CN103811087B - The aging control method of a kind of nuclear power plant instrument control equipment and device - Google Patents
The aging control method of a kind of nuclear power plant instrument control equipment and device Download PDFInfo
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- CN103811087B CN103811087B CN201210457299.4A CN201210457299A CN103811087B CN 103811087 B CN103811087 B CN 103811087B CN 201210457299 A CN201210457299 A CN 201210457299A CN 103811087 B CN103811087 B CN 103811087B
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- 230000032683 aging Effects 0.000 title claims abstract description 345
- 238000000034 method Methods 0.000 title claims abstract description 71
- 238000012545 processing Methods 0.000 claims abstract description 45
- 230000008569 process Effects 0.000 claims abstract description 41
- 238000001514 detection method Methods 0.000 claims description 19
- 230000000737 periodic effect Effects 0.000 claims description 15
- 230000008859 change Effects 0.000 claims description 12
- 230000015556 catabolic process Effects 0.000 claims description 10
- 238000006731 degradation reaction Methods 0.000 claims description 10
- 238000012423 maintenance Methods 0.000 claims description 8
- 238000004519 manufacturing process Methods 0.000 claims description 5
- 238000012544 monitoring process Methods 0.000 claims description 5
- 230000009466 transformation Effects 0.000 claims description 5
- 230000029087 digestion Effects 0.000 claims description 3
- 230000002431 foraging effect Effects 0.000 claims 2
- 239000003990 capacitor Substances 0.000 description 11
- 230000005611 electricity Effects 0.000 description 4
- 239000000523 sample Substances 0.000 description 4
- 230000003679 aging effect Effects 0.000 description 2
- 239000008393 encapsulating agent Substances 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 230000008020 evaporation Effects 0.000 description 2
- 238000001704 evaporation Methods 0.000 description 2
- 230000006870 function Effects 0.000 description 2
- 238000005259 measurement Methods 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 230000001681 protective effect Effects 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 238000013459 approach Methods 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 238000005868 electrolysis reaction Methods 0.000 description 1
- 239000003792 electrolyte Substances 0.000 description 1
- 239000000686 essence Substances 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 238000001465 metallisation Methods 0.000 description 1
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- 229910052710 silicon Inorganic materials 0.000 description 1
- 239000010703 silicon Substances 0.000 description 1
- 229910000679 solder Inorganic materials 0.000 description 1
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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
- Y02E30/30—Nuclear fission reactors
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Abstract
The present invention is applicable to control field of nuclear, it is provided that the aging control method of I &C equipment and device in a kind of nuclear power station, described method includes: the I &C equipment in nuclear power station is carried out aging staged care, obtains the aging grade of each I &C equipment；According to the corresponding relation between default aging grade and ageing management processing mode, obtain the ageing management processing mode corresponding with the aging grade of each I &C equipment；Use the described ageing management processing mode corresponding with the aging grade of each I &C equipment that each I &C equipment in nuclear power station is carried out Aging control.The present invention is by carrying out aging staged care to the I &C equipment used in nuclear power station, I &C equipment for different aging grades, different ageing management processing modes is used to process, thus save the burin-in process cost of nuclear power plant instrument control equipment, improve nuclear power plant instrument control equipment reliability of operation simultaneously.
Description
Technical field
The present invention relates to million kilowatt advanced pressurized water reactor nuclear power plant key technology area, particularly relate to the core in above-mentioned field
The aging control method of power station I &C equipment and device.
Background technology
In million kilowatt advanced pressurized water reactor nuclear power plant, the I &C equipment used in nuclear power plant is large number of, in nuclear power plant
The life-span of the part I &C equipment used, these I &C equipment were in long running less than the projected life of nuclear power plant
There is problem of aging in various degree, the safe and stable operation of nuclear power plant is caused distinct program by the ageing failure of I &C equipment
Impact.Especially relate to nuclear power station safety total correlation and the ageing failure of the important I &C equipment with motor stabilizing operation,
By to the bigger economic loss that causes of nuclear power plant, even threaten the nuclear safety of unit.Therefore each I &C equipment in nuclear power plant
Problem of aging become nuclear power plant need solve major issue.
All I &C equipment that the ageing method of the existing I &C equipment of nuclear power plant generally is directed in nuclear power plant are adopted
By identical aging replacing pattern, although this mode ensure that the safe operation of nuclear power plant to a certain extent, but this mode
Significantly increase the Aging control cost of I &C equipment.
