CN103811087A - Aging control method and device of nuclear power station instrument control equipment - Google Patents
Aging control method and device of nuclear power station instrument control equipment Download PDFInfo
- Publication number
- CN103811087A CN103811087A CN201210457299.4A CN201210457299A CN103811087A CN 103811087 A CN103811087 A CN 103811087A CN 201210457299 A CN201210457299 A CN 201210457299A CN 103811087 A CN103811087 A CN 103811087A
- Authority
- CN
- China
- Prior art keywords
- control equipment
- instrument control
- aging
- level
- 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.)
- Granted
Links
- 230000032683 aging Effects 0.000 title claims abstract description 337
- 238000000034 method Methods 0.000 title claims abstract description 61
- 238000001514 detection method Methods 0.000 claims abstract description 11
- 238000012545 processing Methods 0.000 claims description 63
- 230000008569 process Effects 0.000 claims description 30
- 230000015556 catabolic process Effects 0.000 claims description 10
- 230000008859 change Effects 0.000 claims description 10
- 238000006731 degradation reaction Methods 0.000 claims description 10
- 238000012937 correction Methods 0.000 claims description 5
- 238000004519 manufacturing process Methods 0.000 claims description 5
- 238000012544 monitoring process Methods 0.000 claims description 5
- 230000000737 periodic effect Effects 0.000 claims description 5
- 230000008439 repair process Effects 0.000 claims description 5
- 230000009466 transformation Effects 0.000 claims description 5
- 230000009467 reduction Effects 0.000 claims description 4
- 239000003990 capacitor Substances 0.000 description 13
- 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
- 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
- 230000004069 differentiation Effects 0.000 description 1
- 230000029087 digestion Effects 0.000 description 1
- 238000006073 displacement reaction Methods 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
- 238000012423 maintenance Methods 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
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 229910052710 silicon Inorganic materials 0.000 description 1
- 239000010703 silicon Substances 0.000 description 1
- 229910000679 solder Inorganic materials 0.000 description 1
- 230000000087 stabilizing effect Effects 0.000 description 1
Images
Classifications
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention is applicable to the field of nuclear power control, and provides an aging control method and device of a nuclear power station instrument control device. The method comprises the following steps of grading the aging of each instrument control device in a nuclear power station to obtain an aging stage of each instrument control device; acquiring an aging detection treatment way corresponding to the aging stage of each instrument control device according to the preset corresponding relation between the aging stage and the aging detection treatment way; and controlling the aging of each instrument control device in the nuclear power station by adopting the aging detection treatment way corresponding to the aging stage of each instrument control device. By grading the aging of the instrument control device in the nuclear power station, different aging detection treatment ways are adopted for different instrument control devices of different aging stages, so that the aging treatment cost of different aging stages can be shortened, and the reliability in running of the instrument control device of the nuclear power station also can be improved.
Description
Technical field
The present invention relates to million kilowatt advanced pressurized water reactor nuclear power plant key technology area, relate in particular to aging control method and the device of the nuclear power plant instrument control equipment in above-mentioned field.
Background technology
In million kilowatt advanced pressurized water reactor nuclear power plant, the instrument control number of devices using in nuclear power plant is numerous, the life-span of the part instrument control equipment using in nuclear power plant is less than the designed life of nuclear power plant, in long operational process, there is problem of aging in various degree, the safety of the ageing failure of instrument control equipment on nuclear power plant, the impact that stable operation causes distinct program in these instrument control equipment.Particularly relate to nuclear power station safety total correlation and and the ageing failure of the important instrument control equipment of motor stabilizing operation, the larger economic loss that causes that will give nuclear power plant, even threaten the nuclear safety of unit.Therefore in nuclear power plant, the problem of aging of each instrument control equipment has become the major issue that nuclear power plant need to solve.
The ageing method of the existing instrument control equipment of nuclear power plant is generally to adopt identical aging replacing pattern for all instrument control equipment in nuclear power plant, although this mode has guaranteed the safe operation of nuclear power plant to a certain extent, this mode has increased greatly the aging of instrument control equipment and has controlled cost.
Summary of the invention
The object of the embodiment of the present invention is to provide a kind of aging control method and device of nuclear power plant instrument control equipment, is intended to solve the aging high problem of controlling cost of instrument control equipment.
The embodiment of the present invention is achieved in that the aging control method of instrument control equipment in a kind of nuclear power station, and described method comprises:
Instrument control equipment in nuclear power station is carried out to aging classification processing, obtain the aging grade of each instrument control equipment;
According to the corresponding relation between default aging grade and aging Check processing mode, obtain the aging Check processing mode corresponding with the aging grade of each instrument control equipment;
Adopt the described aging Check processing mode corresponding with the aging grade of each instrument control equipment to carry out aging control to the each instrument control equipment in nuclear power station.
