CN114887254B - Nuclear power plant fire disaster condition nuclear power equipment processing method and device - Google Patents
Nuclear power plant fire disaster condition nuclear power equipment processing method and device Download PDFInfo
- Publication number
- CN114887254B CN114887254B CN202210468473.9A CN202210468473A CN114887254B CN 114887254 B CN114887254 B CN 114887254B CN 202210468473 A CN202210468473 A CN 202210468473A CN 114887254 B CN114887254 B CN 114887254B
- Authority
- CN
- China
- Prior art keywords
- fire
- signal
- power
- equipment
- nuclear power
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- 238000003672 processing method Methods 0.000 title description 6
- 238000000034 method Methods 0.000 claims abstract description 118
- 238000005192 partition Methods 0.000 claims abstract description 79
- 238000012545 processing Methods 0.000 claims abstract description 51
- 238000012790 confirmation Methods 0.000 claims abstract description 34
- 230000008569 process Effects 0.000 claims description 81
- 238000004590 computer program Methods 0.000 claims description 22
- 238000011144 upstream manufacturing Methods 0.000 claims description 17
- 238000003860 storage Methods 0.000 claims description 11
- 238000010586 diagram Methods 0.000 description 9
- 238000012806 monitoring device Methods 0.000 description 9
- 230000002265 prevention Effects 0.000 description 6
- 238000004891 communication Methods 0.000 description 5
- 230000006870 function Effects 0.000 description 5
- 238000002347 injection Methods 0.000 description 4
- 239000007924 injection Substances 0.000 description 4
- 238000012544 monitoring process Methods 0.000 description 3
- 230000001681 protective effect Effects 0.000 description 3
- 230000004913 activation Effects 0.000 description 2
- 230000008859 change Effects 0.000 description 2
- 238000007689 inspection Methods 0.000 description 2
- 239000000779 smoke Substances 0.000 description 2
- 230000003068 static effect Effects 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 238000013459 approach Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000001413 cellular effect Effects 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 230000001627 detrimental effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000002349 favourable effect Effects 0.000 description 1
- 229910021389 graphene Inorganic materials 0.000 description 1
- 238000003384 imaging method Methods 0.000 description 1
- 238000011065 in-situ storage Methods 0.000 description 1
- 239000004973 liquid crystal related substance Substances 0.000 description 1
- 230000000116 mitigating effect Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 230000000241 respiratory effect Effects 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
- 230000000007 visual effect Effects 0.000 description 1
Classifications
-
- A—HUMAN NECESSITIES
- A62—LIFE-SAVING; FIRE-FIGHTING
- A62C—FIRE-FIGHTING
- A62C3/00—Fire prevention, containment or extinguishing specially adapted for particular objects or places
- A62C3/16—Fire prevention, containment or extinguishing specially adapted for particular objects or places in electrical installations, e.g. cableways
-
- A—HUMAN NECESSITIES
- A62—LIFE-SAVING; FIRE-FIGHTING
- A62C—FIRE-FIGHTING
- A62C37/00—Control of fire-fighting equipment
- A62C37/04—Control of fire-fighting equipment with electrically-controlled release
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
Landscapes
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Health & Medical Sciences (AREA)
- Public Health (AREA)
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Safety Devices In Control Systems (AREA)
Abstract
The application relates to a method and a device for processing nuclear power equipment under the condition of a nuclear power plant fire disaster. The method comprises the following steps: acquiring fire information of a nuclear power plant; performing fire confirmation on the nuclear power plant according to the fire alarm information to obtain a fireproof partition of the nuclear power plant where the fire occurs; identifying whether the fireproof subarea in which the fire disaster occurs is a fireproof subarea in which the control equipment is located; if the fireproof subarea where the fire disaster occurs is not the fireproof subarea where the control equipment is located, acquiring a fire disaster outage signal preset in the fireproof subarea where the fire disaster occurs; and sending the fire power-off signal to the control equipment, and performing power-off treatment on the technological equipment to be powered off in the fireproof subarea where the fire disaster occurs through the control equipment according to the fire power-off signal. By adopting the method, the safety of personnel and equipment in the nuclear power plant can be ensured.
Description
Technical Field
The application relates to the technical field of nuclear power, in particular to a nuclear power plant fire disaster situation nuclear power equipment processing method, a nuclear power plant fire disaster situation nuclear power plant nuclear power equipment processing device, a computer device, a storage medium and a computer program product.
Background
Fire is one of the external disasters that the nuclear power plant must take into account, and the fire protection design of the nuclear power plant is to not only reduce the possibility of fire occurrence, but also reduce the consequences caused by fire occurrence, and finally aims to ensure the safety of personnel and equipment in the nuclear power plant. After a fire disaster occurs in a nuclear power plant, the power supply of important equipment affected by the fire disaster needs to be disconnected as soon as possible, so that on one hand, the effect of the fire disaster can be limited, the expansion of the influence range of the fire disaster can be avoided, and on the other hand, the functional disorder caused by misoperation of the equipment under the condition of the fire disaster can be prevented, and the difficulty is brought to an operator for controlling a unit. The conventional approach is for the operator to manually power down the fire-affected safety level equipment in the event of a fire.
However, the nuclear power plant not only comprises safety-level equipment, but also is distributed with a large number of non-safety-level equipment, and the traditional mode cannot conduct power-off treatment on the non-safety-level equipment, so that the safety of personnel and equipment in the nuclear power plant cannot be ensured.
Disclosure of Invention
In view of the foregoing, it is desirable to provide a method, apparatus, computer device, computer readable storage medium, and computer program product for handling nuclear power plant equipment in the event of a nuclear power plant fire that is capable of ensuring personnel and equipment safety within the nuclear power plant.
In a first aspect, the application provides a method for processing nuclear power equipment in the case of a fire disaster in a nuclear power plant. The method comprises the following steps:
acquiring fire information of a nuclear power plant;
performing fire confirmation on the nuclear power plant according to the fire alarm information to obtain a fireproof partition of the nuclear power plant where the fire occurs;
identifying whether the fireproof subarea in which the fire disaster occurs is a fireproof subarea in which the control equipment is located;
if the fireproof subarea where the fire disaster occurs is not the fireproof subarea where the control equipment is located, acquiring a fire disaster outage signal preset in the fireproof subarea where the fire disaster occurs;
and sending the fire power-off signal to the control equipment, and performing power-off treatment on the technological equipment to be powered off in the fireproof subarea where the fire disaster occurs through the control equipment according to the fire power-off signal.
In one embodiment, the power-off processing of the process equipment to be powered off in the fireproof subarea where the fire disaster occurs according to the fire power-off signal by the control equipment includes:
determining a power supply switch controlled by the fire power-off signal through the control equipment according to the equipment type of the to-be-powered-off process equipment;
and the power supply switch is disconnected by the control equipment according to the fire power-off signal.