Summary of the invention
The purpose of the embodiment of the present invention is to provide aging control method and the device of a kind of nuclear power plant instrument control equipment, it is intended to
Solve the problem that the Aging control cost of I &C equipment is high.
The embodiment of the present invention is achieved in that the aging control method of I &C equipment in a kind of nuclear power station, described method
Including:
I &C equipment in nuclear power station is carried out aging staged care, obtains the aging grade of each I &C equipment；
According to the corresponding relation between default aging grade and ageing management processing mode, obtain and each I &C equipment
The ageing management processing mode that aging grade is corresponding；
Use the described ageing management processing mode corresponding with the aging grade of each I &C equipment to each instrument in nuclear power station
Control equipment carries out Aging control.
The another object of the embodiment of the present invention is to provide the ageing control device of I &C equipment in a kind of nuclear power station, described
Device includes:
Aging stage unit, for the I &C equipment in nuclear power station is carried out aging staged care, obtains each I &C equipment
Aging grade；
Burin-in process mode acquiring unit, be used between aging grade and the ageing management processing mode that basis is preset is right
Should be related to, obtain the ageing management processing mode corresponding with the aging grade of each I &C equipment；
Burin-in process unit, for using the described ageing management processing mode corresponding with the aging grade of each I &C equipment
Each I &C equipment in nuclear power station is carried out Aging control.
In embodiments of the present invention, by the I &C equipment used in nuclear power station is carried out aging staged care, for not
With the I &C equipment of aging grade, use different ageing management processing modes to process, thus control nuclear power plant instrument control and set
Standby burin-in process cost, improves nuclear power plant instrument control equipment reliability of operation simultaneously.
Accompanying drawing explanation
Fig. 1 is the flowchart of the aging control method of the nuclear power plant instrument control equipment that the embodiment of the present invention provides；
Fig. 2 is the flowchart of the aging control method of the nuclear power plant instrument control equipment that another embodiment of the present invention provides；
Fig. 3 is the flowchart of the aging control method of the nuclear power plant instrument control equipment that yet another embodiment of the invention provides；
Fig. 4 is the structured flowchart of the ageing control device of the nuclear power plant instrument control equipment that the embodiment of the present invention provides；
Fig. 5 is the structured flowchart of the ageing control device of the nuclear power plant instrument control equipment that another embodiment of the present invention provides.
Detailed description of the invention
In order to make the purpose of the present invention, technical scheme and advantage clearer, below in conjunction with drawings and Examples, right
The present invention is further elaborated.Should be appreciated that specific embodiment described herein only in order to explain the present invention, and
It is not used in the restriction present invention.
In embodiments of the present invention, by the I &C equipment in nuclear power station is carried out classification Aging control and process, thus
Save the burin-in process cost of nuclear power plant instrument control equipment, improve nuclear power plant instrument control equipment reliability of operation simultaneously.
In order to technical solutions according to the invention are described, illustrate below by specific embodiment.
What Fig. 1 showed the aging control method of the nuclear power plant instrument control equipment that the embodiment of the present invention provides realizes flow process, in detail
State as follows:
S101, carries out aging staged care to the I &C equipment in nuclear power station, obtains the aging grade of each I &C equipment.
Wherein the I &C equipment in nuclear power station refers to the instrument in nuclear power station and control equipment, and it includes but not limited to electricity
Source, electromagnetic valve, flow/pressure fluid level transmitter, transformator, temperature probe, switching value primary element, liquid-level switch, pressure are opened
Pass, neutron-flux detector, Electronic Control plate, switching switch, all kinds of relay, vibration and displacement measurement probe, cable, scattered
Hot-air fan, display, keyboard, mouse etc..Wherein every kind of I &C equipment includes one or more components and parts.
Wherein the I &C equipment in nuclear power station being carried out aging staged care, the aging grade obtaining each I &C equipment is concrete
Including: the safety requirements according to nuclear power plant instrument control equipment and the availability to nuclear power generating sets require the I &C equipment in nuclear power station
Carry out aging staged care, obtain the aging grade of each I &C equipment.
Wherein the safety requirements according to nuclear power plant instrument control equipment and the availability to nuclear power generating sets require in nuclear power station
I &C equipment carries out aging staged care, and the mode of the aging grade obtaining each I &C equipment is specific as follows:
I &C equipment in nuclear power station is divided into A level, B level and three aging grades of C level from high to low according to aging grade.
Wherein the aging grade of I &C equipment is the highest, represents impact that nuclear plant safety runs by this I &C equipment or to nuclear power generating sets
The impact of availability is the biggest.