Another object of the embodiment of the present invention is to provide the ageing control device of instrument control equipment in a kind of nuclear power station, and described device comprises:
Aging stage unit, carries out aging classification processing for the instrument control equipment to nuclear power station, obtains the aging grade of each instrument control equipment;
Burin-in process mode acquiring unit, for according to the corresponding relation between default aging grade and aging Check processing mode, obtains the aging Check processing mode corresponding with the aging grade of each instrument control equipment;
Burin-in process unit, for adopting the described aging Check processing mode corresponding with the aging grade of each instrument control equipment to carry out aging control to each instrument control equipment of nuclear power station.
In embodiments of the present invention, carry out aging classification processing by the instrument control equipment to using in nuclear power station, for the instrument control equipment of the aging grade of difference, adopt different aging Check processing modes to process, thereby the burin-in process cost of controlling nuclear power plant instrument control equipment improves nuclear power plant instrument control equipment reliability of operation simultaneously.
Accompanying drawing explanation
Fig. 1 is the realization flow figure of the aging control method of the nuclear power plant instrument control equipment that provides of the embodiment of the present invention;
Fig. 2 is the realization flow figure of the aging control method of the nuclear power plant instrument control equipment that provides of another embodiment of the present invention;
Fig. 3 is the realization flow figure of the aging control method of the nuclear power plant instrument control equipment that provides of yet another embodiment of the invention;
Fig. 4 is the structured flowchart of the ageing control device of the nuclear power plant instrument control equipment that provides of the embodiment of the present invention;
Fig. 5 is the structured flowchart of the ageing control device of the nuclear power plant instrument control equipment that provides of another embodiment of the present invention.
Embodiment
In order to make object of the present invention, technical scheme and advantage clearer, below in conjunction with drawings and Examples, the present invention is further elaborated.Should be appreciated that specific embodiment described herein, only in order to explain the present invention, is not intended to limit the present invention.
In embodiments of the present invention, carry out the aging control of classification and processing by the instrument control equipment in nuclear power station, thereby saved the burin-in process cost of nuclear power plant instrument control equipment, improved nuclear power plant instrument control equipment reliability of operation simultaneously.
For technical solutions according to the invention are described, describe below by specific embodiment.
Fig. 1 shows the realization flow of the aging control method of the nuclear power plant instrument control equipment that the embodiment of the present invention provides, and details are as follows:
S101, carries out aging classification processing to the instrument control equipment in nuclear power station, obtains the aging grade of each instrument control equipment.
Wherein the instrument control equipment in nuclear power station refers to the Instrumentation and Control equipment in nuclear power station, and it includes but not limited to power supply, solenoid valve, flow/pressure fluid level transmitter, transformer, temp probe, switching value primary element, level switch, pressure switch, neutron-flux detector, Electronic Control plate, change-over switch, all kinds of relay, vibration and displacement measurement probe, cable, radiator fan, display, keyboard, mouse etc.Wherein every kind of instrument control equipment comprises one or more components and parts.
Wherein the instrument control equipment in nuclear power station is carried out to aging classification processing, the aging grade that obtains each instrument control equipment specifically comprises: require the instrument control equipment in nuclear power station to carry out aging classification processing according to the safety requirements of nuclear power plant instrument control equipment with to the available rate of nuclear power generating sets, obtain the aging grade of each instrument control equipment.
Wherein require the instrument control equipment in nuclear power station to carry out aging classification processing according to the safety requirements of nuclear power plant instrument control equipment with to the available rate of nuclear power generating sets, the mode of aging grade that obtains each instrument control equipment is specific as follows:
Instrument control 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 instrument control equipment is higher, represents the impact of this instrument control equipment on nuclear plant safety operation or larger on the impact of nuclear power generating sets available rate.
Wherein aging grade is that the instrument control equipment of A level comprises that instrument control equipment relevant to nuclear safety in nuclear power station or single instrument control equipment failure can cause nuclear power station to shut down the instrument control equipment of shutdown; the instrument control equipment that is A level as aging grade includes but not limited to reactor protection loop control logic power supply, Control rod drive line circle, the control plate on evaporator feedwater control loop etc.
Aging grade is that the instrument control equipment of B level comprises the instrument control equipment that the inefficacy because of instrument control equipment in nuclear power station can cause unit available rate to reduce, as the aging grade instrument control equipment that is B level includes but not limited to that three get two, four and get instrument control equipment that two protection loop control logics are relevant etc.
Aging grade is that the instrument control equipment of C level comprises all instrument control equipment except aging grade is A level and B level.
