CN110415846A - Nuclear power unit faces the recognition methods for affected device of stopping for a long time - Google Patents
Nuclear power unit faces the recognition methods for affected device of stopping for a long time Download PDFInfo
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- CN110415846A CN110415846A CN201910749086.0A CN201910749086A CN110415846A CN 110415846 A CN110415846 A CN 110415846A CN 201910749086 A CN201910749086 A CN 201910749086A CN 110415846 A CN110415846 A CN 110415846A
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- equipment
- stopping
- nuclear power
- long time
- recognition methods
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Testing And Monitoring For Control Systems (AREA)
Abstract
Nuclear power unit faces the recognition methods for affected device of stopping for a long time, comprising the following steps: S1, combing are by facing the system for stopping influencing;S2, system operation frequency is analyzed, the equipment that running environment is changed;S3, the equipment analyzed from S2 comprehensively consider according to three criticality of equipment, operation frequency, running environment dimensions and filter out impacted equipment list;S4, Classifying Sum is carried out in the way of equipment class to the equipment list combed out in S3.The present invention stops influencing on because being faced, and the operation frequency of equipment, running environment etc., which change, provides comprehensive recognition methods and means.
Description
Technical field
The invention belongs to the recognition methods that nuclear power unit faces affected device of stopping for a long time.
Background technique
As domestic electrical market environment is increasingly severe, nuclear power unit availability is declined, and nuclear power unit faces often
Stop even medium-term and long-term spare, Zhong Guang core group occurs a lot of stopping leading to equipment damage since unit faces for a long time in fortune nuclear power unit
Event.It is fed back according to the analysis of power plant's event occurred, equipment component preventative maintenance strategy is unable to satisfy to face for a long time and stop
Maintenance of equipment demand leads to the equipment component reliability decrease.Face the technical research stopped for a long time for unit simultaneously because lacking
And deposit, seem experience deficiency when coping with the method for operation and changing bring challenge, results in a large amount of safety problem and equipment
Problem.
Face the equipment management for stopping the stage for unit, at present mainly has the following two problems:
Stop influencing first is that being faced, the operation frequency of equipment, running environment etc. change, and there is no comprehensively the equipment component
The means of identification and method of system;
Second is that existing maintenance policy is unable to satisfy the maintenance requirements for facing affected device under shut-down condition for a long time.At present in group
Unit occurred it is a lot of stop causing the event of equipment damage since unit faces for a long time, as H2GGR010PO face stop during put into operation for a long time
Lead to bearing wear, the red unit in winter of machine along the river, which faces, stops post-condenser vapour side and freeze that titanium tube is caused to be deformed.
Summary of the invention
The object of the present invention is to provide the recognition methods that nuclear power unit faces affected device of stopping for a long time, to solve existing set
Standby way to manage not system, incomplete technical problem.
Nuclear power unit faces the recognition methods for affected device of stopping for a long time comprising following steps:
S1, combing are by facing the system for stopping influencing;
S2, system operation frequency is analyzed, the equipment that running environment is changed;
S3, the equipment analyzed from S2 are examined according to three criticality of equipment, operation frequency, running environment dimension synthesis
Worry filters out impacted equipment list;
S4, Classifying Sum is carried out in the way of equipment class to the equipment list combed out in S3.
It is further preferred that the S1 specifically includes following steps, according to nuclear power station running technology program, RP, NS/ are combed
4 kinds of SG, NS/RRA, MCS are faced and stop system impacted under operational mode.
Further, the S2 specifically includes following steps, and recording step S1 obtains running environment or operation in system
The equipment that frequency is changed, and operation operation purpose, operating parameter variation are illustrated, recorded, convenient for subsequent into one
Walk equipment identification.
Further, the criticality of equipment includes crucial, important, economical in the S3 and four grades are extremely repaired in operation,
Equipment in crucial grade includes to safety and the biggish equipment of unit availability impact, and consequence caused by failing can not connect
It is serious by ground;Equipment in important level includes not directly affecting security function, but will increase unit safety risk, leads to machine
The equipment that group availability reduces, the equipment for influencing environment and risk-aversion measure;Equipment in economic grade includes not influencing
Safety leads to the reduction of unit availability, but has the equipment of larger impact to operating maintenance cost;In operation to maintenance level
Equipment include do not influence safety or cause unit availability reduction, the equipment for not needing any preventative maintenance.