The most aging grade is that the I &C equipment of A level includes I &C equipment relevant to nuclear safety in nuclear power station or single
I &C equipment fault may result in nuclear power station and shuts down the I &C equipment of shutdown, as I &C equipment that aging grade is A level include but not
Being limited to reactor protection loop control logic power supply, Control rod drive line circle, evaporator feedwater controls the control plate on loop
Deng.
Aging grade is that the I &C equipment of B level includes in nuclear power station because the inefficacy of I &C equipment may result in unit availability fall
Low I &C equipment, as I &C equipment that aging grade is B level includes but not limited to two from three, four takes two relay protective scheme and control back
The I &C equipment etc. that road is relevant.
Aging grade is that the I &C equipment of C level includes all I &C equipment in addition to aging grade is A level and B level.
In order to be easy to the Aging control of I &C equipment further, in an alternative embodiment of the invention, the method also includes:
Whether comprise short life components and parts according to I &C equipment and the I &C equipment that aging grade is A level is further divided into A1
Whether level and A2 level, comprise short life components and parts according to I &C equipment and be further divided into by the I &C equipment that aging grade is B level
B1 level and B2 level.
The most aging grade is that the I &C equipment of A1 level includes in the I &C equipment that aging grade is A level containing short life unit
The I &C equipment of device, the I &C equipment if aging grade is A1 level includes but not limited to that evaporator feedwater controls the control of passage
Plate, transmitter；Out-pile neutron-flux detector, the power supply etc. in reactor protection loop, aging grade is that the instrument control of A2 level sets
The standby I &C equipment including not containing short life components and parts in the I &C equipment that aging grade is A level, if aging grade is A2 level
I &C equipment include but not limited to Control rod drive line circle, control rod rod position measurement probe etc..
Aging grade is that the I &C equipment of B1 level includes in the I &C equipment that aging grade is B level containing short life components and parts
I &C equipment, the I &C equipment if aging grade is B1 level includes but not limited to the control plate of two from three protective loop, change
The I &C equipment sending device etc., aging grade to be B2 level includes not containing in the I &C equipment that aging grade is B level short life unit device
The I &C equipment of part, as I &C equipment that aging grade is B2 level include but not limited to the shutdown of non-single failure, the switch of shutdown,
Temperature probe etc..
Wherein short life components and parts refer to because material structure or working mechanism cause its life-span to be serviced significantly less than it
The components and parts of the projected life of integral device, short life components and parts include but not limited to electrochemical capacitor, fuse, relay, electricity
Position device, adapter, Zener diode, controllable silicon, high heating resistor, switch, optocoupler, circuit board connector, binding post, LED,
Solder joint, D and D/A converter, battery etc..
There is provided it should be noted that the above-mentioned hierarchical approaches to each I &C equipment in nuclear power station is only the embodiment of the present invention
The concrete mode of one of which, according to nuclear power station, the safety requirements of I &C equipment and the availability of nuclear power generating sets are required core
I &C equipment in power station carries out the detailed process of aging staged care and is not limited with described above, it is also possible to according to nuclear power station pair
I &C equipment in nuclear power station is divided into other grades by the security requirement of I &C equipment and the availability requirement to nuclear power generating sets,
As being divided into superfine, senior, intermediate and rudimentary four ranks etc., do not limit at this, the most exhaustive.
S102, according to the corresponding relation between default aging grade and ageing management processing mode, obtains and each instrument control
The ageing management processing mode that the aging grade of equipment is corresponding.
In the present embodiment, ageing management processing mode includes but not limited to ageing management cycle, burin-in process mode etc..
Such as the aging grade of difference for I &C equipment, the different ageing management cycles can be set, as old in the height for I &C equipment
Change grade, the shorter ageing management cycle is set, for the low aging grade of I &C equipment, longer digestion period is set, or
Person arranges different burin-in process modes, and such as the aging grade of height for I &C equipment, it is direct for arranging its burin-in process mode
Changing, for the low aging grade of I &C equipment, arranging its burin-in process mode is maintenance, until I &C equipment is because of ageing failure
Time change again, or the different replacement cycles is set.
