CN109521751A - A kind of nuclear power plant's key work center method failure mitigation method - Google Patents
A kind of nuclear power plant's key work center method failure mitigation method Download PDFInfo
- Publication number
- CN109521751A CN109521751A CN201811236704.3A CN201811236704A CN109521751A CN 109521751 A CN109521751 A CN 109521751A CN 201811236704 A CN201811236704 A CN 201811236704A CN 109521751 A CN109521751 A CN 109521751A
- Authority
- CN
- China
- Prior art keywords
- work center
- key work
- equipment
- center method
- 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.)
- Pending
Links
Classifications
-
- G—PHYSICS
- G05—CONTROLLING; REGULATING
- G05B—CONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
- G05B23/00—Testing or monitoring of control systems or parts thereof
- G05B23/02—Electric testing or monitoring
- G05B23/0205—Electric testing or monitoring by means of a monitoring system capable of detecting and responding to faults
- G05B23/0218—Electric testing or monitoring by means of a monitoring system capable of detecting and responding to faults characterised by the fault detection method dealing with either existing or incipient faults
- G05B23/0224—Process history based detection method, e.g. whereby history implies the availability of large amounts of data
Abstract
The invention belongs to Nuclear Power Plant Equipment reliability management technical fields, and in particular to a kind of nuclear power plant's key work center method failure mitigation method.At this stage, nuclear power station shutdown shutdown event is caused by plant issue mostly, it is therefore desirable to be established an equipment dependability analysis and management platform, be carried out key-point management to key work center method.The method specifically includes following steps: Step 1: determining key work center method inventory according to Nuclear Power Plant Equipment principle of grading；Step 2: according to boundary demarcation component list；Step 3: identification key work center method；Step 4: carrying out the analysis of key work center method mitigation strategy for sensing unit；Step 5: mitigation strategy analysis result and corresponding correct action plan.The present invention alleviates key work center method failure, that is, is the reduction of and shuts down shutdown event, ensured the safe and reliable operation of nuclear power generating equipment.
Description
Technical field
The invention belongs to Nuclear Power Plant Equipment reliability management technical fields, and in particular to a kind of nuclear power plant pass based on ERDB
The alleviation method of key sensitive equipment management.
Background technique
Nuclear power is a kind of cleaning, efficient, good modern energy.Ended for the end of the year 2017, China occupies generation building nuclear power quantity
Boundary is the first.While improving the energy for the national economic development, safety more can not be ignored nuclear power.Nuclear power station is a height
Complicated system.Nuclear safety requires to ensure that nuclear power station does not occur to make the reason of any technology, due to thinking with natural calamity
At accident unacceptable radiological hazard is caused to staff, the public and environment, it is therefore necessary to reinforcement persistently keep core
The safe and reliable operation in power station and equipment.
Between 2012-2013, Chinese Nuclear Power repeatedly organizes seminar to promote the reliability of Chinese Nuclear Power operating unit, passes through
Analysis finds that the shutdown shutdown event due to caused by plant issue has accounted for the 87% of total event, people because and external event account for
13%；Since plant issue causes capability facfor penalty values average 2% or so.Therefore, National nuclear power Planning of China is by mentioning comprehensively
Equipment reliability management is risen to improve the safety and reliability of unit.
It is operated for better support equipment reliability management system and operation flow, proposes to build by information-based means
Vertical one equipment management reliability management basic database based on industry historical data and to run each power plant based on center real-time
The dynamic data base of data establishes shared equipment dependability analysis and management platform, i.e. " Chinese Nuclear Power equipment reliability management
Database (ERDB) " construction project.
Key work center method module is established based on ERDB platform, key work center method refers to that individual equipment failure can be led
It sends a telegraph station shutdown, shutdown, drop power, the equipment that power fluctuates widely, abbreviation SPV equipment.Alleviate key work center method event
Barrier is the reduction of and shuts down shutdown event, ensured the safe and reliable operation of nuclear power generating equipment.
Summary of the invention
The alleviation side for nuclear power plant's key work center method management failure based on ERDB that the purpose of the present invention is to provide a kind of
Method alleviates key work center method, reduces the risk for shutting down shutdown, improves power station equipment reliability.