In one embodiment, the determining, by the control device, the power supply switch controlled by the fire power-off signal according to the device type of the process device to be powered off includes:
when the fireproof partition where the fire disaster occurs is the fireproof partition where the emergency bus is located, determining that the process equipment to be powered off is the emergency bus;
determining a power supply switch controlled by the fire control signal to be an upstream line-in switch on the emergency bus according to the emergency bus through the control equipment;
the switching off of the power supply switch by the control device according to the fire power-off signal comprises:
and the control equipment is used for switching off the upstream line-incoming switch on the emergency bus according to the fire power-off signal.
In one embodiment, the method further comprises:
and locking a bus power-off automatic interlocking signal of the emergency bus by the control equipment according to the fire power-off signal.
In one embodiment, the power-off processing of the process equipment to be powered off in the fireproof subarea where the fire disaster occurs according to the fire power-off signal by the control equipment includes:
identifying whether the control device has received a security level auto-start signal corresponding to a process device to be powered off in the fire zone in which the fire occurred;
And if the safety level automatic starting signal is not received, carrying out power-off processing on the process equipment to be powered off according to the fire power-off signal through the control equipment.
In one embodiment, the method further comprises:
and if the safety level automatic starting signal is received, the control equipment ignores the fire power-off signal.
In one embodiment, the performing fire confirmation on the nuclear power plant according to the fire alarm information, and obtaining the fireproof partition where the fire occurs includes:
the fire alarm signal is sent to a fire intervention terminal, so that fire intervention personnel of the fire intervention terminal can extinguish the fire of the nuclear power plant according to the fire alarm signal;
when the fire extinguishing information fed back by the fire intervention terminal is received, a preset fire confirmation interface is displayed;
and receiving a fire-prevention partition confirmation operation acting on the fire confirmation interface to obtain the fire-prevention partition of the nuclear power plant where the fire occurs.
In one embodiment, after the identifying whether the fire zone in which the fire occurred is a fire zone in which a control device is located, the method further comprises:
if the fireproof subarea where the fire disaster occurs is the fireproof subarea where the control equipment is located, acquiring a power-off operation list corresponding to the fireproof subarea where the control equipment is located;
And carrying out power-off treatment on target process equipment in the fireproof partition where the control equipment is located according to the power-off operation list.
In a second aspect, the application also provides a treatment device of nuclear power equipment in the case of a fire disaster of a nuclear power plant.
The device comprises:
the information acquisition module is used for acquiring fire information of the nuclear power plant;
the fire confirmation module is used for confirming the fire of the nuclear power plant according to the fire alarm information to obtain a fireproof partition of the nuclear power plant where the fire occurs;
the fireproof partition identification module is used for identifying whether the fireproof partition where the fire disaster occurs is the fireproof partition where the control equipment is located;
the power-off signal acquisition module is used for acquiring a fire power-off signal preset in the fire-proof subarea where the fire occurs if the fire-proof subarea where the fire occurs is not the fire-proof subarea where the control equipment is located;
and the power-off processing module is used for sending the fire power-off signal to the control equipment, and carrying out power-off processing on the to-be-powered-off process equipment in the fireproof partition where the fire disaster occurs through the control equipment according to the fire power-off signal.
In a third aspect, the present application also provides a computer device. The computer device comprises a memory and a processor, wherein the memory stores a computer program, and the processor executes the computer program to realize the processing method of the nuclear power plant in case of fire of the first aspect.
In a fourth aspect, the present application also provides a computer-readable storage medium. The computer readable storage medium having stored thereon a computer program which, when executed by a processor, implements a method of handling nuclear power plants in case of a fire in a nuclear power plant according to the first aspect.
In a fifth aspect, the present application also provides a computer program product. The computer program product comprises a computer program which, when executed by a processor, implements a method for handling nuclear power plants in case of fire in a nuclear power plant according to the first aspect.
According to the method, the device, the computer equipment, the storage medium and the computer program product for processing the nuclear power plant under the condition of the fire disaster, the fire disaster is confirmed to the nuclear power plant according to the acquired fire alarm information, a fire prevention partition of the fire disaster in the nuclear power plant is obtained, if the fire prevention partition of the fire disaster is not the fire prevention partition where the control equipment is located, the control equipment can ensure the control function of the process equipment, and the automatic power-off processing to the process equipment can be realized. Therefore, a fire power-off signal preset in a fire-proof subarea where a fire disaster occurs is obtained, the fire power-off signal is sent to the control equipment, and power-off processing is carried out on the technological equipment to be powered off in the fire-proof subarea where the fire disaster occurs according to the fire power-off signal through the control equipment. The fire power-off signal is introduced to participate in the driving control of the process equipment, and when a fire disaster occurs in a fireproof subarea, the power supply switch of the affected process equipment is controlled to be disconnected by the fire power-off signal of the fireproof subarea, so that the process equipment is stopped. The automatic power-off of the affected process equipment under the condition of fire can be realized, thereby limiting the consequence of the fire, protecting the equipment and personnel safety, simultaneously defining the equipment state under the condition of the fire, and providing important support for operators to reasonably take treatment measures to control the unit.
Drawings
FIG. 1 is an application environment diagram of a nuclear power plant processing method in the event of a nuclear power plant fire in one embodiment;
FIG. 2 is a flow diagram of a method of handling nuclear power plant in the event of a nuclear power plant fire in one embodiment;
FIG. 3 is a flow chart of a power-off process step performed by a control device according to a fire power-off signal on a process device to be powered off in a fire zone where a fire occurs in one embodiment;
FIG. 4 is a schematic diagram of a power switch controlled by a control device determining a fire power down signal based on the device type of a process device to be powered down in one embodiment;
FIG. 5 is a schematic diagram of a power-off process performed on a process device to be powered off according to a fire power-off signal by a control device in one embodiment;
FIG. 6 is a diagram of a fire confirmation screen according to an embodiment;
FIG. 7 is a block diagram of a processing arrangement of a nuclear power plant in the event of a fire in one embodiment;
fig. 8 is an internal structural diagram of a computer device in one embodiment.
Detailed Description
The present application will be described in further detail with reference to the drawings and examples, in order to make the objects, technical solutions and advantages of the present application more apparent. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the scope of the application.