In the present embodiment, the corresponding relation between aging grade and ageing management processing mode is pre-set, in order to right
The I &C equipment with same aging grade carries out identical ageing management process.The aging grade wherein pre-set is with aging
Corresponding relation between detection processing mode is as described in Table 1, but is not limited with table 1, it is also possible to according to the demand of different nuclear power station,
Other corresponding relations between aging grade and ageing management processing mode are set, illustrate the most one by one at this:
| Aging grade | Ageing management processing mode |
| A1 level | Regularly replace aging I &C equipment, and the performance parameter of periodic monitoring I &C equipment |
| B1 level | Regularly replace the components and parts in aging I &C equipment or aging I &C equipment |
| A2 level | Periodic detection, changes and aging degrades or the components and parts of degradation failure |
| B2 level | Periodic detection, changes and aging degrades or the components and parts of degradation failure |
| C level | Based on corrective maintenance, for the shortage equipment that stops production, it is replaced or transformation and upgrade |
In the present embodiment, the I &C equipment in nuclear power station is carried out aging staged care, obtain the old of each I &C equipment
Change after grade, can corresponding by between the aging grade of I &C equipment with default aging grade and ageing management processing mode
Relation is mated, the ageing management processing mode corresponding to get the aging grade of this I &C equipment.
S103, uses the ageing management processing mode corresponding with the aging grade of each I &C equipment to each instrument in nuclear power station
Control equipment carries out Aging control.
In the present embodiment, after getting the ageing management processing mode corresponding with the aging grade of each I &C equipment,
Can use this ageing management processing mode that each I &C equipment in nuclear power station is carried out Aging control.
Specific as follows:
When the aging grade of I &C equipment is A1 level, then regularly replace aging I &C equipment, and periodic monitoring instrument control
The performance parameter of equipment；
When the aging grade of I &C equipment is A2 level, then periodic detection, change and aging degrade or the unit of degradation failure
Device；
When the aging grade of I &C equipment is B1 level, then regularly replaces aging I &C equipment or aging instrument control sets
Components and parts in Bei；
When the aging grade of I &C equipment is B2 level, then periodic detection, change and aging degrade or the unit of degradation failure
Device；
When the aging grade of I &C equipment is C level, then based on corrective maintenance, for the shortage equipment that stops production, carry out
Replace or transformation and upgrade.
In embodiments of the present invention, by the I &C equipment used in nuclear power station is carried out aging staged care, for not
With the I &C equipment of aging grade, use different ageing management processing modes to process, thus control nuclear power plant instrument control and set
Standby burin-in process cost, improves nuclear power plant instrument control equipment reliability of operation simultaneously.
Fig. 2 shows the realization stream of the aging control method of the nuclear power plant instrument control equipment that another embodiment of the present invention provides
Journey, details are as follows:
S201, carries out aging staged care to the I &C equipment in nuclear power station, obtains the aging grade of each I &C equipment.Its
Detailed process is not as it has been described above, repeat them here.
S202, the aging grade of the I &C equipment in identification nuclear power station.
In the present embodiment, for the various I &C equipment in nuclear power station, need to identify the aging etc. of this I &C equipment
Level.Wherein identify that the detailed process of the aging grade of I &C equipment is as follows:
Judge that whether I &C equipment is the I &C equipment relevant to nuclear safety or single failure may result in nuclear power station and shuts down
The I &C equipment of shutdown, if it is, judge that the aging grade of this I &C equipment, as A level, determines whether that this I &C equipment is
No comprise short life components and parts, if it is, judge the aging grade of this I &C equipment as A1 level, if this I &C equipment does not wraps
Containing short life components and parts, then judge that the aging grade of this I &C equipment is as A2 level.
Judge whether I &C equipment is because the inefficacy of I &C equipment may result in the I &C equipment that unit availability reduces, if
It is then to judge that the aging grade of this I &C equipment, as B level, determines whether whether this I &C equipment comprises short life components and parts,
If it is, judge that the aging grade of this I &C equipment, as B1 level, if this I &C equipment does not comprise short life components and parts, is then sentenced
The aging grade of this I &C equipment fixed is B2 level.
When I &C equipment is not the I &C equipment relevant to nuclear safety or single failure may result in nuclear power station and shuts down shutdown
I &C equipment, be not because of the inefficacy of I &C equipment may result in unit availability reduce I &C equipment, then judge this instrument control
The aging grade of equipment is C level.
S203, according to the corresponding relation between default aging grade and ageing management processing mode, obtains and each instrument control
The ageing management processing mode that the aging grade of equipment is corresponding.Its detailed process is not as it has been described above, repeat them here.
S204, uses the ageing management processing mode corresponding with the aging grade of each I &C equipment to each instrument in nuclear power station
Control equipment carries out Aging control.Its detailed process is not as it has been described above, repeat them here.
In embodiments of the present invention, when I &C equipment being put into use in nuclear power station, set by identifying this instrument control
Standby aging grade, such that it is able to carry out Aging control to any one I &C equipment in nuclear power station.