Technical scheme is as follows:
1. a kind of nuclear power plant's key work center method failure mitigation method, specifically comprises the following steps:
Step 1: determining key work center method inventory according to Nuclear Power Plant Equipment principle of grading:
Step 1.1 collects drawing, including system flow chart, electric hookup, instrument control logic chart；
Step 1.2 collects design document, including system design manual, Technical specification, design specification book；
Step 1.3 collects preventative maintenance history, enumerates the preventative maintenance project that statistics was done, and historical record is gone forward side by side
Row is sorted out；
Step 1.4 collects defect maintenance history, enumerates and counts all corrective maintenance item that the equipment generated in recent years
Mesh；
Step 1.5 collects inside and outside Experience Feedback, shuts down shutdown event description.
2. Step 2: according to boundary demarcation component list:
The boundary that step 2.1, SPV equipment sensing unit identify should include that the electrical control of SPV equipment itself, the equipment is returned
Road, instrument measurement circuit, protective loop, interlock circuit, auxiliary system are part or all of；Specifically define side in accordance with the following methods
Boundary:
(1) electric control loop component: generally assuming that control power supply and electrical source of power are all available, usually supply power supply
Breaker be included in boundary, but bus is not included；
(2) instrument and the relevant circuit element of control: general entire instrument circuit is included in boundary, even if its output
It may be sent to other than analysis boundary；
(3) ancillary system components: dedicated ancillary system components are generally all included in boundary, and other auxiliary systems such as press sky,
It generally assumes that and is all available, consider only to consider that the solenoid valve of supply gas source is included in boundary when system boundary；
Step 2.2, according to identified analysis boundary, the component list in all boundaries is listed, even if the component is existing
Device coding is also required to be included in the inventory and be analyzed again.
3. step 3: identification key work center method:
Step 3.1, the fault mode and trouble location for finding out crucial sensing unit；
Step 3.2, the bill of materials for forming key work center method；
Step 3.3, the sensing unit that the equipment is identified using the method for fault mode evaluation influence or fault tree.
4. Step 4: carrying out the analysis of key work center method mitigation strategy for sensing unit:
Step 4.1, operation are alleviated: operation mitigation strategy pays close attention to the operation of system or equipment；By changing operation side
Formula, operation/administration Isolation Management, additional operation, which are intervened the risk of action reduction key work center method equipment fault or alleviated, closes
The consequence of key sensitive equipment failure；
Step 4.2, maintenance are alleviated: the preventative maintenance strategy and maintenance instruction for paying close attention to key work center method improve；
Examine that all potential fault modes of confirmation key work center method identification all have been subjected to assessment, while it is big to verify preventative maintenance
Corresponding alleviation task is established in guiding principle as needed；
Step 4.3, isolation are alleviated: being physically isolated by scene setting, to prevent key work center method from accidentally being touched, steaming by personnel
The hot environments such as vapour or fluid miss unanticipated action caused by spray and possible missile caused by leaking；By to crucial quick
The inspection of device context actual state is felt to determine the Necessity and feasibility being physically isolated；
Step 4.4, technology are alleviated: according to identified failure or degradation mechanism, examining and improve performance monitoring scheme, such as shape
State monitoring and prospective maintenance, routine test, operation inspection, maintenance personal and Facilities Engineer's inspection, As-found；If closed
Key sensitive equipment risk fails to be effectively relieved by other mitigation strategies, or if can pass through a kind of economic, feasible design
Change is permanent to eliminate key work center method risk, then considers design alteration.
5. Step 5: mitigation strategy analysis result and corresponding correct action plan:
Relevant departments are organized to be examined as needed by equipment management responsible department, corresponding item typing management of taking action is supported
System carries out tracing management；There is the case where apparent performance degradation in SPV device fails, then examine SVP equipment again
Mitigation strategy analysis.
Detailed description of the invention
Fig. 1 equipment alleviates process
Fig. 2 Fault Tree Analysis identifies component cooling pump sensing unit
Specific embodiment
The present invention will be described in detail in the following with reference to the drawings and specific embodiments:
Step 1 collects related data
Step 1.1, drawing, including system flow chart, electric hookup, instrument control logic chart；
Step 1.2, design document, including system design manual, Technical specification, design specification book etc.；
Step 1.3, preventative maintenance history, enumerate which preventative maintenance project was statistics did, and historical record simultaneously carries out
Sort out；
Step 1.4, defect maintenance history are enumerated and count all corrective maintenance items that the equipment generated in recent years；
Step 1.5 collects inside and outside Experience Feedback, shuts down shutdown event description.
