CN110188973A - A kind of nuclear power station fire safety evaluating comprehensive estimation method - Google Patents
A kind of nuclear power station fire safety evaluating comprehensive estimation method Download PDFInfo
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Abstract
The present invention relates to a kind of nuclear power station fire safety evaluating comprehensive estimation methods, it the steps include: for the interrelational form in nuclear power station between distinct device to be divided into process association, cable association, regulation association is associated with workshop position, determine the equipment in nuclear power plant, cable, the attribute information of regulation and workshop simultaneously integrates common information included in its respective attribute information, made by common information interrelated between inhomogeneous attribute information, the all devices that different accident progress influence and the expected movement of these equipment are determined by the relevant regulation treatment process of equipment safety function, pass through the analysis integrated evaluation failure probability of PSA and consequence, the present invention is by nuclear power station equipment, cable, regulation, the information such as workshop are integrated, so as to obtain the shadow that the characteristic of certain point in nuclear power station changes by fire to nuclear power station integrality It rings, improves the accuracy of fire safety evaluating comprehensive assessment.
Description
Technical field
The present invention relates to nuclear safety technical fields, and in particular to a kind of nuclear power station fire safety evaluating comprehensive estimation method.
Background technique
Fire is one of the important risk that nuclear power plant faces, and bring is not only industry security risk, even more nuclear safety
Risk.It is significant that existing operating experience shows that nuclear power plant's fire influences nuclear safety, and therefore, the safety to guarantee nuclear power plant is steady
Fixed operation need to carry out the prevention, detection and fire extinguishing scheme of nuclear power plant's fire, be managed to fire risk.
For the generation of fire preventing accident, and the accident that handles and stamp out a fire in time, nuclear power station is in design, construction and fortune
The analysis and research for having carried out system during row for fire incident, are also configured with corresponding fire detection for nuclear power station and go out
Fiery equipment is provided with corresponding full-time, call fireman, has set up the corresponding accident treatment code of personnel at different levels.Therefore, always
For body, prevention and processing to nuclear power station fire be it is comprehensive, systematic, run through nuclear power station design, construction, debugging and
The full phase in longevity of operation.During the operation of nuclear power station, nuclear power station is also in its industry security management, transformation substitution, safety analysis etc.
Links are provided with corresponding fire-risk management and control measure.
Fire safety evaluating is the safety of a bulking property, and the fire safety evaluating protection of nuclear power station is related to nearly all side of nuclear power station
Face, including actual object and equipment also include Responsibility of Staff and organization and administration, further include corresponding accident treatment program and rule
Journey.But for running nuclear power station, these related fields are all relatively independent, typically operated by nuclear power station single
The different corresponding components of position are controlled and are managed, and due to the complexity and risk of fire in nuclear power station, are difficult by a portion
Fire can occur for door or tissue and control comprehensively to be coordinated and be managed, and nuclear power station is caused to be responsible for the advanced pipe of fire
Reason personnel are difficult that the fire overall risk of nuclear power station is accurately assessed and held, engineering technology relevant to fire risk
The work that personnel are also difficult to assess its part will nuclear safety consequence caused by fire safety evaluating to nuclear power station entirety and correlation
Accurately, timely assess.
Summary of the invention
The present invention is based on defects of the existing technology to provide a kind of nuclear power station fire safety evaluating comprehensive estimation method.
In order to achieve the above objectives, the technical solution adopted by the present invention is that: a kind of nuclear power station fire safety evaluating comprehensive estimation method,
Interrelational form in nuclear power station between distinct device is divided into process association, cable association, regulation association to be associated with workshop position,
The attribute information for determining equipment in nuclear power plant, cable, regulation and workshop, is integrated included in its respective attribute information
Common information makes interrelated between inhomogeneous attribute information, realization equipment, cable, workshop and regulation by common information
Whole association；By the relevant regulation treatment process of equipment safety function determine all devices that different accidents progress influences with
And the expected movement of these equipment, by the analysis integrated evaluation failure probability of PSA and consequence, evaluation result includes to equipment, electricity
The nuclear power station reactor core meltdown probability or nuclear power station radioactivity that cable, workshop, the influence consequence of regulation and these consequences ultimately cause
Substance discharges probability on a large scale.
Further, the attribute information of cable includes type of cable, cable length, the equipment of cable ends connection, cable
The gantry number of the hole and cable that fire performance, the fire load of cable, cable pass through on the way.