Fig. 3 shows the realization stream of the aging control method of the nuclear power plant instrument control equipment that another embodiment of the present invention provides
Journey, the method be based on the aging control method shown in Fig. 1 or Fig. 2 on the basis of, below with based on figure, old shown in 2
As a example by changing the basis of control method, details are as follows:
S301, carries out aging staged care to the I &C equipment in nuclear power station, obtains the aging grade of each I &C equipment.Its
Detailed process is not as it has been described above, repeat them here.
S302, the I &C equipment in detection nuclear power station is the most aging, and when detecting that I &C equipment is aging, identifies nuclear power
The aging grade of this I &C equipment in standing.
In the present embodiment, for each I &C equipment used in nuclear power station, first detect each I &C equipment the most aging, as
The most aging, then identify the aging grade of this aging I &C equipment.
The most aging with I &C equipment in the concrete detection nuclear power station illustrating embodiment of the present invention offer below
Detailed process:
Refer to table 2, provide the aging action of short life components and parts, agine mechaism and ageing failure for the embodiment of the present invention
Corresponding relation between pattern, and table 3, for the embodiment of the present invention provide the aging action of I &C equipment, agine mechaism and
Corresponding relation between ageing failure pattern.
Table 2
Table 3
Can obtain according to the corresponding relation shown in table 2 and table 3:
Detection the most aging the specifically comprising the following steps that of electrochemical capacitor
The loss of the electrolyte of detection electrochemical capacitor, whether electrochemical capacitor ruptures, and whether electrochemical capacitor sealing lost efficacy, electrolysis
Whether electric capacity exists open fault, and whether electrochemical capacitor exists one or more in short trouble, when the electricity of electrochemical capacitor
The loss solving matter reaches predetermined threshold value, and electrochemical capacitor ruptures, electrochemical capacitor seal failure, and electrochemical capacitor exists open fault, electricity
When solution electric capacity exists one or more situations in short trouble, then judge that electrochemical capacitor is aging.
Detection the most aging the specifically comprising the following steps that of fuse
Whether detection fuse there is electromigration of metallizing, and whether fuse exists evaporation of metal phenomenon, and whether fuse
Corrode, one or more during the encapsulant of fuse is the most aging, when fuse occurs metallization electromigration, molten
There is evaporation of metal phenomenon in disconnected device, fuse corrodes, during one or more during the encapsulant of fuse is aging, then
Judge that fuse is aging.
For other short life components and parts and other I &C equipment, its ageing management principle ibid, at this most one by one
Illustrate.
S303, according to the corresponding relation between default aging grade and ageing management processing mode, obtains and each instrument control
The ageing management processing mode that the aging grade of equipment is corresponding.Its detailed process is not as it has been described above, repeat them here.
S304, uses the ageing management processing mode corresponding with the aging grade of each I &C equipment to each instrument in nuclear power station
Control equipment carries out Aging control.Its detailed process is not as it has been described above, repeat them here.
In embodiments of the present invention, the most aging by the I &C equipment used in detection nuclear power station automatically, set in instrument control
For time aging, identify the aging grade of I &C equipment, and use the ageing management processing mode corresponding with this aging grade to instrument
Control equipment carries out Aging control, so that the Aging control of I &C equipment and management are more convenient, flexible.
Fig. 4 shows the structure of the ageing control device of I &C equipment in the nuclear power station that the embodiment of the present invention provides, in order to
It is easy to illustrate to illustrate only the part relevant to the embodiment of the present invention.This device includes:
Aging stage unit 1, for the I &C equipment in nuclear power station is carried out aging staged care, obtains each I &C equipment
Aging grade.
In an alternative embodiment of the invention, this aging stage unit 1 is specifically for according to the peace of I &C equipment in nuclear power station
The full availability required with nuclear power generating sets requires the I &C equipment in nuclear power station is carried out aging staged care, obtains each instrument control and sets
Standby aging grade.
In an alternative embodiment of the invention, this aging stage unit 1 is specifically for being divided into A by the I &C equipment in nuclear power station
Level, B level and three aging grades of C level, wherein relevant to nuclear safety in nuclear power station I &C equipment or single failure may result in
The aging grade of the I &C equipment shutting down shutdown is A level, may result in unit availability fall because of the inefficacy of I &C equipment in nuclear power station
The aging grade of low I &C equipment is B level, and the aging grade of remaining I &C equipment in nuclear power station is C level.