Step 2, according to boundary demarcation component list
The boundary that step 2.1, SPV equipment sensing unit identify should include that the electrical control of SPV equipment itself, the equipment is returned
Road, instrument measurement circuit, protective loop, interlock circuit, auxiliary system are part or all of；Specifically define side in accordance with the following methods
Boundary:
(1) electric control loop component: generally assume that control power supply and electrical source of power are all available.Usually supply power supply
Breaker be included in boundary, but bus is not included；
(2) instrument and the relevant circuit element of control: general entire instrument circuit is included in boundary, even if its output
It may be sent to other than analysis boundary；
(3) ancillary system components: dedicated ancillary system components are generally all included in boundary, other auxiliary systems (as empty in pressed)
It generally assumes that and is all available, consider only to consider that the solenoid valve of supply gas source is included in boundary when system boundary.
Step 2.2, according to identified analysis boundary, the component list in all boundaries is listed, if the component is existing
Device coding (being included in equipment management) is also required to be included in the inventory and be analyzed again.
Step 3, identification sensing unit
Step 3.1, according to failure mode and effect analysis as a result, finding out the sensing unit for leading to the equipment fault.
Step 3.1.1, modular construction, bonded block operating condition feature in systems and component fault mode: are directed to
Theoretically existing fault mode determines the fault mode that component may occur, can for the fault mode of excessive small probability
Without analysis.Do not consider to generate simultaneously during design, manufacture etc. due to component itself when the fault mode of equipment determines
The genetic defects or deficiency left.For component itself there are genetic defects or deficiency, power plant should pass through repairing, replacement or change
Etc. means eliminate these genetic defects or deficiency, rather than the component is managed by the susceptibility of lifting component.
Step 3.1.2, failure effect analysis (FEA): obtaining the possible fault mode of each component for analysis, analyzes and determines and is each
Influence degree of the fault mode to the SPV functions of the equipments.
Step 3.1.3, according to the impact analysis of unit failure as a result, the result being classified in conjunction with the SPV functions of the equipments.
Step 3.2 finds out the sensing unit for leading to the equipment fault according to Fault Tree Analysis.Fault Tree Analysis
It carries out sensing unit identification and is mainly used for logic control system.As shown in Figure 2.
Step 3.2.1 determines top event, such as shutdown, halt turbines, generator outage, transformer tripping, main pump tripping
Deng.
Step 3.2.2 is listed and is threaded off caused by the trip signal for causing top event to occur, including malfunction, error signal.
Step 3.2.3 analyzes these trip signal Producing reasons, and analyses in depth layer by layer, until find it is replaceable most
Small parts.Dual and multiple failure leads to top event, and there is a situation where not in SPV range.
Step 4, mitigation strategy analysis
It is eliminated, SPV failure risk can be reduced to extremely low by SPV.But due to cost or complexity can not in time,
SPV is reasonably eliminated, then should just consider to take a possibility that SPV mitigation strategy is to reduce shutdown/shutdown.This mitigation strategy
Method is alleviated in terms of technology, maintenance, operation, isolation four.
Step 4.1, technology are alleviated
Step 4.1.1, preventative maintenance is alleviated: describing to alleviate the prevention of component SPV fault mode generation by front
Property maintenance task requirement compare outline task, producer ties up suggestion, existing PMT template in advance as the foundation compared with outline,
For the modified content of the clear outline of comparing result.
Step 4.1.2, test after repairing: rear testing regulations is repaired in examination, it is ensured that is had specific acceptance criteria and is met component and sets
Standby technical requirements form the correct action for repairing rear testing regulations modification if being unsatisfactory for.
Step 4.1.3, performance monitoring: whether there is performance monitoring means to find the fault mode in time, monitored as without if
Means propose recommendation on improvement, clearly improvement content, including which file are modified, and the contents such as how to modify, if being related to change
Change request please be describe.
Step 4.1.4, quality controls: the work that clear maintenance relevant to the SPV fault mode needs to pay close attention to
Make content, the requirement including quality control aspect, there are data should be understood that control parameter and required value, such as tolerance, gap, torque
Deng.It is compared with the quality requirement in maintenance instruction, confirms whether the acceptable quality level in quality planning process requires clear, and
Whether meet with regulatory requirements (acceptance requirement), if do not met, proposes modification item.