The nuclear power plant fire disaster situation nuclear power equipment treatment method provided by the embodiment of the application can be applied to an application environment shown in figure 1. Wherein the monitoring device 102 communicates with the nuclear power plant management device 104 via a network. The nuclear power plant management device 104 communicates with the control device 106 via a network. The monitoring device 102 may include a plurality of fire monitoring devices such as cameras, sensors, and the like. The monitoring device 102 is used to monitor the fire conditions of each fire partition of the nuclear power plant. The monitoring device 102 transmits fire alarm information to the nuclear power plant management device 104 through a network when it detects a fire occurrence in the nuclear power plant. The nuclear power plant management equipment 104 confirms the fire disaster of the nuclear power plant according to the fire alarm information, obtains the fireproof subarea of the fire disaster in the nuclear power plant, identifies whether the fireproof subarea of the fire disaster is the fireproof subarea where the control equipment is located, acquires a fire power-off signal preset in the fireproof subarea where the fire disaster occurs if the fireproof subarea of the fire disaster is not the fireproof subarea where the control equipment is located, sends the fire power-off signal to the control equipment 106, and performs power-off processing on equipment to be powered off in the fireproof subarea where the fire disaster occurs according to the fire power-off signal through the control equipment 106. The nuclear power plant management device 104 may be, but not limited to, various personal computers, notebook computers, smart phones, tablet computers, internet of things devices, and portable wearable devices, and the control device 106 may be a control cabinet.
In one embodiment, as shown in fig. 2, a method for processing nuclear power plant in case of fire is provided, and the method is applied to the nuclear power plant management apparatus in fig. 1 for illustration, and includes the following steps:
and 202, acquiring fire alarm information of the nuclear power plant.
The fire alarm information is fire alarm information and is used for indicating the nuclear power plant management equipment to extinguish the fire of the nuclear power plant.
Specifically, a plurality of monitoring devices, and a nuclear power plant management device are installed in advance in the nuclear power plant. The monitoring equipment is used for monitoring the fire condition of each fireproof partition of the nuclear power plant. The nuclear power plant management equipment is used for processing nuclear power equipment under the condition of nuclear power plant fire. The nuclear power plant may be a fire-affected unsafe-level plant that may include process equipment such as a main pump, a main feedwater pump, and the like. The monitoring device may include a plurality of fire monitoring devices such as cameras, sensors, and the like. For example, the sensor may include a smoke detector, an infrared temperature detector, and the like. When the monitoring equipment monitors that the nuclear power plant has a fire disaster, fire alarm information is generated and sent to the nuclear power plant management equipment.
Furthermore, the fire condition of the nuclear power plant can be detected by triggering an existing fire detection system of the nuclear power plant, witnessing by on-site patrol personnel and the like, and after the fire condition is detected, the fire alarm information is sent to the nuclear power plant management equipment.
And 204, carrying out fire confirmation on the nuclear power plant according to the fire alarm information to obtain a fireproof subarea where the fire disaster occurs in the nuclear power plant.
After acquiring the fire information, the nuclear power plant management equipment needs to confirm whether the fire information is false or not on site and try to extinguish the fire. Only if the fire condition is uncontrollable, the fire of the nuclear power plant is considered to be confirmed, so that a fireproof partition of the fire of the nuclear power plant is obtained. If the fire can be controlled quickly, the fire of the nuclear power plant is not considered to be confirmed. Therefore, the expansion of the fire disaster result can be avoided, and the operation of the unit is further greatly influenced.
Step 206, identify whether the fire zone in which the fire occurred is the fire zone in which the control device is located. If the fire partition is the fire partition where the control device is located (if yes), then step 208 is performed; if the fire zone is not the fire zone in which the control device is located (if not), step 210 is performed.
Step 208, obtaining a power-off operation list corresponding to the fireproof partition where the control equipment is located. Execution continues with step 212.
Step 210, acquiring a fire power-off signal preset in a fireproof partition where a fire occurs. Execution continues with step 214.
The control device is used for controlling the process equipment in each fireproof partition of the nuclear power plant. For example, the control device may be a control cabinet.
The power-off operation list is used for indicating an operator to perform a list of power-off operations. The fire power-off signal is used for indicating the control equipment to perform power-off treatment on the process equipment to be powered off in the fireproof subarea where the fire disaster occurs.
Each fire partition has a corresponding power down menu. The power-off operation sheet may be stored in advance in the nuclear power plant management apparatus. When a fire disaster occurs in a fireproof subarea where the control equipment is located, the control function of the control equipment on the process equipment cannot be guaranteed any more. The power-off operation of the process equipment cannot be automatically achieved by controlling the equipment control unit within the equipment. At this time, the power-off processing should be performed on the process equipment according to the power-off operation sheet. Accordingly, the nuclear power plant management apparatus, after obtaining the fire partition in which the fire has occurred, needs to recognize whether the fire partition in which the fire has occurred is the fire partition in which the control apparatus is located. If the fireproof subarea in which the fire disaster occurs is the fireproof subarea in which the control equipment is located, acquiring a power-off operation list corresponding to the fireproof subarea in which the control equipment is located, so that power-off processing is carried out on target process equipment in the fireproof subarea according to the power-off operation list. The target process equipment may include process equipment affected by a fire.
In the case of fire, taking into consideration factors such as fire, smoke attack, operability of equipment in the case of fire and the like, in-situ power-off operation of the equipment in the case of fire is different from that in the case of non-fire, and at least the following information is included in a power-off operation list: equipment requiring power outage (target process equipment), target rooms, access routes, escape routes, protective advice and tools, and the like. For example, the fire protection advice may be an emergency light, a respiratory mask, etc., and the tool may be a test box, etc.
The specific implementation form of the power-off operation list is not limited in this embodiment, and may be various forms such as a table, a document, and the like. As shown in table 1, a power-off operation list is in a table form.
TABLE 1 Power-off operation sheet
The fire power-off signal is used to control process equipment that is still capable of automatic control after taking into account the consequences of the fire. For the fireproof subarea where the non-control equipment for fire disaster is located, the nuclear power plant management equipment is still in a normal working state, and the control function of the process equipment can still be ensured. In this case, each fire partition is provided with a corresponding fire outage signal. The fire power-off signal is directly sent to an equipment control unit in the control equipment and is used for automatically switching off a power supply switch to be powered off, so that the process equipment to be powered off controlled by the switch is powered off and stopped. Therefore, if the nuclear power plant management equipment identifies that the fireproof subarea where the fire disaster occurs is not the fireproof subarea where the control equipment is located, a fire disaster outage signal preset in the fireproof subarea where the fire disaster occurs is acquired, so that the process equipment to be powered off in the fireproof subarea where the non-control equipment where the fire disaster occurs is powered off according to the fire disaster outage signal.
And 212, performing power-off treatment on target process equipment in the fireproof partition where the control equipment is located according to the power-off operation list.
The nuclear power plant management equipment can send the acquired power-off operation list to an operator terminal, and an operator corresponding to the operator terminal performs power-off processing on target process equipment in a fireproof zone where the control equipment is located according to the power-off operation list.
