supply pump shutdown, steam turbine fault shutdown and external power grid fault trip;

and the control module is used for executing a control process corresponding to the target fault type so as to carry out load reduction control on the nuclear power plant.

9. The apparatus of claim 8, wherein the target fault type is a partial reactor trip, and the control module is specifically configured to:

controlling the reactor which is not stopped to keep the current power unchanged and continuously operating; and

and controlling the steam turbine to continue operating at the maximum load shedding speed reduced to the power matched with the reactor which is not stopped.

10. A non-transitory computer readable storage medium having stored thereon computer instructions for causing the computer to perform the method of any one of claims 1-7.

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