Further, the operation frequency of equipment includes that frequency variation is high and frequency changes low two grades, place in the S3
Change high-grade equipment in frequency and be included in unit into when facing stop mode, significant change or frequent movement occur for the state that puts into operation
Equipment;Change low equipment in frequency and be included in unit into when facing stop mode, the state that puts into operation is constant or change frequency is small
In the equipment for being equal to 2 times.
Further, the frequency variation height is judged by the following operating status of equipment,
H1: interruption or continuous operation are switched to by stoppage in transit;
H2: frequent movement is switched to by normally opened normal pass;
H3: switch to frequently adjust by fixed aperture;
H4: switched to by power loss electricly electricly or frequent continuous;
H5: switch to continue or be interrupted with pressure by decompression;
H6: it puts into operation because of maintenance;
H7: steam trap/drain valve perseveration;GSS (separator system), AHP (high-pressure feed water heating
Device system), ARE (main feedwater flow control system), GCT (turbine bypass system), CEX (condensed water extraction system) and GRH
(generator hydrogen cooling system) important adjusting valve events;
H8: switched to by interruption or continuous operation out of service;Normally opened normal pass is switched to by frequent movement;Switched to by frequently adjusting
Fixed aperture;Electric it switch to power loss by continuous electric or frequent;With pressure switch to decompression by continuing or being interrupted.
Further, the running environment of equipment includes that environmental change is harsh and environmental change good two etc. in the S3
Grade.
Judged in addition, the facility environment variation is harsh according to following standard,
A: medium temperature is from room temperature to running temperature, running temperature >=50 DEG C, and pressure medium is from normal pressure to operating pressure, fortune
Row pressure >=7MPa or temperature, pressure frequent fluctuation;
B: vibration obviously becomes larger, variable quantity >=50%;
C: humidity obviously becomes larger, relative humidity >=65%;
D: equipment local environment is deteriorated, and environment includes internal and external environment;
E: flow, flow velocity obviously become larger, variable quantity >=50%, wash away, erosion, erosion, corrosion become larger;
F: equipment has maintenance demand, including important motor, generator and exciter after stopping transport;
G: the important equipment in unit defect list is run in spite of illness;
H: medium temperature from running temperature to room temperature, pressure medium from operating pressure to normal pressure, wherein running temperature >=50
DEG C, operating pressure >=7Mpa.
It is further preferred that the S4 classifies according to particular device and common apparatus, the particular device refers to nuclear power station
It plays an important role and the particular device of negligible amounts;The common apparatus: refer to that nuclear power station is widely used, the general of substantial amounts is set
It is standby.
The invention has the following advantages:
The present invention, which has formulated, to be faced the operation frequency classification clause of stopping time affected device identification, faces the knowledge of stopping time affected device
Other running environment classification clause, face stopping time affected device identification principle, face stopping time affected device principle of classification, to because by
Face and stop influencing, the operation frequency of equipment, running environment etc., which change, provides comprehensive recognition methods and means.
Implementation of the invention, which compensates for domestic nuclear power and tests at present due to facing menopause, compares shortcoming, and equipment, which is set, to be remained in
The experience of each power plant oneself, equipment covering scope pertain only to pay close attention to equipment during maintenance, inspection, important regulating valve and start and stop
Deng not forming the deficiency of overall scientific recognition methods, nuclear power unit can be provided and need to pay close attention in the case where difference faces stop mode
Affected device inventory.On this basis, preventative maintenance strategy and status monitoring are adjusted for equipment list by nuclear power plant
Means not only guarantee the safe and reliable operation of above equipment, reduce maintenance cost, and ensure unit or more to a certain extent
Capable critical path is unaffected.
Detailed description of the invention
Fig. 1 is the flow chart for the recognition methods that nuclear power unit of the present invention faces affected device of stopping for a long time.
Specific embodiment
For a clearer understanding of the technical characteristics, objects and effects of the present invention.Obviously, described embodiment
Only a part of the embodiment of the present invention, instead of all the embodiments.Based on the embodiments of the present invention, the common skill in this field
Art personnel every other embodiment obtained without making creative work belongs to the model that the present invention protects
It encloses.