Step 4.2, maintenance are alleviated
Step 4.2.1, maintenance instruction: whether analysis and maintence regulation prescribed requirement covers in outline to SPV fault mode
Content is repaired, fills in " document is complete " if satisfaction, fills in that " content is not complete if being unsatisfactory for；For SPV fault mode
Whether relevant maintenance needs specific maintenance acceptance index in inspection procedure specification, and whether maintenance standard is complete in regulation,
Whether meet with the requirement of equipment or component, acceptance index such as: whether torque, gap, dimensional tolerance have defined, if met
It then fills in and " meets the requirements, see regulation XXX ", " be unsatisfactory for requiring, require supplementation with XXXX ", if necessary if conditions are not met, filling in
Modification is unified to rise version regulation.
Step 4.2.1, repair inspection: according to the performance monitoring of this equipment and component require, as maintenance inspection requirement,
Can also rule of thumb, whether maintenance and inspection polling period content meets the requirements, and is such as unsatisfactory for requiring to rise version maintenance patrol record.
Step 4.3, operation are alleviated
Operation mitigation strategy pays close attention to the operation of system or equipment.By changing the method for operation, operation/administration isolated tube
Reason, additional operation intervene the means such as action and reduce the risk of SPV equipment fault or alleviate the consequence of SPV failure.Disconnected component goes out
When existing SPV fault mode, if having operation intervention means to carry out the prevention or alleviation of SPV consequence, such as without proposing modification fortune
Professional etiquette journey.
Step 4.4, isolation are alleviated
Be physically isolated by scene setting, come prevent SPV equipment from accidentally being touched by personnel, the hot environments such as steam or fluid leakage
Caused by accidentally unanticipated action etc. caused by spray and possible missile.This is needed by SPV device context actual state
Inspection to determine the Necessity and feasibility being physically isolated.Be physically isolated to implement on existing utility as far as possible, such as by electric instrument
Control cabinet door locking, room door locking etc. modes, if to increase additional entities isolation facility, should by design alteration process into
Row assessment, has an adverse effect to equipment to avoid increased facility.
The triggering of step 5, mitigation strategy
There is the case where apparent performance degradation in SPV device fails, it is also necessary to examine that SVP equipment alleviates plan again
Slightly analyze.
Implementation method of the invention is elaborated above in conjunction with embodiment, but the present invention is not limited to above-mentioned realities
Example is applied, it within the knowledge of a person skilled in the art, can also be without departing from the purpose of the present invention
Various changes can be made.The content that description in the present invention is not described in detail can use the prior art.
Claims (6)
1. a kind of nuclear power plant's key work center method failure mitigation method, characterized by the following steps:
Step 1: determining key work center method inventory according to Nuclear Power Plant Equipment principle of grading；
Step 2: according to boundary demarcation component list；
Step 3: identification key work center method；
Step 4: carrying out the analysis of key work center method mitigation strategy for sensing unit；
Step 5: mitigation strategy analysis result and corresponding correct action plan.
2. a kind of nuclear power plant's key work center method failure mitigation method as described in claim 1, it is characterised in that: the step
Rapid one, specifically comprise the following steps:
Step 1.1 collects drawing, including system flow chart, electric hookup, instrument control logic chart；
Step 1.2 collects design document, including system design manual, Technical specification, design specification book；
Step 1.3 collects preventative maintenance history, enumerates the preventative maintenance project that statistics was done, and historical record is simultaneously returned
Class；
Step 1.4 collects defect maintenance history, enumerates and counts all corrective maintenance items that the equipment generated in recent years；
Step 1.5 collects inside and outside Experience Feedback, shuts down shutdown event description.
3. a kind of nuclear power plant's key work center method failure mitigation method as described in claim 1, it is characterised in that: the step
Rapid two, specifically comprise the following steps:
Step 2.1, SPV equipment sensing unit identification boundary should include SPV equipment itself, the equipment electric control loop,
Instrument measurement circuit, protective loop, interlock circuit, auxiliary system are part or all of；Specifically define boundary in accordance with the following methods:
(1) electric control loop component: generally assuming that control power supply and electrical source of power are all available, and usually supplies the disconnected of power supply
Road device is included in boundary, but bus is not included；
(2) instrument and the relevant circuit element of control: general entire instrument circuit is included in boundary, even if its output may
It is sent to other than analysis boundary；
(3) ancillary system components: dedicated ancillary system components are generally all included in boundary, and other auxiliary systems such as press sky, generally
Assuming that being all available, consider only to consider that the solenoid valve of supply gas source is included in boundary when system boundary；
Step 2.2, according to identified analysis boundary, the component list in all boundaries is listed, even if the component existing device
Coding is also required to be included in the inventory to be analyzed again.