In an alternative embodiment of the invention, this device also includes classification subelement 4.This classification subelement 4 is for according to instrument
Whether control equipment contains short life components and parts is further divided into A1 level and A2 level by the I &C equipment that aging grade is A level, will be old
Changing grade is that the I &C equipment of B level is further divided into B1 level and B2 level, the most aging grade be A level I &C equipment in containing short
The aging grade of the I &C equipment of life-span components and parts is A1 level, and the aging grade of the I &C equipment not containing short life components and parts is
A2 level, aging grade be B level I &C equipment in the aging grade of I &C equipment containing short life components and parts be B1 level, do not contain
The aging grade having the I &C equipment of short life components and parts is B2 level.
It is right that burin-in process mode acquiring unit 2 is used between aging grade and the ageing management processing mode that basis is preset
Should be related to, obtain the ageing management processing mode corresponding with the aging grade of each I &C equipment.Its detailed process as it has been described above,
This repeats no more.
Burin-in process unit 3 is for using the described ageing management processing mode corresponding with the aging grade of each I &C equipment
Each I &C equipment in nuclear power station is carried out Aging control.
In a preferred embodiment of the invention, this burin-in process unit 3 specifically for
When the aging grade of I &C equipment is A1 level, then regularly replace aging I &C equipment, and periodic monitoring instrument control
The performance parameter of equipment；
When the aging grade of I &C equipment is A2 level, then periodic detection, change and aging degrade or the unit of degradation failure
Device；
When the aging grade of I &C equipment is B1 level, then regularly replaces aging I &C equipment or aging instrument control sets
Components and parts in Bei；
When the aging grade of I &C equipment is B2 level, then periodic detection, change and aging degrade or the unit of degradation failure
Device；
When the aging grade of I &C equipment is C level, then based on corrective maintenance, for the shortage equipment that stops production, carry out
Replace or transformation and upgrade.
Fig. 5 shows the structure of the ageing control device of I &C equipment in the nuclear power station that another embodiment of the present invention provides,
Illustrate only the part relevant to the embodiment of the present invention for convenience of description.This device, on the basis of the device shown in Fig. 4, increases
Add with lower part:
This device also includes aging grade recognition unit 5.This aging grade recognition unit 5 is for identifying the instrument in nuclear power station
The aging grade of control equipment.The detailed process of the most concrete aging grade identification is not as it has been described above, repeat them here.
In an alternative embodiment of the invention, this device also includes ageing management unit 6.This ageing management unit 6 is used for examining
Survey the I &C equipment in nuclear power station the most aging, and when detecting that I &C equipment is aging, perform in described identification nuclear power station
The aging grade of this I &C equipment.
It should be noted that said system, included unit is to carry out dividing according to function logic, but also
It is not limited to above-mentioned division, as long as being capable of corresponding function；It addition, the specific name of each functional unit is also
For the ease of mutually distinguishing, it is not limited to protection scope of the present invention.
It will appreciated by the skilled person that all or part of step realizing in above-described embodiment method is permissible
Instructing relevant hardware by program to complete, described program can be stored in a computer read/write memory medium
In, described storage medium, such as ROM/RAM, disk, CD etc..
In embodiments of the present invention, by the I &C equipment used in nuclear power station is carried out aging staged care, for not
With the I &C equipment of aging grade, use different ageing management processing modes to process, thus control nuclear power plant instrument control and set
Standby burin-in process cost, improves nuclear power plant instrument control equipment reliability of operation simultaneously.
The foregoing is only presently preferred embodiments of the present invention, not in order to limit the present invention, all essences in the present invention
Any amendment, equivalent and the improvement etc. made within god and principle, should be included within the scope of the present invention.
Claims (12)
1. the aging control method of I &C equipment in a nuclear power station, it is characterised in that described method includes:
Require the I &C equipment in nuclear power station according to the safety requirements of I &C equipment in nuclear power station and the availability of nuclear power generating sets
Carrying out aging staged care, obtain the aging grade of each I &C equipment, the highest aging grade, represents that this I &C equipment is to nuclear power station
The impact of safe operation or the impact on nuclear power generating sets availability are the biggest；
According to the corresponding relation between default aging grade and ageing management processing mode, acquisition is aging with each I &C equipment
The ageing management processing mode that grade is corresponding；
Use the described ageing management processing mode corresponding with the aging grade of each I &C equipment that each instrument control in nuclear power station is set
Standby carrying out Aging control, described ageing management processing mode includes ageing management cycle and burin-in process mode, for aging etc.
The I &C equipment that level is high, arranges the shorter ageing management cycle or arranges its burin-in process mode for directly changing；For aging
The I &C equipment that grade is low, arranges longer digestion period or arranges its burin-in process mode for maintenance.