Main thought of the present invention is that combing difference first faces system impacted under stop mode, which is analyzed in the system and is set
Standby operation frequency, running environment are changed;Then according to the criticality of these equipment, operation frequency, running environment three
A dimension, which comprehensively considers, filters out impacted equipment list;Finally, to the equipment list combed out in the way of equipment class
Classifying Sum is carried out, final design nucleation motor group faces the recognition methods for affected device of stopping for a long time, and particular technique route is such as
Lower Fig. 1, comprising the following steps:
S1, combing are by facing the system for stopping influencing;
S2, system operation frequency is analyzed, the equipment that running environment is changed;
S3, the equipment analyzed from S2 are examined according to three criticality of equipment, operation frequency, running environment dimension synthesis
Worry filters out impacted equipment list;
S4, Classifying Sum is carried out in the way of equipment class to the equipment list combed out in S3.
1, affected systems and equipment screening
According to nuclear power station running technology program, RP (reactor capability operational mode) is combed, (evaporator is cooling just by NS/SG
Normal shutdown mode), NS/RRA (the cooling normal shutdown mode of RRA), 4 kinds of MCS (maintenance shutdown mode) face stop under operational mode by
The system of influence, which equipment operating environment or operation frequency are changed in record system, and to operation operation purpose, fortune
Situations such as row Parameters variation, is illustrated, records, convenient for subsequent further equipment identification.
2, affected device recognition methods introduction
1) affected device identifies dimension
For facing the identification of affected device under stop mode, reference device is classified theory, by equipment criticality, operation frequency
Consider with three dimensions of running environment.
A) equipment criticality
Crucial C: to safety and the biggish equipment of unit availability impact, consequence caused by failing is unacceptably tight
Weight.Such as shut down shutdown, unit is forced to drop back, causes great casualties, unexpected radio exposure.
Important S: not directly affecting security function, but will increase unit safety risk;Lead to setting for unit availability reduction
Equipment that is standby, influencing environment and risk-aversion measure can just connect only when the frequency that the failure of these equipment occurs is considerably less
By.
The equipment that economic E: not influencing safety or unit availability is caused to reduce, but have larger shadow to operating maintenance cost
It rings.
Operation is to maintenance R: not influencing safety or leads to the reduction of unit availability, does not need setting for any preventative maintenance
It is standby.
B) equipment runs frequency
Frequency changes high H: when unit enters and faces stop mode, significant change occurs for putting equipment in service state or equipment is frequently moved
Make.
Frequency changes low L: when unit enters and faces stop mode, putting equipment in service state is constant or change frequency is less than or equal to 2
It is secondary.
Face operation frequency classification clause such as the following table 1 of stopping time affected device identification.
Table 1 faces the operation frequency classification clause of stopping time affected device identification
C) equipment operating environment
Face running environment classification clause such as the following table 2 of stopping time affected device identification.
Table 2 faces the running environment classification clause of stopping time affected device identification
2) face stopping time affected device identification principle
Face stopping time affected device identification principle such as the following table 3.
Table 3 faces stopping time affected device identification principle
Remarks: Y --- it needs to retain;N --- it is not required to retain;" optional " --- optionally select;
3, affected device is classified
Classify to affected device, convenient for Unify legislation dependent failure mechanism, possible mitigation scheme and can take
Monitoring task type.Preventative maintenance and monitoring task are typically based on device type, therefore help to affected device classification
In the operation sequence formulated suitable maintenance task and may need to modify.
According to the above-mentioned equipment list filtered out, classify according to following device class principle.
1) particular device: referring to that nuclear power station plays an important role and the particular device of negligible amounts, such as drum net, main transformer, main pump, vapour
Turbine, generator, diesel engine etc..
2) common apparatus: refer to nuclear power station be widely used, the common apparatus of substantial amounts, such as pump, motor, valve, pick-up
Device etc..For common apparatus, mainly from function, device structure and working principle, while considering that architectural difference can to equipment
Classify by whether property and maintenance policy demand have an impact.As gate valve one-board and double ram type in structure area
Not, but management strategy is almost the same, with regard to no longer classifying;As dc motor more than ac motor converter, structure
Different, maintenance requirements difference, it is necessary to classify.
General device type includes but is not limited to:
Rotating machinery (pump class, motor, blower, air compressor machine, refrigeration machine etc.)
Drive apparatus (gear-box, shaft coupling, fluid coupling etc.)
Valve (regulating valve, pressure reducing valve, safety valve, shut-off valve, gate valve, butterfly valve, diaphragm valve, check-valves etc.)
Container and heat exchanger (pressure vessel, surface-type heat exchanger, direct contact heat exchanger, water tank, fuel tank etc.)