If the fireproof subarea where the fire disaster occurs is the fireproof subarea where the control equipment is located, the fireproof subarea where the control equipment is located is subjected to power-off treatment according to a power-off operation sheet corresponding to the fireproof subarea, so that when the control equipment cannot automatically realize the power-off operation of the process equipment, the power-off operation sheet is used for manually carrying out the power-off treatment of the process equipment on site by an operator, and the safety of equipment and personnel in the nuclear power plant is further ensured.
Step 214, a fire power-off signal is sent to the control device.
And step 216, performing power-off processing on the process equipment to be powered off in the fireproof subarea where the fire disaster occurs by the control equipment according to the fire disaster power-off signal.
The fire protection subarea in which the fire disaster occurs comprises the process equipment to be powered off, and the starting or stopping of the process equipment to be powered off can be controlled by the control equipment.
After acquiring the fire power-off signal, the nuclear power plant management device sends the fire power-off signal to the control device. And the control equipment cuts off a power supply switch of the process equipment to be powered off according to the fire power-off signal, so that the process equipment to be powered off is stopped.
According to the method for processing the nuclear power plant under the condition of the fire disaster of the nuclear power plant, the fire disaster of the nuclear power plant is confirmed according to the acquired fire alarm information, a fire prevention partition of the fire disaster in the nuclear power plant is obtained, if the fire prevention partition of the fire disaster is not the fire prevention partition where the control equipment is located, the control equipment can ensure the control function of the process equipment, and the automatic power-off processing of the process equipment can be realized. Therefore, a fire power-off signal preset in a fire-proof subarea where a fire disaster occurs is obtained, the fire power-off signal is sent to the control equipment, and power-off processing is carried out on the technological equipment to be powered off in the fire-proof subarea where the fire disaster occurs according to the fire power-off signal through the control equipment. The fire power-off signal is introduced to participate in the driving control of the process equipment, and when a fire disaster occurs in a fireproof subarea, the power supply switch of the affected process equipment is controlled to be disconnected by the fire power-off signal of the fireproof subarea, so that the process equipment is stopped. The automatic power-off of the affected process equipment under the condition of fire can be realized, thereby limiting the consequence of the fire, protecting the equipment and personnel safety, simultaneously defining the equipment state under the condition of the fire, and providing important support for operators to reasonably take treatment measures to control the unit.
In an alternative manner of this embodiment, as shown in fig. 3, performing, by the control device, power-off processing on the process device to be powered off in the fireproof partition where the fire occurs according to the fire power-off signal includes:
and 302, determining a power supply switch controlled by a fire power-off signal by the control equipment according to the equipment type of the process equipment to be powered off.
Step 304, the power supply switch is turned off by the control device according to the fire power-off signal.
The fire power-off signal directly participates in the control of a power supply switch of the process equipment, and the purpose of the fire power-off signal is to disconnect the power supply of the process equipment. The power supply switch controlled by the fire power-off signal is different from one process equipment type to another. For example, process equipment types may include pumps, electric heaters, fans, and other active equipment, distribution boards, bus bars, electrically operated valves, and the like. The power supply switch corresponding to the active equipment is a switch (a breaker, a contactor and the like) on the power supply outlet. The power supply switch corresponding to the distribution board or the bus is a distribution board or bus upstream line incoming switch (a breaker, a contactor and the like), and when the power supply switch is disconnected, an automatic interlocking signal of the distribution board or the bus in power failure is also needed to be locked. The corresponding power supply switch of the electric valve is a switch (a contactor, etc.) on the power supply outlet.
The power supply switch controlled by the fire power-off signal can be a power supply switch which can successfully implement equipment power-off under the premise of not expanding the power-off influence range as much as possible and considering the fire consequence.
The power supply switch controlled by the fire power-off signal determined by the control device according to the device type of the process device to be powered off will be described below by taking an electrical diagram as an example. As shown in fig. 4. If a fire disaster in a fireproof subarea only affects process equipment such as a pump, an electric valve and the like, the control equipment directly opens a switch (a breaker 5 and a contactor 6 shown in fig. 4) corresponding to the process equipment according to a fire power-off signal. If the emergency bus is in a fireproof subarea fire disaster in the figure, the emergency bus incoming line switch (the breaker 3 and the breaker 4) can also be affected by the fire disaster, and in this case, the control equipment directly opens the emergency bus upstream incoming line switch (the breaker 2) according to a fire disaster outage signal. If the fire-protection zone fire occurs in the plant bus in fig. 4, the plant bus line switch (breaker 1) is also affected by the fire, in which case the control device directly opens the line switch (not shown in fig. 4) in the main switchyard according to the fire power-off signal.
In the alternative mode, the power supply switch controlled by the fire power-off signal is determined according to the equipment type of the technological equipment to be powered off, the power supply switch is disconnected, the corresponding power supply switch is determined according to different equipment types, and the power supply switch which can successfully implement equipment power-off after considering the fire result can be selected on the premise of not expanding the power-off influence range as much as possible.
In this alternative, determining, by the control device, the power supply switch controlled by the fire power-off signal according to the device type of the process device to be powered off includes: when the fireproof partition where the fire disaster occurs is the fireproof partition where the emergency bus is located, determining that the process equipment to be powered off is the emergency bus; determining an emergency bus upstream line switch controlled by a fire control signal through control equipment according to an emergency bus; the switching off of the power supply switch by the control device according to the fire power-off signal comprises: and the control equipment is used for switching off the upstream incoming line switch of the emergency bus according to the fire power-off signal.
The types of equipment of the process equipment to be powered off can include pumps, electric heaters, fans and other active equipment, distribution boards, buses, electric valves and the like. When the fireproof partition where the fire disaster occurs is the fireproof partition where the emergency bus is located, the equipment to be powered off in the fireproof partition is the emergency bus, and the emergency bus belongs to one of the buses. The power supply switch controlled by the fire power-off signal can be determined to be an upstream line-in switch on the emergency bus by the control equipment according to the emergency bus, so that the upstream line-in switch on the emergency bus is disconnected.
Furthermore, the automatic interlocking signal of bus power failure of the emergency bus can be locked by the control equipment according to the fire power failure signal.
Referring to fig. 4, when a fire disaster occurs in a fireproof partition where an emergency bus is located, the emergency bus is out of voltage, and since the emergency diesel engine is automatically started after the emergency bus is out of voltage, the control device is used for switching off an upstream line switch on the emergency bus according to a fire disaster outage signal and locking a bus outage automatic linkage signal of the emergency bus. Specifically, the automatic starting logic of the emergency diesel engine is locked through the control equipment, so that the emergency diesel engine is prevented from being automatically started and loaded, and further damage of the emergency diesel engine is prevented.
In this embodiment, when the fire disaster occurs in the fireproof subarea where the emergency bus is located, the control device is used for switching off the upstream incoming line switch of the emergency bus according to the fire disaster power-off signal. The emergency bus upstream incoming line switch can successfully power off the emergency bus under the premise of not expanding the influence range of power off as much as possible and considering the result of fire.