4. a kind of nuclear power plant's key work center method failure mitigation method as described in claim 1, it is characterised in that: the step
Rapid three, specifically comprise the following steps:
Step 3.1, the fault mode and trouble location for finding out crucial sensing unit；
Step 3.2, the bill of materials for forming key work center method；
Step 3.3, the sensing unit that the equipment is identified using the method for fault mode evaluation influence or fault tree.
5. a kind of nuclear power plant's key work center method failure mitigation method as described in claim 1, it is characterised in that: the step
Rapid four, specifically comprise the following steps:
Step 4.1, operation are alleviated: operation mitigation strategy pays close attention to the operation of system or equipment；By changing the method for operation, fortune
Row/administrative Isolation Management, additional operation intervene action and reduce the risk of key work center method equipment fault or alleviate crucial quick
Feel the consequence of equipment fault；
Step 4.2, maintenance are alleviated: the preventative maintenance strategy and maintenance instruction for paying close attention to key work center method improve；It examines
All potential fault modes of confirmation key work center method identification all have been subjected to assessment, while verifying in preventive maintaining outline
Corresponding alleviation task is established as needed；
Step 4.3, isolation are alleviated: be physically isolated by scene setting, come prevent key work center method from accidentally being touched by personnel, steam etc.
Hot environment or fluid miss unanticipated action caused by spray and possible missile caused by leaking；By being set to crucial sensitivity
The inspection of standby scene actual state is to determine the Necessity and feasibility being physically isolated；
Step 4.4, technology are alleviated: according to identified failure or degradation mechanism, examining and improve performance monitoring scheme, as state is supervised
It surveys and prospective maintenance, routine test, operation inspection, maintenance personal and Facilities Engineer's inspection, As-found；If crucial quick
Sense equipment Risk fails to be effectively relieved by other mitigation strategies, or if can pass through a kind of economic, feasible design alteration
It is permanent to eliminate key work center method risk, then consider design alteration.
6. a kind of nuclear power plant's key work center method failure mitigation method as described in claim 1, it is characterised in that: the step
Rapid five, specifically comprise the following steps:
Relevant departments are organized to be examined as needed by equipment management responsible department, corresponding item typing Administrative Support System processing of taking action
Carry out tracing management；There is the case where apparent performance degradation in SPV device fails, then examine that SVP equipment is alleviated again
Analysis of strategies.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811236704.3A CN109521751A (en) | 2018-10-23 | 2018-10-23 | A kind of nuclear power plant's key work center method failure mitigation method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811236704.3A CN109521751A (en) | 2018-10-23 | 2018-10-23 | A kind of nuclear power plant's key work center method failure mitigation method |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN109521751A true CN109521751A (en) | 2019-03-26 |
Family
ID=65772831
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811236704.3A Pending CN109521751A (en) | 2018-10-23 | 2018-10-23 | A kind of nuclear power plant's key work center method failure mitigation method |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN109521751A (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110941255A (en) * | 2019-12-05 | 2020-03-31 | 中国航发贵阳发动机设计研究所 | Fault information management system |
| CN110972405A (en) * | 2019-11-29 | 2020-04-07 | 苏州热工研究院有限公司 | Method and device for preventing silver ion electromigration of nuclear-grade circuit board of nuclear power plant |
| CN111553061A (en) * | 2020-04-17 | 2020-08-18 | 苏州热工研究院有限公司 | Nuclear power plant typhoon emergency response and early warning device and construction method thereof |
| CN111950744A (en) * | 2020-07-27 | 2020-11-17 | 福建福清核电有限公司 | On-site operation safety control method and system |
| CN114091237A (en) * | 2021-10-20 | 2022-02-25 | 中核核电运行管理有限公司 | Method for identifying key sensitive equipment of digital reactor protection system |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN101968864A (en) * | 2010-11-17 | 2011-02-09 | 山东电力研究院 | Electric power system operation reliability-centered equipment importance evaluation method |
| CN103745293A (en) * | 2013-11-27 | 2014-04-23 | 苏州热工研究院有限公司 | RCM analysis method |