2. the method for claim 1, it is characterised in that according to the safety requirements of I &C equipment in nuclear power station and nuclear power machine
The availability of group requires the I &C equipment in nuclear power station is carried out aging staged care, obtains the aging grade tool of each I &C equipment
Body includes:
I &C equipment in nuclear power station is divided into A level, B level and three aging grades of C level, wherein relevant to nuclear safety in nuclear power station
I &C equipment or single failure may result in that to shut down the aging grade of I &C equipment of shutdown be A level, because of instrument control in nuclear power station
It is B level that the inefficacy of equipment may result in the aging grade of the I &C equipment that unit availability reduces, and remaining instrument control in nuclear power station sets
Standby aging grade is C level.
3. method as claimed in claim 2, it is characterised in that described method also includes:
According to I &C equipment whether contain short life components and parts the I &C equipment that aging grade is A level is further divided into A1 level and
A2 level, is further divided into B1 level and B2 level by the I &C equipment that aging grade is B level, and the most aging grade is that the instrument control of A level sets
The aging grade of the I &C equipment containing short life components and parts in Bei is A1 level, does not contains the I &C equipment of short life components and parts
Aging grade is A2 level, and aging grade is the aging grade of the I &C equipment containing short life components and parts in the I &C equipment of B level
For B1 level, the aging grade of the I &C equipment not containing short life components and parts is B2 level.
4. the method for claim 1, it is characterised in that described in described employing, the aging grade with each I &C equipment is corresponding
Ageing management processing mode each I &C equipment in nuclear power station carried out Aging control specifically include:
When the aging grade of I &C equipment is A1 level, then regularly replace aging I &C equipment, and periodic monitoring I &C equipment
Performance parameter；
When the aging grade of I &C equipment is A2 level, then periodic detection, change and aging degrade or the components and parts of degradation failure；
When the aging grade of I &C equipment is B1 level, then regularly replace in aging I &C equipment or aging I &C equipment
Components and parts；
When the aging grade of I &C equipment is B2 level, then periodic detection, change and aging degrade or the components and parts of degradation failure；
When the aging grade of I &C equipment is C level, then based on corrective maintenance, for the shortage equipment that stops production, it is replaced
Or transformation and upgrade.
5. the method for claim 1, it is characterised in that the aging grade preset in described basis processes with ageing management
Corresponding relation between mode, before obtaining the ageing management processing mode corresponding with the aging grade of each I &C equipment, described
Method also includes:
The aging grade of the I &C equipment in identification nuclear power station.
6. method as claimed in claim 5, it is characterised in that the aging grade of the I &C equipment in described identification nuclear power station
Before, described method also includes:
I &C equipment in detection nuclear power station is the most aging, and when detecting that I &C equipment is aging, performs described identification nuclear power
The aging grade of this I &C equipment in standing.
7. the ageing control device of I &C equipment in a nuclear power station, it is characterised in that described device includes:
Aging stage unit, for requiring core according to the safety requirements of I &C equipment in nuclear power station and the availability of nuclear power generating sets
I &C equipment in power station carries out aging staged care, obtains the aging grade of each I &C equipment, and the highest aging grade, and representing should
The impact that nuclear plant safety is run by I &C equipment or the impact on nuclear power generating sets availability are the biggest；
Burin-in process mode acquiring unit, for according to the corresponding pass between aging grade and the ageing management processing mode preset
System, obtains the ageing management processing mode corresponding with the aging grade of each I &C equipment；
Burin-in process unit, for using the described ageing management processing mode corresponding with the aging grade of each I &C equipment to core
Each I &C equipment in power station carries out Aging control, and described ageing management processing mode includes ageing management cycle and burin-in process
Mode, for the I &C equipment that aging grade is high, arranges the shorter ageing management cycle or to arrange its burin-in process mode is straight
Connect replacing；For the I &C equipment that aging grade is low, longer digestion period is set or its burin-in process mode is set for maintenance.
8. device as claimed in claim 7, it is characterised in that described aging stage unit is specifically for by the instrument in nuclear power station
Control equipment is divided into A level, B level and three aging grades of C level, wherein relevant to nuclear safety in nuclear power station I &C equipment or single
It is A level that fault may result in the aging grade of the I &C equipment shutting down shutdown, and in nuclear power station, the inefficacy because of I &C equipment may result in machine
The aging grade of the I &C equipment that group availability reduces is B level, and the aging grade of remaining I &C equipment in nuclear power station is C level.