In an alternative manner of this embodiment, performing, by the control device, power-off processing on to-be-powered-off process devices in a fireproof partition where a fire occurs according to a fire power-off signal includes: identifying whether the control device has received a security level auto-start signal corresponding to a process device to be powered off in a fire zone in which a fire is occurring; if the safety level automatic starting signal is not received, the control equipment is used for carrying out power-off processing on the technological equipment to be powered off in the fireproof subarea where the fire disaster occurs according to the fire disaster power-off signal.
The equipment control unit of the control equipment generally receives various equipment control signals, including a safety level automatic control signal, a non-safety level automatic control signal, a manual control signal and the like, and the signals can directly control a power supply switch of the process equipment after priority management, so that the equipment is started or powered off and shut down. Based on these signals, a fire power-off signal is introduced, and a principle that the control device performs power-off processing on the process equipment to be powered off according to the fire power-off signal is described below by taking control of the pump as an example. As shown in fig. 5. After the fire power-off signal is introduced, the priority of the equipment control signal may be: the safety level automatic control signal > the fire power-off signal > the manual control signal > the non-safety level automatic control signal. The priority of the fire power down signal is lower than the safety level automatic control signal because the safety level automatic control signal is typically set from a nuclear safety point of view.
After receiving the fire power-off signal sent by the nuclear power plant management equipment, the control equipment firstly identifies whether the control equipment receives a safety automatic starting signal corresponding to the technological equipment to be powered off in the fireproof subarea where the fire disaster occurs. If the safety level automatic starting signal is not received, the control equipment performs power-off processing on the technological equipment to be powered off according to the fire power-off signal. In this alternative, if the control device has received the security level auto-start signal, the control device ignores the fire power-off signal and does not power-off the device.
Because the safety level automatic control signal is better than the fire power-off signal, if the safety level automatic control signal requires that certain equipment be started, the fire power-off signal is not powered off and stopped even if the fire power-off signal exists. For example, the safety injection system activation signal generated by the reactor protection system requires that the high pressure safety injection pump and the low pressure safety injection pump be activated, at which time even if a fire outage signal is present, these pumps will not be shut down because the fire outage signal has a lower priority than the automatic activation signal generated by the reactor protection system. This is because the occurrence of a safety level automatic control signal generally means that some type of nuclear accident has occurred, and that the corresponding safety level equipment needs to be started immediately to alleviate the accident, for example, after a coolant loss accident occurs, the reactor protection system triggers the safety injection system to start, and after a main water loss accident occurs, the reactor protection system triggers the emergency water supply system to start. Preventing further damage to the device by powering down the device is a secondary consideration compared to nuclear safety. Even in the case of fire, maintaining the continuous operation of these devices rather than directly powering them off, while being detrimental to the devices themselves, is advantageous in terms of mitigating nuclear accidents.
Further, the fire power-off signal has a higher priority than the manual control signal and the non-safety level automatic control signal because: (1) In case of fire, the normal operation of the equipment is seriously affected, the performance target of the equipment can not be ensured any more, and the continuous operation brings serious interference to the operation and control of the unit; (2) Meanwhile, from the viewpoints of protecting equipment and preventing further damage of the equipment, the equipment is beneficial to be powered off and shut down. For example, when an operator intends to start the charging pump by switching on the power supply switch of the charging pump through the manual control signal, if the fire power-off signal exists at this time, the power supply switch of the charging pump is directly disconnected to stop the operation of the charging pump, because under the condition of fire, the shutdown of the charging pump can clarify the equipment state, the operator can timely put into operation for replacing the function, and further damage of the charging pump is prevented.
In the alternative mode, if the control equipment does not receive the security level automatic start signal, the power-off processing is performed on the process equipment to be powered off according to the fire power-off signal. The device is powered off only when the security level automatic start signal is not received, and if the security level automatic start signal is received, the control device ignores the fire power-off signal. Therefore, the equipment control can be realized through the priority of the signals, a mode which is favorable for link nuclear accidents can be adopted when nuclear accidents occur, and further damage to the equipment can be prevented when nuclear accidents do not occur.
In one embodiment, performing fire confirmation on a nuclear power plant according to fire alarm information, and obtaining a fireproof partition for the occurrence of a fire comprises: the fire alarm signal is sent to the fire intervention terminal, so that fire intervention personnel of the fire intervention terminal can extinguish the fire of the nuclear power plant according to the fire alarm signal; when fire disaster interference terminal feedback fire disaster incapacity information is received, a preset fire disaster confirmation interface is displayed; and receiving a fire-prevention partition confirmation operation acting on the fire confirmation interface to obtain the fire-prevention partition of the nuclear power plant where the fire occurs.
After the nuclear power plant management equipment acquires the fire alarm signal, the fire alarm signal is sent to the fire intervention terminal. The fire intervention terminal may be a secondary intervention terminal, such as a dispatch personnel terminal. Specifically, after detecting the fire information, the monitoring device sends the fire information to the nuclear power plant management device in the main control room. After the fire information is found by the personnel on duty in the main control room, the fire information is sent to a dispatching personnel terminal, and the dispatching personnel wear protective clothing to reach the scene to try to extinguish the fire. The master control room on duty personnel are dispatched to the scene to try to extinguish the fire as a secondary intervention by wearing protective clothing with equipment.
Furthermore, the nuclear power plant can detect the fire condition of the nuclear power plant through the witnessed eye of the on-site patrol personnel, the on-site patrol personnel try to extinguish the fire after finding the fire condition, and if the fire cannot be extinguished, the on-site patrol personnel terminal can feed back corresponding information to the nuclear power plant management equipment. And taking the fire extinguishment attempt of the field inspection personnel as a first-level intervention, and taking the terminal of the field inspection personnel as a first-level intervention terminal.
The multi-level intervention mode can extinguish fire simultaneously or sequentially according to a preset intervention sequence. For example, the preset intervention sequence may be a first level of intervention followed by a second level of intervention.
When fire intervention terminals, namely the fire extinguishable information fed back by the secondary intervention terminals, are received, a preset fire confirmation interface is displayed. The nuclear power plant management apparatus is provided with a fire confirmation screen in advance. When the nuclear power plant management equipment receives the fire extinguishing incapability information fed back by the secondary intervention terminal, the fact that the fire disaster in the fireproof subarea cannot be extinguished by the existing means is indicated, and the third-level intervention and the fourth-level intervention can be implemented by special firefighting team support. Wherein three-level intervention is fire extinguishing for the fire department in the factory, and four-level intervention is fire extinguishing for the fire department outside the factory. The nuclear power plant management equipment displays a fire confirmation picture, a master control room attendant triggers a confirmation button corresponding to the fire-proof partition where the fire occurs in the fire confirmation picture to confirm the fire, and accordingly the nuclear power plant management equipment receives confirmation operation acting on the fire confirmation picture, and further the fire-proof partition where the fire occurs in the nuclear power plant is obtained. As shown in fig. 6, a fire confirmation screen is schematically shown. The fire-proof partition comprises two columns A and B, wherein each fire-proof partition corresponds to one fire confirmation button.