Steam trap, filter, expansion joint etc.
Analog quantity and switching value transmitter (temperature transmitter, pressure transmitter, flow switch, liquid-level switch etc.)
Pneumatic operated valve instrument control component (locator, valve position feedback device, limit switch, E/P converter etc.)
Electric/pneumatic executing agency
Electric switch, heater and component.
The embodiment of the present invention is described with above attached drawing, but the invention is not limited to above-mentioned specific
Embodiment, the above mentioned embodiment is only schematical, rather than restrictive, those skilled in the art
Under the inspiration of the present invention, without breaking away from the scope protected by the purposes and claims of the present invention, it can also make very much
Form, all of these belong to the protection of the present invention.
Claims (9)
1. the recognition methods that nuclear power unit faces affected device of stopping for a long time comprising following steps:
S1, combing are by facing the system for stopping influencing;
S2, system operation frequency is analyzed, the equipment that running environment is changed;
S3, the equipment analyzed from S2 comprehensively consider sieve according to three criticality of equipment, operation frequency, running environment dimensions
Select impacted equipment list;
S4, Classifying Sum is carried out in the way of equipment class to the equipment list combed out in S3.
2. the recognition methods that nuclear power unit as described in claim 1 faces affected device of stopping for a long time, it is characterised in that: described
Step S1 specifically includes following steps, and according to nuclear power station running technology program, combing RP, NS/SG, NS/RRA, MCS4 kind, which is faced, stops
Impacted system under operational mode.
3. the recognition methods that nuclear power unit as described in claim 1 faces affected device of stopping for a long time, it is characterised in that: described
Step S2 specifically includes following steps, and recording step S1 obtains running environment in system or what operation frequency was changed sets
It is standby, and operation operation purpose, operating parameter variation are illustrated, recorded, convenient for subsequent further equipment identification.
4. the recognition methods that nuclear power unit as described in claim 1 faces affected device of stopping for a long time, it is characterised in that: described
The criticality of equipment includes crucial, important, economical in step S3 and operation is to four grades of maintenance, the equipment in crucial grade
Including to safety and the biggish equipment of unit availability impact, consequence caused by failing is unacceptably serious;In important
The equipment of grade includes not directly affecting security function, but will increase unit safety risk, leads to setting for unit availability reduction
Equipment that is standby, influencing environment and risk-aversion measure;Equipment in economic grade includes not influencing safety or causing unit can
It is reduced with property, but has the equipment of larger impact to operating maintenance cost;Equipment in operation to maintenance level includes not influencing
Safety leads to the reduction of unit availability, the equipment for not needing any preventative maintenance.
5. the recognition methods that nuclear power unit as described in claim 1 faces affected device of stopping for a long time, it is characterised in that: described
The operation frequency of equipment includes that frequency variation is high and frequency changes low two grades in step S3, is changed in frequency high-grade
Equipment is included in unit into the equipment that when facing stop mode, significant change or frequent movement occur for the state that puts into operation;Become in frequency
Change low equipment and be included in unit and enter when facing stop mode, the state that puts into operation is constant or change frequency is less than or equal to 2 equipment.
6. the recognition methods that nuclear power unit as claimed in claim 5 faces affected device of stopping for a long time, it is characterised in that: described
Frequency variation is high to be judged by the following operating status of equipment,
H1: interruption or continuous operation are switched to by stoppage in transit;
H2: frequent movement is switched to by normally opened normal pass;
H3: switch to frequently adjust by fixed aperture;
H4: switched to by power loss electricly electricly or frequent continuous;
H5: switch to continue or be interrupted with pressure by decompression;
H6: it puts into operation because of maintenance;
H7: steam trap/drain valve perseveration;The important adjusting valve events of GSS/AHP/ARE/GCT/CEX/GRH;
H8: switched to by interruption or continuous operation out of service;Normally opened normal pass is switched to by frequent movement;Switch to fix by frequently adjusting
Aperture;Electric it switch to power loss by continuous electric or frequent;With pressure switch to decompression by continuing or being interrupted.
7. the recognition methods that nuclear power unit as described in claim 1 faces affected device of stopping for a long time, it is characterised in that: described
The running environment of equipment includes that environmental change is harsh and good two grades of environmental change in S3.