Further, the attribute information of equipment includes security function, device location, the power of equipment connection and control electricity
The process connection figure of cable, the PSA analysis of equipment safety function and equipment place system.
Further, the attribute information of regulation includes the PSA analysis of equipment and the regulation treatment process that regulation is related to.
Further, the attribute information of workshop includes existing equipment, cable, hole and cable testing bridge in workshop.
Further, pass through the location information of endpoint device, hole location information and the bridge passed through in cable attribute information
Workshop location information belonging to frame information acquisition endpoint device, hole and cable testing bridge, realize cable and equipment and cable with
The association of workshop position.
Further, the regulation for having used the equipment is determined by the security function in device attribute information, realizes equipment
With being associated with for regulation；Determine the workshop position where the equipment by the device location in device attribute information, realize equipment with
The association of workshop position；The power and control cable that are connected by the equipment in device attribute realize the pass of equipment and connecting cable
Connection；By flow chart by equipment with and its be associated by the other equipment that system is connected；It is carried out by equipment safety function
Nuclear power station fire safety evaluating comprehensive assessment passes through PSA assay fire incident severity degree.
Further, the equipment realization regulation being related to by regulation in the attribute information of regulation is associated with equipment, is passed through
The PSA analysis of regulation treatment process carries out the comprehensive assessment of nuclear power station fire safety evaluating.
Further, model is established in PSA analysis based on equipment and regulation in nuclear power station, establish equipment and regulation it
Between association, analyzed using system reliability evaluation technology and probabilistic risk assessment technology.
Further, the nuclear power station reactor core meltdown probability or nuclear power station ultimately caused using event discharge on a large scale probability as
The evaluation index of PSA evaluation fire incident severity degree.
After the above technical solution is adopted, the invention has the following advantages over the prior art: the present invention will be in nuclear power station
The information such as equipment, cable, regulation, workshop are integrated, and realize the overall fusion of all elements, so as to efficient, accurate
After on the cable of nuclear power station part, equipment, workshop accident or deviation on the influence process of nuclear power station general safety and its influence
Fruit is assessed, and the accuracy of nuclear plant safety evaluation decision is improved.
Detailed description of the invention
Attached drawing 1 is equipment, cable, regulation, process and the relation schematic diagram of workshop position in the present invention；
Attached drawing 2 is the attribute information figure of cable in the present invention；
Attached drawing 3 is the attribute information figure of equipment in the present invention；
Attached drawing 4 is the attribute information figure of regulation in the present invention；
Attached drawing 5 is the attribute information figure of workshop in the present invention；
Attached drawing 6 is to carry out the comprehensive assessment of nuclear power station fire safety evaluating for single or several cable in the embodiment of the present invention 1
Method；
Attached drawing 7 is the method for carrying out the comprehensive assessment of nuclear power station fire safety evaluating for hole in the embodiment of the present invention 2；
Attached drawing 8 is to carry out the comprehensive assessment of nuclear power station fire safety evaluating for the cable testing bridge in nuclear power station in the embodiment of the present invention 3
Method；
Attached drawing 9 is the method for carrying out the comprehensive assessment of nuclear power station fire safety evaluating for workshop in the embodiment of the present invention 4.
Specific embodiment
Below in conjunction with the accompanying drawings and embodiment the invention will be further described.
What one typical nuclear power station was made of sorts of systems, and it is able to achieve different production or security function, it is such as auxiliary
Help water supply system ASG, residual heat removal system RRI, safety injection system RIS etc..Each system includes corresponding equipment,
Such as pump, valve, pipeline, filter, heat exchanger；Also include the electrical equipment of all kinds of measurements, control in each system, such as controls
Cabinet processed, relay, motor, sensor etc..These systems and equipment not only include mechanical equipment on above-mentioned common meaning,
Electrical equipment, instrumentation further include corresponding structures equipment, such as steel construction, containment inside liner, containment concrete.
For the needs for meeting production and safety, nuclear power station is an organic whole, is closely joined between sorts of systems, equipment and structures
System, Change Power, fluid or control information.
Nuclear power station fire safety evaluating comprehensive estimation method of the invention, step include:
(1) interrelational form in nuclear power station between distinct device is divided into process association, cable association, regulation association and workshop position
Set association.It is specific:
Process association is to be connected between equipment by process (pipeline), all kinds of containers, the pump, valve, filtering connected by pipeline
Device etc. jointly realize fluid transmitting, realize the exchange of cold and hot energy or the measurement of pressure, temperature, thus realize system and
The design function of equipment.Fluid includes liquid, also includes gas such as coolant, boron water, fire water, condensed water, as steam,
Hydrogen etc..Such process interrelational form is in nuclear power station initial design it has been determined that and having obtained accurate calculating.