If the fire of the nuclear power plant can be quickly controlled by at least one of the primary and secondary interventions, the fire is not considered to be confirmed. Therefore, the expansion of the fire disaster result can be avoided, and further, the larger influence on the operation of the unit is avoided.
In this embodiment, fire intervention personnel through the fire intervention terminal extinguish the fire of the nuclear power plant according to the fire alarm signal, and if the fire cannot be extinguished, the fire is confirmed, so that the nuclear power equipment can be rapidly processed according to the fire situation, the fire consequences can be limited, and the equipment and personnel safety are protected.
It should be understood that, although the steps in the flowcharts related to the above embodiments are sequentially shown as indicated by arrows, these steps are not necessarily sequentially performed in the order indicated by the arrows. The steps are not strictly limited to the order of execution unless explicitly recited herein, and the steps may be executed in other orders. Moreover, at least some of the steps in the flowcharts described in the above embodiments may include a plurality of steps or a plurality of stages, which are not necessarily performed at the same time, but may be performed at different times, and the order of the steps or stages is not necessarily performed sequentially, but may be performed alternately or alternately with at least some of the other steps or stages.
Based on the same inventive concept, the embodiment of the application also provides a processing device for the nuclear power plant under the condition of fire disaster, which is used for realizing the processing method for the nuclear power plant under the condition of fire disaster. The implementation scheme of the device for solving the problems is similar to the implementation scheme recorded in the method, so the specific limitation in the embodiment of the device for processing nuclear power equipment in the case of one or more nuclear power plant fires provided below can be referred to the limitation of the method for processing nuclear power equipment in the case of nuclear power plant fires hereinabove, and the description is omitted here.
In one embodiment, as shown in fig. 7, there is provided a treatment apparatus for nuclear power plant in case of fire, comprising: an information acquisition module 702, a fire confirmation module 704, a fire partition identification module 706, a power down signal acquisition module 708, and a power down processing module 710, wherein:
the information acquisition module 702 is configured to acquire fire information of a nuclear power plant.
And the fire confirmation module 704 is used for carrying out fire confirmation on the nuclear power plant according to the fire alarm information to obtain a fireproof partition of the nuclear power plant where the fire occurs.
A fire partition identification module 706 for identifying whether the fire partition in which the fire occurred is a fire partition in which the control device is located.
The power-off signal acquisition module 708 is configured to acquire a fire power-off signal preset in a fire partition in which a fire occurs if the fire partition in which the fire occurs is not the fire partition in which the control device is located.
The power-off processing module 710 is configured to send a fire power-off signal to the control device, and perform power-off processing on the to-be-powered-off process device in the fireproof partition where the fire occurs according to the fire power-off signal by the control device.
In one embodiment, the power-off processing module 710 is further configured to determine, by the control device, a power switch controlled by the fire power-off signal according to a device type of the process device to be powered off; the power supply switch is disconnected according to the fire power-off signal through the control equipment.
In one embodiment, the power down processing module 710 is further configured to determine that the process device to be powered down is an emergency bus when the fire partition in which the fire occurs is the fire partition in which the emergency bus is located; the control device determines that a power supply switch controlled by a fire control signal is an upstream line-in switch on the emergency bus according to the emergency bus; the switching off of the power supply switch by the control device according to the fire power-off signal comprises: and the control equipment is used for switching off the upstream incoming line switch of the emergency bus according to the fire power-off signal.
In one embodiment, the apparatus further comprises: and the signal locking module is used for locking the bus power-off automatic interlocking signal of the emergency bus according to the fire power-off signal through the control equipment.
In one embodiment, the power down processing module 710 is further configured to identify whether the control device has received a security level auto-start signal corresponding to a process device to be powered down in a fire zone in which a fire is occurring; if the safety level automatic starting signal is not received, the control equipment performs power-off processing on the technological equipment to be powered off according to the fire power-off signal.
In one embodiment, the apparatus further comprises: and the signal control module is used for ignoring the fire power-off signal by the control equipment if the safety level automatic start signal is received.
In one embodiment, the fire confirmation module 704 is further configured to send a fire alarm signal to the fire intervention terminal, so that a fire intervention person of the fire intervention terminal extinguishes the nuclear power plant according to the fire alarm signal; when fire disaster interference terminal feedback fire disaster incapacity information is received, a preset fire disaster confirmation interface is displayed; and receiving a fire-prevention partition confirmation operation acting on the fire confirmation interface to obtain the fire-prevention partition of the nuclear power plant where the fire occurs.
In one embodiment, the apparatus further comprises: the operation list processing module is used for acquiring a power-off operation list corresponding to the fireproof subarea where the control equipment is located if the fireproof subarea where the fire disaster occurs is the fireproof subarea where the control equipment is located; and carrying out power-off treatment on target process equipment in the fireproof partition where the control equipment is located according to the power-off operation list.
All or part of each module in the processing device of the nuclear power plant under the condition of fire disaster can be realized by software, hardware and the combination thereof. The above modules may be embedded in hardware or may be independent of a processor in the computer device, or may be stored in software in a memory in the computer device, so that the processor may call and execute operations corresponding to the above modules.
In one embodiment, a computer device is provided, which may be a terminal, and the internal structure thereof may be as shown in fig. 8. The computer device includes a processor, a memory, an input/output interface, a communication interface, a display unit, and an input means. The processor, the memory and the input/output interface are connected through a system bus, and the communication interface, the display unit and the input device are connected to the system bus through the input/output interface. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system and a computer program. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The input/output interface of the computer device is used to exchange information between the processor and the external device. The communication interface of the computer device is used for carrying out wired or wireless communication with an external terminal, and the wireless mode can be realized through WIFI, a mobile cellular network, NFC (near field communication) or other technologies. The computer program, when executed by a processor, implements a method for processing nuclear power plant equipment in the event of a fire. The display unit of the computer device is used for forming a visual picture, and can be a display screen, a projection device or a virtual reality imaging device. The display screen can be a liquid crystal display screen or an electronic ink display screen, and the input device of the computer equipment can be a touch layer covered on the display screen, can also be a key, a track ball or a touch pad arranged on the shell of the computer equipment, and can also be an external keyboard, a touch pad or a mouse and the like.