8. the recognition methods that nuclear power unit as claimed in claim 7 faces affected device of stopping for a long time, it is characterised in that: described
Facility environment variation is harsh to be judged according to following standard,
A: medium temperature is from room temperature to running temperature, running temperature >=50 DEG C, and pressure medium is from normal pressure to operating pressure, operation pressure
Power >=7MPa or temperature, pressure frequent fluctuation;
B: vibration obviously becomes larger, variable quantity >=50%;
C: humidity obviously becomes larger, relative humidity >=65%;
D: equipment local environment is deteriorated, and environment includes internal and external environment;
E: flow, flow velocity obviously become larger, variable quantity >=50%, wash away, erosion, erosion, corrosion become larger;
F: equipment has maintenance demand, including important motor, generator and exciter after stopping transport;
G: the important equipment in unit defect list is run in spite of illness;
H: medium temperature from running temperature to room temperature, pressure medium from operating pressure to normal pressure, wherein running temperature >=50 DEG C, fortune
Row pressure >=7Mpa.
9. the nuclear power unit as described in claim 1~8 any one faces the recognition methods for affected device of stopping for a long time, special
Sign is: the S4 classifies according to particular device and common apparatus, the particular device refer to nuclear power station play an important role and
The particular device of negligible amounts;The common apparatus: refer to nuclear power station be widely used, the common apparatus of substantial amounts.
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Citations (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH01291115A (en) * | 1988-05-19 | 1989-11-22 | Nippon Atom Ind Group Co Ltd | Security object equipment selector |
CN103745293A (en) * | 2013-11-27 | 2014-04-23 | 苏州热工研究院有限公司 | RCM analysis method |
CN107132780A (en) * | 2017-04-25 | 2017-09-05 | 中广核研究院有限公司 | A kind of method and device for screening nuclear power plant's system under evaluation |
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 |
CN108710959A (en) * | 2018-06-05 | 2018-10-26 | 广东核电合营有限公司 | Reduce method, nuclear power generating sets and the storage medium of nuclear power generating sets failure rate |
CN109299846A (en) * | 2018-07-20 | 2019-02-01 | 岭东核电有限公司 | A kind of nuclear power plant equipment analysis method for reliability, system and terminal device |
CN109583600A (en) * | 2018-11-29 | 2019-04-05 | 苏州热工研究院有限公司 | A kind of method, computer equipment and storage medium for reducing nuclear power unit and shutting down shutdown probability |
CN109961217A (en) * | 2019-02-28 | 2019-07-02 | 苏州热工研究院有限公司 | Nuclear power plant equipment reliability stage division, system and readable storage medium storing program for executing |
CN110085340A (en) * | 2019-04-22 | 2019-08-02 | 中国核电工程有限公司 | A kind of nuclear power plant supports security function identification method when system is unavailable |
-
2019
- 2019-08-14 CN CN201910749086.0A patent/CN110415846B/en active Active
Patent Citations (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH01291115A (en) * | 1988-05-19 | 1989-11-22 | Nippon Atom Ind Group Co Ltd | Security object equipment selector |
CN103745293A (en) * | 2013-11-27 | 2014-04-23 | 苏州热工研究院有限公司 | RCM analysis method |
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 |
CN107132780A (en) * | 2017-04-25 | 2017-09-05 | 中广核研究院有限公司 | A kind of method and device for screening nuclear power plant's system under evaluation |
CN108710959A (en) * | 2018-06-05 | 2018-10-26 | 广东核电合营有限公司 | Reduce method, nuclear power generating sets and the storage medium of nuclear power generating sets failure rate |
CN109299846A (en) * | 2018-07-20 | 2019-02-01 | 岭东核电有限公司 | A kind of nuclear power plant equipment analysis method for reliability, system and terminal device |
CN109583600A (en) * | 2018-11-29 | 2019-04-05 | 苏州热工研究院有限公司 | A kind of method, computer equipment and storage medium for reducing nuclear power unit and shutting down shutdown probability |
CN109961217A (en) * | 2019-02-28 | 2019-07-02 | 苏州热工研究院有限公司 | Nuclear power plant equipment reliability stage division, system and readable storage medium storing program for executing |
CN110085340A (en) * | 2019-04-22 | 2019-08-02 | 中国核电工程有限公司 | A kind of nuclear power plant supports security function identification method when system is unavailable |
Non-Patent Citations (1)
Title |
---|
田露: "核电厂DCS***运行维护管理策略研讨", 《核动力工程》 * |
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