Cable association is to realize status monitoring, the power supply, start and stop information of equipment between equipment by cable connection
Transmitting.Cable include: to equipment provide operation power power cable (piezoelectricity such as 6.6kV and low tension such as 380V in generally,
220V)；The measurement cable that the information such as the relevant pressure of system equipment, temperature, humidity, radioactive activity are detected；To setting
Standby state is controlled, is determined the control cable of equipment start-stop.Power cable piezoelectric system and low generally from substation's warp
Piezoelectric system transfers power to equipment, and partial power cable is also connected with the start and stop such as emergency power supply, battery auxiliary and safety electricity
Pressure.Measurement cable connects equipment itself or sensor with control general one end of cable, and one end connects relay, cabinet, and most
Measuring signal and control signal are transmitted to main control room or spare control room at last.
Regulation association is to be connected between equipment by regulation.The regulation of nuclear power station refers to that determining nuclear power station personnel and equipment are dynamic
The program of work, regulation include: personnel's manual activity of master control room of nuclear power station operator and site operation personnel, also include fire-fighting
Regulation etc.；For workshop physical device such as the operation of pump, valve；Using console control switch button to the behaviour of such as pump, valve
Make；The auto-action etc. of nuclear power plant system equipment.For different initial state and event, regulation determined nuclear power station personnel,
The state and movement of equipment are realized with reasonably being controlled nuclear power station to nuclear plant safety, effective management.Nuclear power station
Regulation both included operate normally regulation, anticipated transient regulation, malfunction protocol, major accident regulation, also include maintenance instruction, fire
Calamity event handling regulation etc..
The association of workshop position is associated by position between equipment.According to function and security needs, Nuclear Power Station Factory Building is drawn
Divide size is a about more than 200 to be spaced, most equipment is in some interval, and a small number of such as pipelines, pump may pass through more
A interval.There are multiple equipments and cable in the same interval.When fire incident operating condition occurs, generally assume that at same
All fail every interior all devices and cable, at this point, these equipment and cable due to interval location same where it phase
Mutual correlation, and interact.
Design drawing and flow chart are for illustrating pipeline connection type between equipment；Electric diagram, cable inventory illustrate equipment it
Between electrical connection；Regulation illustrates that the management between equipment connects；The workshop location drawing illustrates that the position between equipment is associated with.
(2) it determines the attribute information of the equipment in nuclear power plant, cable, regulation and workshop and integrates its respective attribute letter
Common information included in breath makes interrelated between inhomogeneous attribute information, realization equipment, electricity by common information
Cable, workshop are associated with the entirety of regulation.It is referring to figure 1 equipment, cable, regulation, process and workshop position in the present invention
The relation schematic diagram set.
The attribute information figure of cable in the present invention is shown referring to attached drawing 2.The attribute information of one typical cable includes
The hole that type of cable, cable length, the equipment of cable ends connection, cable fire-proof characteristic, the fire load of cable, cable pass through
The gantry number of hole and cable on the way.By the location information of endpoint device, hole location information in cable attribute information and lead to
Workshop location information belonging to gantry information acquisition endpoint device, hole and the cable testing bridge crossed, realize cable and equipment and
Cable is associated with workshop position.
The attribute information figure of equipment in the present invention is shown referring to attached drawing 3.The attribute information of one typical equipment includes
Security function, device location, the power of equipment connection and control cable, the PSA analysis of equipment safety function and equipment place
The process connection figure of system.The regulation for having used the equipment is determined by the security function in device attribute information, realizes equipment
With being associated with for regulation；Determine the workshop position where the equipment by the device location in device attribute information, realize equipment with
The association of workshop position；The power and control cable that are connected by the equipment in device attribute realize the pass of equipment and connecting cable
Connection；By flow chart by equipment with and its be associated by the other equipment that pipe-line system is connected；Pass through equipment safety function
PSA analysis carry out the comprehensive assessment of nuclear power station fire safety evaluating.
The attribute information figure of regulation in the present invention is shown referring to attached drawing 4.The attribute information of one typical regulation includes
The PSA for the equipment and the regulation treatment process that regulation is related to is analyzed.The equipment being related to by regulation in the attribute information of regulation
Realization regulation is associated with equipment；The comprehensive assessment of nuclear power station fire safety evaluating is carried out by the PSA analysis of regulation treatment process.
When fire incident occurs, fire may cause equipment and cable failure and cannot implement its setting function or
Person causes equipment that the movement of non-expected design occurs, and nuclear power station related system equipment investment is caused to run, and nuclear power station is caused to be sent out
Raw power reduces, jump heap or emergency shut-down even cause more serious failure and reactor core caused to melt down.PSA analysis method is using system
The various possibility of reliability evaluation technology of uniting (i.e. fault tree and event number analysis) and probabilistic risk assessment technology to complication system
The generation of accident and its process are analyzed comprehensively, from their probability of happening and caused by consequence comprehensively considered.PSA
Model is established in analysis based on nuclear power plant equipment and regulation, that is, establishes being associated between equipment and regulation, determination is not worked together
Therefore equipment and the expected movement of these equipment that progress influences, and evaluate its failure probability and consequence.
The attribute information figure of workshop in the present invention is shown referring to attached drawing 5.The attribute information of one typical workshop includes
Existing equipment, cable, hole and cable testing bridge in workshop.It is realized by equipment existing in workshop in the attribute information of workshop
Equipment is associated with workshop position；Cable and workshop position are realized by cable existing in workshop, hole or cable testing bridge
Association.
The information for the general character that 2-attached equipment, cable, workshop and processes shown in fig. 5 include with reference to the accompanying drawings, to realize phase
The overall fusion of all information of nuclear power plant is realized in the inquiry of associate device, cable, workshop and process.
(3) by the relevant regulation treatment process of equipment safety function determine all devices that different accidents progress influences with
And the expected movement of these equipment, by the analysis integrated evaluation failure probability of PSA and consequence, evaluation result includes to equipment, electricity
The nuclear power station reactor core meltdown probability or nuclear power station radioactivity that cable, workshop, the influence consequence of regulation and these consequences ultimately cause
Substance discharges probability on a large scale.The nuclear power station reactor core meltdown probability or nuclear power station ultimately caused with event discharges probability work on a large scale
For the final evaluation index of nuclear power station fire safety evaluating comprehensive assessment.
The following are specific embodiments:
Embodiment 1
It is shown referring to attached drawing 6 and carries out the comprehensive assessment of nuclear power station fire safety evaluating for single in nuclear power station or several cable
Method, specifically: the equipment with the root cable or the beam cable, such cable connection is inquired according to the attribute information of cable,
It is needed using these equipment using the attribute information inquiry of equipment to class regulation, so that it is determined that these equipment are analyzed according to PSA
Obtained final security implication.
Embodiment 2
The method for carrying out the comprehensive assessment of nuclear power station fire safety evaluating for the hole in nuclear power station is shown referring to attached drawing 7, specifically:
According to the attribute information for the cable that the number inquiry in duct is passed through from the hole, further inquire and the root cable or the beam
The equipment of cable, such cable connection, and then needed using these equipment using the inquiry of the attribute information of equipment to class regulation,
So that it is determined that the final security implication that these equipment are analyzed according to PSA.
Embodiment 3
The method for carrying out the comprehensive assessment of nuclear power station fire safety evaluating for the cable testing bridge in nuclear power station, tool are shown referring to attached drawing 8
Body are as follows: the attribute information of the cable passed through from the gantry is inquired according to the number of cable testing bridge, further inquiry and the root
The equipment of cable or the beam cable, such cable connection, and then need to use these using the inquiry of the attribute information of equipment
Equipment gives class regulation, so that it is determined that the final security implication that these equipment are analyzed according to PSA.
Embodiment 4
The method for carrying out the comprehensive assessment of nuclear power station fire safety evaluating for the workshop in nuclear power station is shown referring to attached drawing 9, specifically:
The facility information for including in the workshop is inquired according to workshop number, and then needs to utilize this using the inquiry of the attribute information of equipment
A little equipment give class regulation, and determine the final security implication that these equipment are analyzed according to PSA.Alternatively, being compiled according to workshop
Number the cable information for including in the workshop is inquired, further inquires the root cable or the beam cable, such cable connection
Equipment, and then using the inquiry of the attribute information of equipment need to use these equipment to class regulation, and determine these equipment
The final security implication analyzed according to PSA.
Appraisal procedure of the invention integrates all information, can pass through the characteristic variations of certain point in nuclear power station
Its influence to nuclear power station integrality is solved, such as fire occurs for certain point, so that accurately evaluation is provided to its security implication,
Improve assessment accuracy and assessment efficiency.
The above embodiments merely illustrate the technical concept and features of the present invention, and its object is to allow person skilled in the art
Scholar cans understand the content of the present invention and implement it accordingly, and it is not intended to limit the scope of the present invention.It is all according to the present invention
Equivalent change or modification made by Spirit Essence, should be covered by the protection scope of the present invention.
Claims (10)
1. a kind of nuclear power station fire safety evaluating comprehensive estimation method, it is characterised in that: by the association in nuclear power station between distinct device
Mode is divided into process association, cable is associated with, regulation association is associated with workshop position, determines equipment, cable, the regulation in nuclear power plant
And the attribute information of workshop, common information included in its respective attribute information is integrated, difference is made by common information
It is interrelated between the attribute information of class, realize that the entirety of equipment, cable, workshop and regulation is associated with；Pass through equipment safety function
Relevant regulation treatment process determines all devices that different accident progress influence and the expected movement of these equipment, passes through
The analysis integrated evaluation failure probability of PSA and consequence, evaluation result include to equipment, cable, workshop, regulation influence consequence, with
And the nuclear power station reactor core meltdown probability that ultimately causes of these consequences or nuclear power station radioactive substance discharge probability on a large scale.
2. a kind of nuclear power station fire safety evaluating comprehensive estimation method according to claim 1, it is characterised in that: the attribute of cable
Information include type of cable, cable length, cable ends connection equipment, cable fire-proof characteristic, the fire load of cable, cable
The gantry number of the hole and cable passed through on the way.
3. a kind of nuclear power station fire safety evaluating comprehensive estimation method according to claim 2, it is characterised in that: the attribute of equipment
Information include security function, device location, equipment connection power and control cable, equipment safety function PSA analysis and
The process connection figure of system where equipment.
4. a kind of nuclear power station fire safety evaluating comprehensive estimation method according to claim 3, it is characterised in that: the attribute of regulation
Information includes the equipment that regulation is related to and the PSA analysis of the regulation treatment process.
5. a kind of nuclear power station fire safety evaluating comprehensive estimation method according to claim 4, it is characterised in that: the attribute of workshop
Information includes existing equipment, cable, hole and cable testing bridge in workshop.
6. a kind of nuclear power station fire safety evaluating comprehensive estimation method according to claim 5, it is characterised in that: pass through cable category
Location information, hole location information and gantry information acquisition endpoint device, hole and the electricity passed through of endpoint device in property information
Workshop location information belonging to cable gantry realizes being associated with for cable and equipment and cable and workshop position.
7. a kind of nuclear power station fire safety evaluating comprehensive estimation method according to claim 5, it is characterised in that: pass through equipment category
Property information in security function determine and used the regulation of the equipment, realize being associated with for equipment and regulation；Believed by device attribute
Device location in breath determines the workshop position where the equipment, and realization equipment is associated with workshop position；Pass through device attribute
In the power of equipment connection and being associated with for control cable realization equipment and connecting cable；By flow chart by equipment with and its lead to
The connected other equipment of system are crossed to be associated；The comprehensive assessment of nuclear power station fire safety evaluating is carried out by equipment safety function, is passed through
PSA assay fire incident severity degree.
8. a kind of nuclear power station fire safety evaluating comprehensive estimation method according to claim 5, it is characterised in that: pass through regulation
The equipment realization regulation that regulation is related in attribute information is associated with equipment, and the PSA analysis for passing through regulation treatment process carries out core
Power station fire safety evaluating comprehensive assessment.
9. a kind of nuclear power station fire safety evaluating comprehensive estimation method according to claim 1, it is characterised in that: PSA analysis with
Model is established based on equipment and regulation in nuclear power station, is established being associated between equipment and regulation, is commented using system reliability
Valence technology and probabilistic risk assessment technology are analyzed.
10. a kind of nuclear power station fire safety evaluating comprehensive estimation method according to claim 1, it is characterised in that: most with event
Nuclear power station reactor core meltdown probability or nuclear power station caused by end discharge probability as PSA on a large scale and evaluate the serious journey of fire incident consequence
The evaluation index of degree.
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112271008A (en) * | 2020-10-26 | 2021-01-26 | 岭澳核电有限公司 | Assessment method for nuclear power plant fire accident safe shutdown path |
| CN112349441A (en) * | 2020-10-27 | 2021-02-09 | 岭澳核电有限公司 | Safety processing method for cable fire misoperation of nuclear power plant |
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