It will be appreciated by those skilled in the art that the structure shown in FIG. 8 is merely a block diagram of some of the structures associated with the present inventive arrangements and is not limiting of the computer device to which the present inventive arrangements may be applied, and that a particular computer device may include more or fewer components than shown, or may combine some of the components, or have a different arrangement of components.
In one embodiment, a computer device is provided, comprising a memory and a processor, the memory having stored therein a computer program, the processor implementing the steps of the method embodiments described above when the computer program is executed.
In one embodiment, a computer-readable storage medium is provided, on which a computer program is stored which, when executed by a processor, implements the steps of the method embodiments described above.
In an embodiment, a computer program product is provided, comprising a computer program which, when executed by a processor, implements the steps of the method embodiments described above.
It should be noted that, the user information (including but not limited to user equipment information, user personal information, etc.) and the data (including but not limited to data for analysis, stored data, presented data, etc.) related to the present application are information and data authorized by the user or sufficiently authorized by each party, and the collection, use and processing of the related data need to comply with the related laws and regulations and standards of the related country and region.
Those skilled in the art will appreciate that implementing all or part of the above described methods may be accomplished by way of a computer program stored on a non-transitory computer readable storage medium, which when executed, may comprise the steps of the embodiments of the methods described above. Any reference to memory, database, or other medium used in embodiments provided herein may include at least one of non-volatile and volatile memory. The nonvolatile Memory may include Read-Only Memory (ROM), magnetic tape, floppy disk, flash Memory, optical Memory, high density embedded nonvolatile Memory, resistive random access Memory (ReRAM), magnetic random access Memory (Magnetoresistive Random Access Memory, MRAM), ferroelectric Memory (Ferroelectric Random Access Memory, FRAM), phase change Memory (Phase Change Memory, PCM), graphene Memory, and the like. Volatile memory can include random access memory (Random Access Memory, RAM) or external cache memory, and the like. By way of illustration, and not limitation, RAM can be in the form of a variety of forms, such as static random access memory (Static Random Access Memory, SRAM) or dynamic random access memory (Dynamic Random Access Memory, DRAM), and the like. The databases referred to in the embodiments provided herein may include at least one of a relational database and a non-relational database. The non-relational database may include, but is not limited to, a blockchain-based distributed database, and the like. The processor referred to in the embodiments provided in the present application may be a general-purpose processor, a central processing unit, a graphics processor, a digital signal processor, a programmable logic unit, a data processing logic unit based on quantum computing, or the like, but is not limited thereto.
The technical features of the above embodiments may be arbitrarily combined, and all possible combinations of the technical features in the above embodiments are not described for brevity of description, however, as long as there is no contradiction between the combinations of the technical features, they should be considered as the scope of the description.
The foregoing examples illustrate only a few embodiments of the application and are described in detail herein without thereby limiting the scope of the application. It should be noted that it will be apparent to those skilled in the art that several variations and modifications can be made without departing from the spirit of the application, which are all within the scope of the application. Accordingly, the scope of the application should be assessed as that of the appended claims.
Claims (11)
1. A method for treating nuclear power plant fire conditions, the method comprising:
acquiring fire information of a nuclear power plant;
performing fire confirmation on the nuclear power plant according to the fire alarm information to obtain a fireproof partition of the nuclear power plant where the fire occurs, wherein the fireproof partition comprises: according to the fire alarm information, extinguishing fire, if the fire condition is uncontrollable, confirming the fire disaster of the nuclear power plant and obtaining a fireproof partition of the fire disaster in the nuclear power plant;
Identifying whether the fireproof subarea in which the fire disaster occurs is a fireproof subarea in which the control equipment is located;
if the fireproof subarea where the fire disaster occurs is not the fireproof subarea where the control equipment is located, acquiring a fire disaster outage signal preset in the fireproof subarea where the fire disaster occurs;
sending the fire power-off signal to the control equipment, and performing power-off processing on the to-be-powered-off process equipment in the fireproof partition with the fire according to the fire power-off signal by the control equipment, wherein the power-off processing comprises the following steps: determining a power supply switch controlled by the fire power-off signal through the control equipment according to the equipment type of the to-be-powered-off process equipment; when the fireproof partition where the fire disaster occurs is the fireproof partition where the emergency bus is located, determining that the process equipment to be powered off is the emergency bus; determining a power supply switch controlled by the fire control signal to be an upstream line-in switch on the emergency bus according to the emergency bus through the control equipment; the switching off of the power supply switch by the control device according to the fire power-off signal comprises: disconnecting an upstream line-in switch on the emergency bus by the control equipment according to the fire power-off signal; locking a bus power-off automatic interlocking signal of the emergency bus according to the fire power-off signal through the control equipment;
And the power supply switch is disconnected by the control equipment according to the fire power-off signal.
2. The method of claim 1, wherein the powering off process equipment to be powered off in the fire zone for which a fire occurred according to the fire power-off signal by the control device comprises:
identifying whether the control device has received a security level auto-start signal corresponding to a process device to be powered off in the fire zone in which the fire occurred;
and if the safety level automatic starting signal is not received, carrying out power-off processing on the process equipment to be powered off according to the fire power-off signal through the control equipment.
3. The method according to claim 2, wherein the method further comprises:
and if the safety level automatic starting signal is received, the control equipment ignores the fire power-off signal.
4. A method according to claim 3, wherein the control device comprises a device control unit for receiving a plurality of device control signals, the device control signals comprising: a safety level automatic control signal, a non-safety level automatic control signal, a manual control signal and a fire power-off signal.
5. The method of claim 1, wherein said validating the fire of the nuclear power plant based on the fire alarm information to obtain a fire zone in which the fire occurred comprises:
the fire alarm signal is sent to a fire intervention terminal, so that fire intervention personnel of the fire intervention terminal can extinguish the fire of the nuclear power plant according to the fire alarm signal;
when the fire extinguishing information fed back by the fire intervention terminal is received, a preset fire confirmation interface is displayed;
and receiving a fire-prevention partition confirmation operation acting on the fire confirmation interface to obtain the fire-prevention partition of the nuclear power plant where the fire occurs.
6. The method of any one of claims 1 to 5, wherein after the identifying whether the fire zone in which the fire occurred is a fire zone in which a control device is located, the method further comprises:
if the fireproof subarea where the fire disaster occurs is the fireproof subarea where the control equipment is located, acquiring a power-off operation list corresponding to the fireproof subarea where the control equipment is located;
and carrying out power-off treatment on target process equipment in the fireproof partition where the control equipment is located according to the power-off operation list.