9. device as claimed in claim 8, it is characterised in that described device also includes:
Whether classification subelement, for containing short life components and parts by I &C equipment that aging grade is A level according to I &C equipment
It is further divided into A1 level and A2 level, the I &C equipment that aging grade is B level is further divided into B1 level and B2 level, the most aging etc.
The aging grade of the I &C equipment containing short life components and parts in the I &C equipment that level is A level is A1 level, does not contains short life unit
The aging grade of the I &C equipment of device is A2 level, and aging grade is the instrument containing short life components and parts in the I &C equipment of B level
The aging grade of control equipment is B1 level, and the aging grade of the I &C equipment not containing short life components and parts is B2 level.
10. device as claimed in claim 7, it is characterised in that described burin-in process unit specifically for
When the aging grade of I &C equipment is A1 level, then regularly replace aging I &C equipment, and periodic monitoring I &C equipment
Performance parameter；
When the aging grade of I &C equipment is A2 level, then periodic detection, change and aging degrade or the components and parts of degradation failure；
When the aging grade of I &C equipment is B1 level, then regularly replace in aging I &C equipment or aging I &C equipment
Components and parts；
When the aging grade of I &C equipment is B2 level, then periodic detection, change and aging degrade or the components and parts of degradation failure；
When the aging grade of I &C equipment is C level, then based on corrective maintenance, for the shortage equipment that stops production, it is replaced
Or transformation and upgrade.
11. devices as claimed in claim 7, it is characterised in that described device also includes:
Aging grade recognition unit, for identifying the aging grade of the I &C equipment in nuclear power station.
12. devices as claimed in claim 11, it is characterised in that described device also includes:
Ageing management unit, the most aging for detecting the I &C equipment in nuclear power station, and when detecting that I &C equipment is aging,
Perform the aging grade of this I &C equipment in described identification nuclear power station.
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| CN201210457299.4A CN103811087B (en) | 2012-11-14 | 2012-11-14 | The aging control method of a kind of nuclear power plant instrument control equipment and device |
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| CN201210457299.4A CN103811087B (en) | 2012-11-14 | 2012-11-14 | The aging control method of a kind of nuclear power plant instrument control equipment and device |
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| CN109165747A (en) * | 2018-07-23 | 2019-01-08 | 广东核电合营有限公司 | Nuclear power station steam generator aging and life span management system, method and terminal device |
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| KR100982774B1 (en) * | 2008-09-30 | 2010-09-16 | 한국전력기술 주식회사 | Performance validation apparatus and method for control systems of nuclear power plant |
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Address after: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city in Guangdong province 518031 17-19 floor Applicant after: China General Nuclear Power Corporation Applicant after: Dayawan Nuclear Power Running Management Co., Ltd. Address before: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city in Guangdong province 518031 17-19 floor Applicant before: China Guangdong Nuclear Power Group Co., Ltd. Applicant before: Dayawan Nuclear Power Running Management Co., Ltd. |
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Free format text: CORRECT: APPLICANT; FROM: CHINA GUANGDONG NUCLEAR POWER GROUP CO., LTD. TO: CHINA GENERAL NUCLEAR GROUP CO., LTD. |
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Effective date of registration: 20171019 Address after: Three road CGN building Futian District Shennan Road 518031 Shenzhen City, Guangdong Province, 33 floor, No. 2002 Co-patentee after: Dayawan Nuclear Power Running Management Co., Ltd. Patentee after: China General Nuclear Power Corporation Co-patentee after: Guangdong Nuclear Power Joint Venture Co., Ltd Address before: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city in Guangdong province 518031 17-19 floor Co-patentee before: Dayawan Nuclear Power Running Management Co., Ltd. Patentee before: China General Nuclear Power Corporation |
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Effective date of registration: 20181203 Address after: 518031 33rd Floor, Zhongguanghe Building, No. 2002 Shennan Avenue, Futian District, Shenzhen City, Guangdong Province Co-patentee after: Dayawan Nuclear Power Running Management Co., Ltd. Patentee after: China General Nuclear Power Corporation Co-patentee after: Guangdong Nuclear Power Joint Venture Co., Ltd Co-patentee after: Lingao Nuclear Power Co., Ltd. Address before: 518031 33rd Floor, Zhongguanghe Building, No. 2002 Shennan Avenue, Futian District, Shenzhen City, Guangdong Province Co-patentee before: Dayawan Nuclear Power Running Management Co., Ltd. Patentee before: China General Nuclear Power Corporation Co-patentee before: Guangdong Nuclear Power Joint Venture Co., Ltd |