| CN108256713A (en) * | 2016-12-29 | 2018-07-06 | 中核核电运行管理有限公司 | Nuclear power plant system measure of supervision based on ERDB |
| CN108268981A (en) * | 2016-12-29 | 2018-07-10 | 中核核电运行管理有限公司 | A kind of Nuclear Power Plant Equipment grading management method |
-
2018
- 2018-10-23 CN CN201811236704.3A patent/CN109521751A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN101968864A (en) * | 2010-11-17 | 2011-02-09 | 山东电力研究院 | Electric power system operation reliability-centered equipment importance evaluation method |
| CN103745293A (en) * | 2013-11-27 | 2014-04-23 | 苏州热工研究院有限公司 | RCM analysis method |
| CN108256713A (en) * | 2016-12-29 | 2018-07-06 | 中核核电运行管理有限公司 | Nuclear power plant system measure of supervision based on ERDB |
| CN108268981A (en) * | 2016-12-29 | 2018-07-10 | 中核核电运行管理有限公司 | A kind of Nuclear Power Plant Equipment grading management method |
Non-Patent Citations (2)
| Title |
|---|
| 陈杰等: "《核电厂关键敏感设备管理创新与实践》", 《发电运维》 * |
| 高立刚等: "《大亚湾核电站设备管理体系创新》", 《工业工程与管理》 * |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110972405A (en) * | 2019-11-29 | 2020-04-07 | 苏州热工研究院有限公司 | Method and device for preventing silver ion electromigration of nuclear-grade circuit board of nuclear power plant |
| CN110941255A (en) * | 2019-12-05 | 2020-03-31 | 中国航发贵阳发动机设计研究所 | Fault information management system |
| CN110941255B (en) * | 2019-12-05 | 2023-11-24 | 中国航发贵阳发动机设计研究所 | Fault information management system |
| CN111553061A (en) * | 2020-04-17 | 2020-08-18 | 苏州热工研究院有限公司 | Nuclear power plant typhoon emergency response and early warning device and construction method thereof |
| CN111950744A (en) * | 2020-07-27 | 2020-11-17 | 福建福清核电有限公司 | On-site operation safety control method and system |
| CN114091237A (en) * | 2021-10-20 | 2022-02-25 | 中核核电运行管理有限公司 | Method for identifying key sensitive equipment of digital reactor protection system |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109521751A (en) | A kind of nuclear power plant's key work center method failure mitigation method | |
| CN102930365B (en) | A kind of relay protection statistical analysis and the check method of operational management data | |
| CN108256713A (en) | Nuclear power plant system measure of supervision based on ERDB | |
| CN102005736B (en) | On-line monitoring method of state of relay protection equipment | |
| CN107977714A (en) | A kind of intelligent control platform of power transformation fortune inspection | |
| CN104638764A (en) | Intelligent state diagnosis and overhauling system for power distribution network equipment | |
| CN110728424A (en) | Cloud five-prevention intelligent scheduling system | |
| CN109358583A (en) | A method of preventing the failure of nuclear power unit key work center method | |
| CN104240781A (en) | Signal distribution method and signal distribution system of digital instrument control system (DCS) of nuclear power plant | |
| Linnerooth‐Bayer et al. | Applications of probabilistic risk assessments: the selection of appropriate tools 1 | |
| CN106228472A (en) | A kind of substation equipment intelligent patrol detection failure analysis methods | |
| Eltyshev et al. | Diagnostics of the power oil-filled transformer equipment of thermal power plants | |
| KR102232876B1 (en) | Breakdown type analysis system and method of digital equipment | |
| CN110210722A (en) | A kind of development approach of nuclear power plant system supervision scheme | |
| CN109685682A (en) | The method of regulator control system inspection operation ticket is intelligently generated based on relational database | |
| CN110212585A (en) | Running of wind generating set Reliability Prediction Method, device and Wind turbines based on statistical analysis | |
| Zerger et al. | Nuclear power plant commissioning experience | |
| Yunguang et al. | Research on secondary circuit identification technology and condition-based maintenance mode of intelligent substation | |
| CN113488957A (en) | Relay protection setting value online checking and early warning subsystem based on D5000 system | |
| CN105303315B (en) | A kind of power equipment reliability appraisal procedure counted and maintenance randomness influences | |
| Arena et al. | Functional safety of railway systems | |
| Kim et al. | Estimating Human Error Probabilities in Off-normal Situations from Full-Scope Simulator Data | |
| Chunyan et al. | Research on operation and maintenance management and control technology of power monitoring system based on personnel operation and equipment status evaluation | |
| Ameyaw et al. | A Review of Ghana Research Reactor-1 (GHARR-1) Component Aging Degradation Problems and Ways of Mitigation | |
| Zhang et al. | Compilation and optimization of nuclear power plant preventive maintenance program |
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 | ||
| RJ01 | Rejection of invention patent application after publication | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20190326 |