7. A nuclear power plant fire condition nuclear power plant treatment apparatus, the apparatus comprising:
the information acquisition module is used for acquiring fire information of the nuclear power plant;
the fire confirmation module is used for confirming the fire of the nuclear power plant according to the fire alarm information to obtain a fireproof partition of the nuclear power plant, and comprises the following components: according to the fire alarm information, extinguishing fire, if the fire condition is uncontrollable, confirming the fire disaster of the nuclear power plant and obtaining a fireproof partition of the fire disaster in the nuclear power plant;
the fireproof partition identification module is used for identifying whether the fireproof partition where the fire disaster occurs is the fireproof partition where the control equipment is located;
the power-off signal acquisition module is used for acquiring a fire power-off signal preset in the fire-proof subarea where the fire occurs if the fire-proof subarea where the fire occurs is not the fire-proof subarea where the control equipment is located;
the power-off processing module is used for sending the fire power-off signal to the control equipment, and carrying out power-off processing on the to-be-powered-off process equipment in the fireproof partition where the fire disaster occurs through the control equipment according to the fire power-off signal, and comprises the following steps: determining a power supply switch controlled by the fire power-off signal through the control equipment according to the equipment type of the to-be-powered-off process equipment; when the fireproof partition where the fire disaster occurs is the fireproof partition where the emergency bus is located, determining that the process equipment to be powered off is the emergency bus; determining a power supply switch controlled by the fire control signal to be an upstream line-in switch on the emergency bus according to the emergency bus through the control equipment; the switching off of the power supply switch by the control device according to the fire power-off signal comprises: disconnecting an upstream line-in switch on the emergency bus by the control equipment according to the fire power-off signal; locking a bus power-off automatic interlocking signal of the emergency bus according to the fire power-off signal through the control equipment; and the power supply switch is disconnected by the control equipment according to the fire power-off signal.
8. The apparatus of claim 7, wherein the power down processing module is further configured to identify whether the control device has received a security level auto-start signal corresponding to a process device to be powered down in a fire zone in which a fire is occurring; if the safety level automatic starting signal is not received, the control equipment performs power-off processing on the technological equipment to be powered off according to the fire power-off signal.
9. The apparatus of claim 7, further comprising a signal control module for controlling the device to ignore the fire power down signal if the security level auto-start signal has been received.
10. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor implements the steps of the method of any of claims 1 to 6 when the computer program is executed.
11. A computer readable storage medium, on which a computer program is stored, characterized in that the computer program, when being executed by a processor, implements the steps of the method of any of claims 1 to 6.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210468473.9A CN114887254B (en) | 2022-04-29 | 2022-04-29 | Nuclear power plant fire disaster condition nuclear power equipment processing method and device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210468473.9A CN114887254B (en) | 2022-04-29 | 2022-04-29 | Nuclear power plant fire disaster condition nuclear power equipment processing method and device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN114887254A CN114887254A (en) | 2022-08-12 |
| CN114887254B true CN114887254B (en) | 2023-11-21 |
Family
ID=82720178
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202210468473.9A Active CN114887254B (en) | 2022-04-29 | 2022-04-29 | Nuclear power plant fire disaster condition nuclear power equipment processing method and device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN114887254B (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115394033A (en) * | 2022-08-26 | 2022-11-25 | 华能核能技术研究院有限公司 | Intelligent fire fighting method and device for nuclear power plant |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN100468473C (en) * | 2007-06-27 | 2009-03-11 | 山西通威消防电子有限公司 | Cascade type electric appliance fire alarming and control device |
| US9881705B2 (en) * | 2012-03-16 | 2018-01-30 | Catherine Lin-Hendel | Emergency and back-up cooling of nuclear fuel and reactors and fire-extinguishing, explosion prevention using liquid nitrogen |
| CN106710652B (en) * | 2016-11-01 | 2018-06-29 | 广州中国科学院工业技术研究院 | Fire fire source power monitors system in nuclear power plant's restricted clearance |
| CN107945897B (en) * | 2017-11-15 | 2020-07-17 | 中广核工程有限公司 | Method and device for processing nuclear power accidents |
| JP7085934B2 (en) * | 2018-07-23 | 2022-06-17 | エア・ウォーター防災株式会社 | Nuclear power plant fire extinguishing system |
| CN112349441B (en) * | 2020-10-27 | 2022-04-26 | 岭澳核电有限公司 | Safety processing method for cable fire misoperation of nuclear power plant |
-
2022
- 2022-04-29 CN CN202210468473.9A patent/CN114887254B/en active Active
Non-Patent Citations (1)
| Title |
|---|
| 路耀华等.《中国煤矿建井技术》.中国矿业大学出版社,1995,第1058-1059页. * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN114887254A (en) | 2022-08-12 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109493985B (en) | Digital auxiliary control panel system of nuclear power plant, design method and control system | |
| CN103632738B (en) | The fire compartment division methods of nuclear power plant | |
| CN114887254B (en) | Nuclear power plant fire disaster condition nuclear power equipment processing method and device | |
| CN111035872A (en) | Battery box fire prevention and control system and method | |
| CN114839555A (en) | Early warning method and device for battery energy storage system, electronic equipment and storage medium | |
| CN104282349A (en) | Method for guiding nuclear power plant to be safe under condition of fire disaster | |
| WO2024114272A1 (en) | Method for remotely solving thermal runaway, and related product | |
| JP2006067030A (en) | Disaster management system, method, device and program | |
| CN114864125A (en) | Failure processing method and device for fire information of nuclear power plant and computer equipment | |
| EP3324251B1 (en) | Method for managing electrical supply of a device and system for implementing said method | |
| CN115920293A (en) | Fire-fighting equipment state monitoring system, method and device | |
| CN114461491A (en) | Nuclear steam supply system function detection method and device, computer equipment and medium | |
| CN205656734U (en) | Fire alarm device of real time monitoring condition of a fire | |
| CN210313005U (en) | Elevator machine room fire control monitored control system | |
| CN204480014U (en) | A kind of Safe Production Supervision and dynamic supervision system | |
| CN106846169B (en) | Method and device for controlling nuclear power plant under fire condition | |
| CN117861133A (en) | Fire control linkage control system, method, device, computer equipment and storage medium | |
| CN206804722U (en) | A kind of residual current monitoring device | |
| WO2021026305A1 (en) | System, method and apparatus for smart ventilation in hazardous locations | |
| CN112271008B (en) | Assessment method for nuclear power plant fire accident safe shutdown path | |
| CN116052917A (en) | Nuclear power plant fire disaster caused operation event identification method and system | |
| US20240001168A1 (en) | System and method of a ring architecture of a fixed piping system implemented within a safety system of a structure to continuously supply breathable air therewithin | |
| CN117010680A (en) | Nuclear power plant factory building fire confirmation method, system, storage medium and electronic equipment | |
| US20240003561A1 (en) | System and method of a loop architecture of a fixed piping system implemented within a safety system of a structure to continuously supply breathable air therewithin | |
| CN116672636A (en) | Power consumption safety monitoring system and method |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |