CN101894595B - Fault detection method applied to nuclear power plant system - Google Patents

Fault detection method applied to nuclear power plant system Download PDF

Info

Publication number
CN101894595B
CN101894595B CN2010102088235A CN201010208823A CN101894595B CN 101894595 B CN101894595 B CN 101894595B CN 2010102088235 A CN2010102088235 A CN 2010102088235A CN 201010208823 A CN201010208823 A CN 201010208823A CN 101894595 B CN101894595 B CN 101894595B
Authority
CN
China
Prior art keywords
node
fault
nuclear power
power plant
plant system
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.)
Expired - Fee Related
Application number
CN2010102088235A
Other languages
Chinese (zh)
Other versions
CN101894595A (en
Inventor
刘瑞峡
杨新民
李明钢
蒋栋
卢宁
刘益群
杨浩
况德军
韩毅
黄云光
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China General Nuclear Power Corp
Daya Bay Nuclear Power Operations and Management Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Original Assignee
China General Nuclear Power Corp
Daya Bay Nuclear Power Operations and Management Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by China General Nuclear Power Corp, Daya Bay Nuclear Power Operations and Management Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN2010102088235A priority Critical patent/CN101894595B/en
Publication of CN101894595A publication Critical patent/CN101894595A/en
Application granted granted Critical
Publication of CN101894595B publication Critical patent/CN101894595B/en
Expired - Fee Related legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Landscapes

  • Testing And Monitoring For Control Systems (AREA)

Abstract

The invention relates to fault detection technology, and provides a fault detection method applied to a nuclear power plant system aiming at the defects of time consumption and labor consumption existing in fault clearance schemes of the conventional nuclear power plant systems. The method comprises the following steps of: setting a root node of a fault tree as an operating node; determining a possible fault node based on a logic gate for connecting the operating node and each sub-node and fault probability; acquiring operating parameters of equipment; judging whether the fault node is a bottom node of the fault tree when judging that fault exists in the equipment corresponding to the possible fault node according to fault conditions associated with the possible fault node and the operating parameters; if so, outputting the equipment which corresponds to the possible fault node and serves as a fault point; and otherwise, setting the possible fault node as the operating node and returning to the second step. The technical scheme provided by the invention completely automatically runs during the clearance of failed equipment, and the clearance speed is high, so the method can actually save time and labor.

Description

A kind of fault detection method that is applied to nuclear power plant system
Technical field
The present invention relates to fault detection technique, more particularly, relate to a kind of fault detection method that is applied to nuclear power plant system.
Background technology
The safe operation of nuclear power plant system is most important.
In actual application, in order to guarantee the safe operation of nuclear power plant system, power management unit has taked various measures necessary, so that when detecting operation troubles, can in time send alarm.Yet nuclear power plant system is very huge, even detect alarm, also need waste the part that great amount of time comes careful investigation to go wrong, and the investigation need of work calls numerous production divisions and together participates in.If alarm causes the power station out of service, the plenty of time that the problem of then investigating is wasted brings difficulty will inevitably for the power supply in relevant area.
Therefore, need a kind of fault detection method, can after detecting alarm, confirm the equipment that breaks down in the short period of time.
Summary of the invention
The technical matters that the present invention will solve is that the defective that takes time and effort to existing in the existing nuclear power plant system malfunction elimination scheme provides a kind of fault detection method that is applied to nuclear power plant system.
The technical solution adopted for the present invention to solve the technical problems is:
A kind of fault detection method that is applied to nuclear power plant system; Be used for after detecting indicating fault; Come the trouble spot in the definite kernel electric power station system based on fault tree, the different nodes in each of said fault tree layer are the distinct device in the corresponding said nuclear power plant system respectively, is connected through logic gate between each node and its child node; The pairing equipment of the child node of each node is positioned among the pairing equipment of this node, and each node is associated with at least one fault condition; Said method comprises:
The root node of S1, fault tree is set to running node;
S2, confirm the possible breakdown node based on the logic gate and the pairing probability of malfunction of each child node of attended operation node and each node thereof;
S3, the operational factor of gathering the pairing equipment of this possible breakdown node;
S4, according to this possible breakdown node related fault condition and this operational factor when judging that there is fault in the pairing equipment of this possible breakdown node; Judge whether this possible breakdown node is the bottom layer node of fault tree; If; Then export the pairing equipment of this possible breakdown node, with as said trouble spot; Otherwise this possible breakdown node is set to running node, gets back to step S2 then.
Wherein, the logic gate that connects each node and its child node be following one of them:
With door;
Or door;
Not gate;
Sheffer stroke gate;
After finding said trouble spot, said method also comprises:
Search the corresponding slip-stick artist's contact details in this trouble spot, to send the alarm notification that comprises this trouble spot relevant information.
In the fault detection method that is applied to nuclear power plant system provided by the invention, after finding said trouble spot, said method also comprises:
Search and export the corresponding solution information in this trouble spot.
In the fault detection method that is applied to nuclear power plant system provided by the invention, said bottom layer node is an apparatus card, and the father node of this bottom layer node is the rack that holds this apparatus card.
The technical scheme of embodiment of the present invention has following beneficial effect: technical scheme provided by the invention is set up the logical relation between the fault through making up fault tree.When detecting alarm, can come the operational factor of the equipment that automatic collection possibly break down by the logical relation in the fault tree, come automatic fault location equipment with this.This shows that technical scheme provided by the invention is operation fully automatically in the process of investigation faulty equipment, and investigation speed is fast, it is time saving and energy saving really to accomplish.
Description of drawings
To combine accompanying drawing and embodiment that the present invention is described further below, in the accompanying drawing:
Fig. 1 is the synoptic diagram according to the fault tree that is applied to nuclear power plant system of the present invention's one preferred embodiment;
Fig. 2 is the process flow diagram according to the fault detection method that is applied to nuclear power plant system of the present invention's one preferred embodiment;
Fig. 3 is the nuclear power station DCS system architecture synoptic diagram according to the use fault detection method of the present invention of the present invention's one preferred embodiment.
Embodiment
In order to make the object of the invention, technical scheme and advantage clearer,, the present invention is further elaborated below in conjunction with accompanying drawing and embodiment.Should be appreciated that specific embodiment described herein only in order to explanation the present invention, and be not used in qualification the present invention.
The invention provides a kind of fault detection method that is applied to nuclear power plant system, set up the logical relation between the fault through making up fault tree.When detecting alarm, can come the operational factor of the equipment that automatic collection possibly break down by the logical relation in the fault tree, come automatic fault location equipment with this.This shows that technical scheme provided by the invention is operation fully automatically in the process of investigation faulty equipment, and investigation speed is fast, it is time saving and energy saving really to accomplish.Just combine accompanying drawing and specific embodiment to come technical scheme provided by the invention is described in detail below.
Fig. 1 is the synoptic diagram according to the fault tree that is applied to nuclear power plant system 100 of the present invention's one preferred embodiment.As shown in Figure 1; Fault tree 100 is a multilayer number; Distinct device in the different nodes corresponding nuclear power plant systems of difference (being digitizing nuclear power station appearance control system) in its each layer; Be connected through logic gate between each node and its child node, the pairing equipment of the child node of each node is positioned among the pairing equipment of this node, and each node is associated with at least one fault condition.Each of said fault tree layer topological structure corresponding to nuclear power plant system.
The foundation of fault tree with nuclear power plant system for example the topological structure of DCS system be the basis, the topological structure of DCS system is the basis and the core of whole M ES system.The DCS system architecture is complicated, and the equipment that comprises is various, is in different levels, and system hierarchy for example is divided into the power station---unit---system---subsystem---POF---equipment---parts---subassembly, parts and the management of subassembly recurrence.Malfunctioning node will directly carry out related with different levels.
For example, node 1 corresponding nuclear power plant system, node 2 and corresponding racks 1 of node 3 difference and racks 2, the distinct device in node 4 and the corresponding rack 1 of node 5 difference, the distinct device in node 6 and the corresponding rack 2 of node 7 difference.Fault condition in the node 1 is the condition that nuclear power plant system breaks down; The condition that corresponding respectively rack 1 of fault condition in node 2 and the node 3 and rack 2 break down; The condition that distinct device breaks down in the corresponding respectively rack 1 of fault condition in node 4 and the node 5, the condition that distinct device breaks down in the corresponding respectively rack 2 of fault condition in node 6 and the node 7.
On the whole, all nodes of whole fault tree all are faults, and the fault that child node takes place is the failure cause that father node breaks down.
Logic gate between father node and the child node can be such as but not limited to and door or door, not gate, Sheffer stroke gate or the like.For example, with only being defined as when all child node corresponding equipment all break down of door, father node just can break down.Or the door be defined as when at least one child node corresponding equipment all breaks down, father node will break down.Inverter is used for expression when the child node corresponding equipment does not break down, and father node just breaks down.The function class of NOT-AND gate is similar to a kind of combination with door and not gate.Sheffer stroke gate is used for expression when one of child node does not break down at least, and father node just breaks down.
Fig. 2 is the process flow diagram according to the fault detection method that is applied to nuclear power plant system 200 of the present invention's one preferred embodiment.When nuclear power plant system breaks down, nuclear power plant system will send alarm prompt.After detecting alarm prompt, can carry out fault detect according to method shown in Figure 2.As shown in Figure 2, method 200 starts from step 202.
Subsequently, at next step 204, the root node of fault tree is set to running node.
Subsequently, at next step 206, confirm the possible breakdown node based on the logic gate and the pairing probability of malfunction of each child node of attended operation node and each node thereof.
In concrete implementation procedure, can be each child node corresponding probability of malfunction (for example empirical value) is set, when breaking down with the demonstration child node, the possibility that causes father node to break down.Be understood that when father node broke down, several node that its probability of malfunction is bigger were the possible breakdown node.In addition, when confirming the quantity of possible breakdown node, also need with reference to the logic gate that connects father node and child node.
Subsequently, at next step 208, gather the operational factor of the pairing equipment of this possible breakdown node.
Subsequently; At next step 210; According to this possible breakdown node related fault condition when judging that with this operational factor there is fault in the pairing equipment of this possible breakdown node, judge whether this possible breakdown node is the bottom layer node of fault tree, if; Then forward step 214 to, otherwise forward step 212 to.
The fault condition here is exactly failure criterion, is normal under which type of situation, under which type of situation, is unusual, the state when also being the pairing unit exception of node.For example suppose that a certain subset WV of DCS system is 220V, do not satisfy 220V so, think that then the voltage of this subset is unusual, so just can be with localization of fault in this subset.Certainly be merely example here, relatively more absolute, can fault condition be set according to different application scenarios and demand during practical operation.About operational factor, the parameter setting information when said operational factor is the corresponding device normal operation of node institute.Because each equipment all has the parameter of own normal operation; Such as power, temperature or the like; If against regulation numerical value can be thought and break down, utilize fault detection method of the present invention to go layer by layer to approach here; Finally find the fault rootstock node, come to solve rapidly and accurately fault according to the fault solution that provides.
As indicated above, if judge that in step 210 the possible breakdown node is the bottom layer node of fault tree, then forward step 214 to, export the pairing equipment of this possible breakdown node, with as the trouble spot, method 200 forwards step 216 to subsequently.
Subsequently, at next step 216, search the corresponding slip-stick artist's contact details in this trouble spot, to send the alarm notification that comprises this trouble spot relevant information, method 200 forwards step 218 to subsequently.
In concrete implementation procedure, can adopt such as but not limited to modes such as short message, the voice mail information that the trouble spot is relevant and send to the slip-stick artist who is responsible for this trouble spot maintenance job.
Subsequently, at next step 218, search and export the corresponding solution information in this trouble spot, method 200 forwards step 220 to subsequently.
In concrete implementation procedure, can generate fault solution information to each equipment in advance, be used for that ancillary works teacher keeps in repair this equipment when this equipment becomes the trouble spot.
It should be noted that step 216 and step 218 are optional step, and can not follow the described execution sequence of Fig. 2 between these two steps in concrete implementation procedure, promptly these two steps can adopt other order to carry out, such as but not limited to carrying out simultaneously.
As indicated above, if judge that in step 210 the possible breakdown node is not the bottom layer node of fault tree, then forward step 212 to, this possible breakdown node is set to running node, gets back to step 206 then.
At last, method 200 ends at step 220.
In concrete implementation procedure, method 200 after finding the trouble spot, the risk information that fault that can also the said trouble spot of analyzing and processing causes.In step 218, the solution information of output comprises the operation information of evading said risk, and the operation instruction information of handling the fault of said trouble spot.
In concrete implementation procedure, in order constantly to improve fault detection method, method 200 also need be stored the fault signature and the solution information of said trouble spot, so that upgrade and replenish the fault condition of each node in time.
Detection method of the present invention can also provide the platform of training and learning for the maintainer; Can set up the learning platform of fault detect and processing according to the fault signature and the solution information of said trouble spot; The maintainer can provide this learning platform to draw the experience of maintenance; Promote troubleshooting capability as soon as possible, for maintainer's training provides good training material.
In concrete implementation procedure, the primary element in general each equipment of corresponding nuclear power plant system of bottom layer node.When these primary elements break down, will cause chain-react, the node that is associated with this primary element in the nodes promptly at different levels all will break down, and cause root node also to break down the most at last.Therefore, when nuclear power plant system self sends alarm prompt (root node breaks down), can be according to the method for describing among Fig. 2 suspected fault reason successively, until finding the bottom layer node that breaks down.
Because in actual application, upper layer node is sent alarm prompt possibly mean that there is the fault possibility in a plurality of nodes of a plurality of lower floors that are subordinated to this upper layer node, therefore generally can be provided with the fault probability of happening of lower level node according to experience.So, in the investigation process, just can at first gather the operational factor of the higher node of fault probability of happening, judge with this whether it breaks down.Be understood that operation can be simplified workflow greatly like this.
Can know by method 200; Warning can be reported to the police by a plurality of sons and caused; And the father report to the police with the son warning between be connected with child warning criterion, the superiors are warning messages, are the basic reason of initiating failure at the bottom; And the centre all is the criterion information that comprises different levels, and its hierarchical structure possibly have the progression that how much differs according to system complex degree difference.When the father reported to the police generation, the criterion of reporting to the police according to which son under it was triggered, and just knew it is this son warning generation, in layer goed deep into, until the basic reason that navigates to fault.
In addition, in concrete implementation procedure, probability of malfunction and fault condition can be set according to concrete needs.
For example, if a plurality of racks of preliminary judgement among one of break down, then can the alarm lamp state on the rack lintel be detected, promptly gather the operational factor of rack lintel alarm lamp.If this alarm lamp is bright, then explanation is that this rack breaks down.Next, can judge the state of the child node of this rack, i.e. the state of the inner installed device of this rack.For example, based on logic gate between rack and its child node and the pairing probability of malfunction of each child node,, then can further detect the state of apparatus card alarm lamp in the rack if the apparatus card that the preliminary judgement fault goes out in rack is drawn out of.If this alarm lamp is bright, then explanation is that in a plurality of apparatus card at least one is drawn out of.In like manner, next can be further being determined to the end according to the state of each layer alarm lamp in the rack is that the apparatus card of which layer is drawn out of, thereby finally confirms bottom layer node, the apparatus card that promptly is drawn out of.
The present invention can gather failure message in real time and can locate apace and handling failure, and this is far-reaching for nuclear power plant system.Fast effective solution of fault can be avoided unnecessary loss for nuclear power station; And adopt detection method of the present invention that the platform of training and learning can also be provided for the maintainer; Can also good training material be provided according to the continuous renewal of Breakdown Maintenance experience of reality and the criterion in the additional fault testing method for new staffs training.
Fig. 3 is the nuclear power station DCS system architecture synoptic diagram according to the use fault detection method of the present invention of the present invention's one preferred embodiment.DCS system shown in Fig. 3 comprises operating terminal 1, operating terminal 2, processing unit, service unit, engineer station, diagnosis server, a plurality of subset ( subset 1,2,3,4).A plurality of operating terminals are connected through second network service with processing unit, service unit etc., and processing unit, service unit etc. is connected through first network service with a plurality of subsets; Examination and repair system is connected with second network service in the said DCS system through the 3rd network, is used for after detecting indicating fault positioning and to provide the fault solution information based on fault tree to the trouble spot of said DCS system.Wherein, Distinct device in the corresponding respectively said DCS of different nodes in each of the said fault tree layer system; Be connected through logic gate between each node and its child node; The pairing equipment of the child node of each node is positioned among the pairing equipment of this node, and each node is associated with at least one fault condition.Particular content is described in detail in Fig. 1-2.
Wherein, second network is such as but not limited to the TCP-IP link, and first network is such as but not limited to the industrial data net, and the 3rd network is such as but not limited to external network (any network that connects of can realizing communicating by letter all can use, for example LAN or wide area network).The type of network is not limited here, all be fine as long as can guarantee the network of nuclear power station DCS system normal operation.Examination and repair system is connected to second network through for example gateway 3 with fire wall, is merely example here, also can use other connected mode according to actual needs.
Here, subset is divided into ground floor level 1, processing unit, service unit, engineer station, diagnosis server etc. are divided into second layer level 2, the number of plies of the fault tree that relates among Fig. 2-3 is appreciated that level 1, the level 2 into here.Certainly, but about the also refinement of division of the concrete number of plies of fault tree, specific to a certain parts of a certain subset.Here be merely example.
Subset is such as but not limited to the nuclear power station genset; Also can be employed other special devices of nuclear power station; Subset can be directly connected on the communication network or be connected to network through gateway; For example subset 1 and 2 is directly connected to first network, and subset 3 and 4 is connected to first network through gateway 1 and 2.When subset or wherein parts break down, just can report layer by layer, last DCS system can provide indicating fault, and this indicating fault can be provided by the diagnosis server in the DCS system, also can be provided by other unshowned equipment.After detection system (MES) detects indicating fault; Will position and provide the fault solution to corresponding slip-stick artist to the trouble spot in the said DCS system according to fault tree, the slip-stick artist can or carry out handled at operating terminal according to the fault solution the engineer station.
Service unit among the figure or processing unit are the equipment that guarantees subset and the normal operation of DCS system, or the equipment of DCS system needs.Should be understood that the terminal shown in Figure 3 or the number of equipment are merely example, not as limitation of the present invention.
DCS system among Fig. 3 communicates by letter with examination and repair system and is connected, examination and repair system use the present invention for example the fault detection method among Fig. 1-2 the DCS system is carried out localization of fault and suitable fault solution is provided.Use fault detection method of the present invention, a certain rack or the parts that can be accurately break down in the location nuclear power station DCS system fast, and can localization of fault be shown with visual in image mode and be presented at (not shown) on the network topological diagram of DCS.For example zone 1 warning of breaking down; Then examination and repair system will according to above-mentioned fault detection method fault location equipment, thereby in layer go forward one by one the outstanding demonstration of regional 1 icon; After finally navigating to trouble unit, with outstanding show (such as but not limited to the red display) of trouble unit icon.Examination and repair system also can provide manual criterion except human machine interface graphics sign and automatic fault location are provided, combine automatically and manually, makes that the localization of fault of DCS equipment is more accurate.
Provide the concrete troubleshooting process instance of nuclear power station maintainer operation below:
1, event of failure explanation
* * * * * month * * day, * * divides master control the RGL001KA/RGL001AA warning to occur during * *, and field observation finds that the RDL1 plate sign of DB009 position in the L3RGL302AR cabinet shows fault.
2, venture analysis and measure
The RDL1 plate is that the position processing of RGL rod is relevant, because it transfers to AU two sub-systems with signal simultaneously, will lose SA2/H8 on the KIC after the fault, SC/E5, and SD1/G7, the measurement rod position of SD2/J5, master control will be remembered second group of I0.In the processing procedure; Will produce RGL001KA, RGL0006KA (insert and keep watch on), RGL008KA (room warning), RGL035KA (open alarm), also have the relevant warning SA rod of rod position step-out: RGL031KS, RGL032KS, RGL034KS, RGL0016KA SC rod: RGL041KS, RGL042KS, RGL044KS, RGL018KA SD rod: RGL046KS, RGL047KS, RGL049KS, RGL022KA.
3, work order (being the fault solution information)
1) discusses risk and measure with the related personnel.
2) and operation person risk is discussed, the checkout facility label is correct, should make again and polishing the label breakage.
3) work order, work permit are examined in strictness before the work, the field apparatus three is in full accord and carry out the signature affirmation.
Groundwork point: * * * *
Work responsible official signature: work guardian signature:
4) on-the-spot affirmation RDL1 plate fault, second group of I0 remembered in the operator notified master control; Do you how to confirm?
5) confirm that CCS-SU starts, otherwise with its startup.
6) land SU-client in the computer house, confirm not have this system in that other are unusual, otherwise report the higher level, propose the ticket processing.
7) take the corresponding label hurdle apart, put on the electrostatic prevention bracelet.
8) pull down the fault plate, more renew plate, please confirm consistent with plate comparison wire jumper and the switch changed.
9) confirm that plate installed fasteningly, go back to dress label hurdle.
10) wait for about 2 minutes, confirm that fault disappears.
11) on SIC4, remove warning.
12) the notice master control operator recovers, and eliminates second group of I0.
13) land SU-client in the computer house, confirming does not have other faults.
14) check result is fed back to the person in charge and coordinates.
15) site clearing, power cut-off.
16) read the instruction signature before the guardian works:
17) guardian's signature of completing:
Can know by above-mentioned treatment step; Handle the operation instruction information of the fault of said trouble spot, also being the slip-stick artist comprises the affirmation step again (confirming whether to also have other fault) after the operation steps of slip-stick artist's handling failure, the report step of processing procedure (report and coordinate with other related personnel to the higher level), fault are eliminated for the command information of eliminating this fault and need carrying out.
Should be understood that above-mentioned character string that relates to or code name are virtual hypothesis, are merely the usefulness of explanation, not as limitation of the present invention.For example RGL001KA/RGL001AA only is a code name of reporting to the police, and can use the method for any convenient sign that the indication of reporting to the police is distinguished.Other are also similar.SA2/H8, SC/E5, SD1/G7, SD2/J5 are the signs of measuring the rod position, are the code names of the physical unit in the nuclear power station DCS rod control system.This example is merely example, so that better understand scheme of the present invention.
The above is merely preferred embodiment of the present invention, not in order to restriction the present invention, all any modifications of within spirit of the present invention and principle, being done, is equal to and replaces and improvement etc., all should be included within protection scope of the present invention.

Claims (13)

1. fault detection method that is applied to nuclear power plant system; Be used for after detecting indicating fault; Come the trouble spot in the definite kernel electric power station system based on fault tree, the foundation of fault tree is the basis with the topological structure of nuclear power plant system, it is characterized in that; Different nodes in each of said fault tree layer are the distinct device in the corresponding said nuclear power plant system respectively; Be connected through logic gate between each node and its child node, the pairing equipment of the child node of each node is positioned among the pairing equipment of this node, and each node is associated with at least one fault condition; Said method comprises:
The root node of S1, fault tree is set to running node;
S2, confirm the possible breakdown node based on the logic gate and the pairing probability of malfunction of each child node of attended operation node and each node thereof;
S3, the operational factor of gathering the pairing equipment of this possible breakdown node;
S4, according to this possible breakdown node related fault condition and this operational factor when judging that there is fault in the pairing equipment of this possible breakdown node; Judge whether this possible breakdown node is the bottom layer node of fault tree; If; Then export the pairing equipment of this possible breakdown node, with as said trouble spot; Otherwise this possible breakdown node is set to running node, gets back to step S2 then;
The logic gate that wherein connects each node and its child node be following one of them: with door; Or door; Not gate; Sheffer stroke gate;
After finding said trouble spot, said method also comprises:
Search and export the corresponding solution information in this trouble spot.
2. the fault detection method that is applied to nuclear power plant system according to claim 1 is characterized in that, after finding said trouble spot, said method also comprises:
Search the corresponding slip-stick artist's contact details in this trouble spot, to send the alarm notification that comprises this trouble spot relevant information.
3. the fault detection method that is applied to nuclear power plant system according to claim 1 is characterized in that, said bottom layer node is an apparatus card, and the father node of this bottom layer node is the rack that holds this apparatus card.
4. according to each described fault detection method that is applied to nuclear power plant system of claim 1 ~ 3, it is characterized in that each of said fault tree layer topological structure corresponding to nuclear power plant system.
5. according to each described fault detection method that is applied to nuclear power plant system of claim 1 ~ 3, it is characterized in that the state when said fault condition is the pairing unit exception of node.
6. according to each described fault detection method that is applied to nuclear power plant system of claim 1 ~ 3, it is characterized in that the parameter setting information when said operational factor is the corresponding device normal operation of node institute.
7. the fault detection method that is applied to nuclear power plant system according to claim 2 is characterized in that, the corresponding solution information in said trouble spot is used in reference to and connects the fault that the slip-stick artist who receives alarm notification handles said trouble spot.
8. the fault detection method that is applied to nuclear power plant system according to claim 2 is characterized in that, said method also comprises:
The risk information that causes in the failure process of the said trouble spot of analyzing and processing.
9. the fault detection method that is applied to nuclear power plant system according to claim 8 is characterized in that said solution information comprises the operation information of evading said risk.
10. the fault detection method that is applied to nuclear power plant system according to claim 4 is characterized in that said solution information comprises the operation instruction information of the fault of handling said trouble spot.
11. the fault detection method that is applied to nuclear power plant system according to claim 10; It is characterized in that the operation instruction information of handling the fault of said trouble spot comprises the affirmation step again after report step, the fault of the operation steps of slip-stick artist's handling failure, processing procedure are eliminated.
12. the fault detection method that is applied to nuclear power plant system according to claim 2 is characterized in that, said method also comprises:
Store the fault signature and the solution information of said trouble spot, so that upgrade and replenish the fault condition of each node in time.
13. the fault detection method that is applied to nuclear power plant system according to claim 2 is characterized in that, said method also comprises:
Fault signature and solution information according to said trouble spot are set up the learning platform of fault detect and processing.
CN2010102088235A 2010-06-24 2010-06-24 Fault detection method applied to nuclear power plant system Expired - Fee Related CN101894595B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN2010102088235A CN101894595B (en) 2010-06-24 2010-06-24 Fault detection method applied to nuclear power plant system

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN2010102088235A CN101894595B (en) 2010-06-24 2010-06-24 Fault detection method applied to nuclear power plant system

Publications (2)

Publication Number Publication Date
CN101894595A CN101894595A (en) 2010-11-24
CN101894595B true CN101894595B (en) 2012-10-31

Family

ID=43103757

Family Applications (1)

Application Number Title Priority Date Filing Date
CN2010102088235A Expired - Fee Related CN101894595B (en) 2010-06-24 2010-06-24 Fault detection method applied to nuclear power plant system

Country Status (1)

Country Link
CN (1) CN101894595B (en)

Families Citing this family (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102298978A (en) * 2011-05-17 2011-12-28 哈尔滨工程大学 MFM (multilevel flow model)-based indeterminate fault diagnosis method for nuclear power plant for ship
CN102867556B (en) * 2011-07-08 2015-07-29 中广核工程有限公司 The fault handling method of nuclear power station DCS safety injection system Signal Fail and system
CN102360335B (en) * 2011-10-19 2014-11-19 北京广利核系统工程有限公司 Method for quantitatively evaluating value of security level DCS (Data Communication System) application software defect for nuclear power plant
CN102426862B (en) * 2011-11-17 2014-11-26 中广核工程有限公司 Modeling method for reliability of reactor-shutdown protecting signal in DCS (digitizer control system) and system
CN102760501B (en) * 2012-07-02 2015-02-25 华北电力大学 Methodfor troubleshooting of equipment in nuclear power plant
CN103744295A (en) * 2013-12-09 2014-04-23 武汉大学 Reliability analysis system based on GO-FLOW methodology
WO2016107587A1 (en) * 2014-12-31 2016-07-07 大亚湾核电运营管理有限责任公司 Comprehensive security response system and device for multi-unit nuclear power base
CN105118243A (en) * 2015-09-16 2015-12-02 上海核工程研究设计院 Portable alarm display system based on power plant dynamic data
CN106533754A (en) * 2016-11-08 2017-03-22 北京交通大学 Fault diagnosis method and expert system for college teaching servers
CN108573761A (en) * 2017-03-14 2018-09-25 中核核电运行管理有限公司 A kind of Nuclear Power Plant Equipment real-time performance monitoring method and system
US10467126B2 (en) 2017-03-31 2019-11-05 Microsoft Technology Licensing, Llc Scenarios based fault injection
CN107707408B (en) * 2017-10-20 2020-08-14 杭州杭淳广播电视设备有限公司 Remote monitoring method and system for digital broadcast transmitter
CN109192339B (en) * 2018-07-23 2021-01-15 广东核电合营有限公司 Method and device for diagnosing state of generator of million-kilowatt pressurized water reactor nuclear power station and terminal equipment
CN110517369B (en) * 2019-08-23 2021-04-23 中国航空无线电电子研究所 Fault tree construction method and system based on mind map
CN110493066A (en) * 2019-09-04 2019-11-22 山东钢铁股份有限公司 Substation's background monitoring communications trouble shoot method
CN111901156B (en) * 2020-07-09 2024-02-13 腾讯科技(深圳)有限公司 Method and device for monitoring faults
CN113421670B (en) * 2021-06-18 2022-05-13 中国核动力研究设计院 Nuclear power plant accident regulation quantitative analysis method and system
CN115102828A (en) * 2022-08-26 2022-09-23 歌尔股份有限公司 Fault analysis method and device

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5305426A (en) * 1991-05-15 1994-04-19 Kabushiki Kaisha Toshiba Plant operation support system for diagnosing malfunction of plant
JP2002024337A (en) * 2000-07-10 2002-01-25 Toshiba Corp Risk analysis supporting method, and storage medium
CN101217064A (en) * 2007-12-27 2008-07-09 大亚湾核电运营管理有限责任公司 A fatal accident disposal for improved type gigawatt-level PWR nuclear power plant
TW201017686A (en) * 2008-10-17 2010-05-01 Iner Aec Executive Yuan Fault tree analysis system for the instrument control process for nuclear power plant with advanced boiling water reactor background
CN101710400A (en) * 2009-12-15 2010-05-19 中科华核电技术研究院有限公司 Method and device for evaluating risk of nuclear power station

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH07200981A (en) * 1993-12-28 1995-08-04 Toshiba Corp Reliability evaluating method for plant and update evaluating method therefor

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5305426A (en) * 1991-05-15 1994-04-19 Kabushiki Kaisha Toshiba Plant operation support system for diagnosing malfunction of plant
JP2002024337A (en) * 2000-07-10 2002-01-25 Toshiba Corp Risk analysis supporting method, and storage medium
CN101217064A (en) * 2007-12-27 2008-07-09 大亚湾核电运营管理有限责任公司 A fatal accident disposal for improved type gigawatt-level PWR nuclear power plant
TW201017686A (en) * 2008-10-17 2010-05-01 Iner Aec Executive Yuan Fault tree analysis system for the instrument control process for nuclear power plant with advanced boiling water reactor background
CN101710400A (en) * 2009-12-15 2010-05-19 中科华核电技术研究院有限公司 Method and device for evaluating risk of nuclear power station

Non-Patent Citations (4)

* Cited by examiner, † Cited by third party
Title
周春娟.基于故障树的反应堆故障诊断及在报警系统中的应用.《中国优秀硕士学位论文全文数据库》.2010, *
周春娟等.FTA在核电站超压保护系统故障诊断中的应用.《微型电脑应用》.2009,第25卷(第8期), *
陈兆兵等.核电系统的故障树可靠性定量分析数字仿真.《计算机仿真》.2005,第22卷(第10期), *
陈浩等.核电厂故障检测与报警系统的发展概况.《原子能科学技术》.2000,第34卷(第6期), *

Also Published As

Publication number Publication date
CN101894595A (en) 2010-11-24

Similar Documents

Publication Publication Date Title
CN101894595B (en) Fault detection method applied to nuclear power plant system
CN110011829B (en) Comprehensive airborne task system health management subsystem
CN101255950A (en) Intelligent warning system for computation and pipe monitoring of oil transportation collection and transmission system
CN108909773A (en) A kind of signalling arrangement comprehensive analysis of fault system
CN105279919A (en) Electricity utilization information acquiring system
CN112487119B (en) Power failure early warning signal verification method and system
CN110159929A (en) Subdrainage pipe network intelligently manages big data processing method
CN109588763A (en) Detect alarm system in glue position applied to ZJ112 cigarette machine
CN115393142A (en) Intelligent park management method and management platform
KR102517384B1 (en) Smart platform for explosion proof inspection at industrial sites
CN104076808A (en) Fault diagnosis system and method for industrial control equipment
CN113761234A (en) Method and device for routing inspection of equipment in hydraulic power plant, electronic equipment and storage medium
CN105891679A (en) Fault detection system and method for electric power grid
CN114137302A (en) Monitoring system for whole verification process of electric energy metering device
JP2018185774A (en) Facility management apparatus, facility management system, program and facility management method
CN101414737A (en) Control method and system for track traffic electric power data acquisition and surveillance
CN115980062A (en) Industrial production line whole-process vision inspection method based on 5G
CN109521314A (en) A kind of steam-electric power plant remote fault diagnosis method
CN214784393U (en) Intelligent operation and maintenance system for airport water supply pipe network
CN101169872A (en) System and method for monitoring patrol personnel for outdoor display screen
CN114896096A (en) Data center equipment fault prediction system and method based on image recognition algorithm
CN204166669U (en) Be applied to the wireless self-networking data acquisition module of cable shaft early warning
CN112731857A (en) Online monitoring system and monitoring method for running state of environmental protection equipment
KR101651063B1 (en) Apparatus and Method for Remote Monitoring Based on the Recognizing Position using Smart Device
CN114615344B (en) Intelligent protocol conversion method and device for electric power instrument

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
C14 Grant of patent or utility model
GR01 Patent grant
ASS Succession or assignment of patent right

Owner name: CHINA GENERAL NUCLEAR GROUP CO., LTD.

Free format text: FORMER OWNER: DAYAWAN NUCLEAR POWER RUNNING MANAGEMENT CO., LTD.

Effective date: 20141028

Owner name: GUANGDONG NUCLEAR POWER JOINT CO., LTD.

Free format text: FORMER OWNER: CHINA GENERAL NUCLEAR GROUP CO., LTD.

Effective date: 20141028

C41 Transfer of patent application or patent right or utility model
C56 Change in the name or address of the patentee

Owner name: CHINA GENERAL NUCLEAR GROUP CO., LTD.

Free format text: FORMER NAME: CHINA GUANGDONG NUCLEAR POWER GROUP CO., LTD.

CP01 Change in the name or title of a patent holder

Address after: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city in Guangdong province 518031 17-19 floor

Patentee after: CHINA GENERAL NUCLEAR POWER Corp.

Patentee after: DAYABAY NUCLEAR POWER OPERATIONS AND MANAGEMENT Co.,Ltd.

Address before: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city in Guangdong province 518031 17-19 floor

Patentee before: CHINA GUANGDONG NUCLEAR POWER GROUP Co.,Ltd.

Patentee before: DAYABAY NUCLEAR POWER OPERATIONS AND MANAGEMENT Co.,Ltd.

TR01 Transfer of patent right

Effective date of registration: 20141028

Address after: 518031 Guangdong city of Shenzhen province Futian District science and technology building, Shangbu Road 15

Patentee after: GUANGDONG NUCLEAR POWER JOINT VENTURE Co.,Ltd.

Patentee after: CHINA GENERAL NUCLEAR POWER Corp.

Address before: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city in Guangdong province 518031 17-19 floor

Patentee before: CHINA GENERAL NUCLEAR POWER Corp.

Patentee before: DAYABAY NUCLEAR POWER OPERATIONS AND MANAGEMENT Co.,Ltd.

CF01 Termination of patent right due to non-payment of annual fee

Granted publication date: 20121031

CF01 Termination of patent right due to non-payment of annual fee