In order to be further convenient to the aging control of instrument control equipment, in another embodiment of the present invention, the method also comprises:
Whether comprise according to instrument control equipment the instrument control equipment that short life components and parts are A level by aging grade and be further divided into A1 level and A2 level, whether comprise according to instrument control equipment the instrument control equipment that short life components and parts are B level by aging grade and be further divided into B1 level and B2 level.
Wherein aging grade is that the instrument control equipment of A1 level comprises that aging grade is the instrument control equipment that contains short life components and parts in the instrument control equipment of A level, as the aging grade instrument control equipment that is A1 level includes but not limited to control plate, the transmitter of evaporator feedwater control channel; The power supply in out-pile neutron-flux detector, reactor protection loop etc.; aging grade is that the instrument control equipment of A2 level comprises that aging grade is the instrument control equipment that does not contain short life components and parts in the instrument control equipment of A level, and the instrument control equipment that is A2 level as aging grade includes but not limited to Control rod drive line circle, control rod rod position measurement probe etc.
Aging grade is that the instrument control equipment of B1 level comprises that aging grade is the instrument control equipment that contains short life components and parts in the instrument control equipment of B level; the instrument control equipment that is B1 level as aging grade includes but not limited to that three get control plate, the transmitter etc. in two protection loops; aging grade is that the instrument control equipment of B2 level comprises that aging grade is the instrument control equipment that does not contain short life components and parts in the instrument control equipment of B level, and the instrument control equipment that is B2 level as aging grade includes but not limited to that non-single failure is shut down, switch, the temp probe etc. of shutdown.
Wherein short life components and parts refer to that short life components and parts include but not limited to electrochemical capacitor, fuse, relay, potentiometer, connector, Zener diode, controllable silicon, high heating resistor, switch, optocoupler, circuit board connector, connection terminal, LED, solder joint, D and D/A converter, battery etc. because material structure or working mechanism cause its life-span to be significantly less than the components and parts of the designed life of its integral device of serving.
It should be noted that, the above-mentioned hierarchical approaches to the each instrument control equipment in nuclear power station is only wherein a kind of concrete mode that the embodiment of the present invention provides, safety requirements according to nuclear power station to instrument control equipment and the available rate of nuclear power generating sets require the detailed process of the instrument control equipment in nuclear power station being carried out to aging classification processing not state above bright being limited, can also be according to nuclear power station the security requirement to instrument control equipment and the available rate of nuclear power generating sets is required the instrument control equipment in nuclear power station to be divided into other grades, as be divided into superfine, senior, intermediate and rudimentary four ranks etc., do not limit at this, also no longer exhaustive.
S102, according to the corresponding relation between default aging grade and aging Check processing mode, obtains the aging Check processing mode corresponding with the aging grade of each instrument control equipment.
In the present embodiment, aging Check processing mode includes but not limited to aging sense cycle, burin-in process mode etc.Grade as aging in the difference for instrument control equipment, different aging sense cycle can be set, grade as aging in the height for instrument control equipment, shorter aging sense cycle is set, for the low aging grade of instrument control equipment, be set longer digestion period, or different burin-in process modes is set, grade as aging in the height for instrument control equipment, its burin-in process mode is set for directly changing, for the low aging grade of instrument control equipment, its burin-in process mode is set for maintenance, until instrument control equipment is changed during because of ageing failure again, or be set the different replacement cycles.
In the present embodiment, set in advance the corresponding relation between aging grade and aging Check processing mode, to carry out identical aging Check processing to thering is the instrument control equipment of same aging grade.Corresponding relation between the aging grade wherein setting in advance and aging Check processing mode is as described in Table 1, but be not limited with table 1, can also be according to the demand of different nuclear power station, other corresponding relations between aging grade and aging Check processing mode are set, illustrate no longer one by one at this:
| Aging grade | Aging Check processing mode |
| A1 level | Regularly replace aging instrument control equipment, and the performance parameter of periodic monitoring instrument control equipment |
| B1 level | Regularly replace the components and parts in aging instrument control equipment or aging instrument control equipment |
| A2 level | Regularly detect, change and agingly degrade or the components and parts of degradation failure |
| B2 level | Regularly detect, change and agingly degrade or the components and parts of degradation failure |
| C level | Keep in repair as main take correction property, for the short equipment that stops production, replace or transformation and upgrade |
In the present embodiment, instrument control equipment in nuclear power station is carried out to aging classification processing, obtain after the aging grade of each instrument control equipment, the aging grade of instrument control equipment can be mated with the corresponding relation between aging grade and the aging Check processing mode preset, to get the aging Check processing mode corresponding to aging grade of this instrument control equipment.
S103, adopts the aging Check processing mode corresponding with the aging grade of each instrument control equipment to carry out aging control to the each instrument control equipment in nuclear power station.
In the present embodiment, getting after the aging Check processing mode corresponding with the aging grade of each instrument control equipment, can adopt this aging Check processing mode to carry out aging control to the each instrument control equipment in nuclear power station.
Specific as follows:
In the time that the aging grade of instrument control equipment is A1 level, regularly replace aging instrument control equipment, and the performance parameter of periodic monitoring instrument control equipment;
In the time that the aging grade of instrument control equipment is A2 level, regularly detect, change and agingly degrade or the components and parts of degradation failure;
In the time that the aging grade of instrument control equipment is B1 level, regularly replace the components and parts in aging instrument control equipment or aging instrument control equipment;
In the time that the aging grade of instrument control equipment is B2 level, regularly detect, change and agingly degrade or the components and parts of degradation failure;
In the time that the aging grade of instrument control equipment is C level, keep in repair as main take correction property, for the short equipment that stops production, replace or transformation and upgrade.
In embodiments of the present invention, carry out aging classification processing by the instrument control equipment to using in nuclear power station, for the instrument control equipment of the aging grade of difference, adopt different aging Check processing modes to process, thereby the burin-in process cost of controlling nuclear power plant instrument control equipment improves nuclear power plant instrument control equipment reliability of operation simultaneously.
Fig. 2 shows the realization flow of the aging control method of the nuclear power plant instrument control equipment that another embodiment of the present invention provides, and details are as follows:
S201, carries out aging classification processing to the instrument control equipment in nuclear power station, obtains the aging grade of each instrument control equipment.Its detailed process is described above, does not repeat them here.
S202, the aging grade of the instrument control equipment in identification nuclear power station.
In the present embodiment, for the various instrument control equipment in nuclear power station, need to identify the aging grade of this instrument control equipment.The detailed process of aging grade of wherein identifying instrument control equipment is as follows:
Judge whether instrument control equipment is that instrument control equipment or the single failure relevant to nuclear safety can cause nuclear power station to shut down the instrument control equipment of shutdown; if; the aging grade of judging this instrument control equipment is A level; further judge whether this instrument control equipment comprises short life components and parts; if; the aging grade of judging this instrument control equipment is A1 level, if this instrument control equipment does not comprise short life components and parts, the aging grade of judging this instrument control equipment is A2 level.
Judge whether instrument control equipment is the instrument control equipment that can cause unit available rate to reduce because of the inefficacy of instrument control equipment, if, the aging grade of judging this instrument control equipment is B level, further judge whether this instrument control equipment comprises short life components and parts, if, the aging grade of judging this instrument control equipment is B1 level, if this instrument control equipment does not comprise short life components and parts, the aging grade of judging this instrument control equipment is B2 level.
When instrument control equipment is not that instrument control equipment or the single failure relevant to nuclear safety can cause nuclear power station to shut down the instrument control equipment of shutdown; the instrument control equipment that neither can cause because of the inefficacy of instrument control equipment the reduction of unit available rate, the aging grade of judging this instrument control equipment is C level.
S203, according to the corresponding relation between default aging grade and aging Check processing mode, obtains the aging Check processing mode corresponding with the aging grade of each instrument control equipment.Its detailed process is described above, does not repeat them here.
S204, adopts the aging Check processing mode corresponding with the aging grade of each instrument control equipment to carry out aging control to the each instrument control equipment in nuclear power station.Its detailed process is described above, does not repeat them here.
In embodiments of the present invention, by instrument control equipment investment when using in nuclear power station, by identifying the aging grade of this instrument control equipment, thereby can carry out aging control to any instrument control equipment in nuclear power station.
Fig. 3 shows the realization flow of the aging control method of the nuclear power plant instrument control equipment that another embodiment of the present invention provides, the method is on the basis of the aging control method based on shown in Fig. 1 or Fig. 2, with based on figure, the basis of the aging control method shown in 2 is example below, and details are as follows:
S301, carries out aging classification processing to the instrument control equipment in nuclear power station, obtains the aging grade of each instrument control equipment.Its detailed process is described above, does not repeat them here.
S302, whether the instrument control equipment in detection nuclear power station is aging, and in the time detecting instrument control ageing equipment, the aging grade of this instrument control equipment in identification nuclear power station.
In the present embodiment, for the each instrument control equipment using in nuclear power station, whether agingly first detect each instrument control equipment, if aging, identify the aging grade of this aging instrument control equipment.
The whether aging detailed process of instrument control equipment in the detection nuclear power station providing with the concrete example explanation embodiment of the present invention below:
Refer to table 2, for the embodiment of the present invention provides the corresponding relation between aging action, agine mechaism and the ageing failure pattern of short life components and parts, and table 3, the corresponding relation between aging action, agine mechaism and the ageing failure pattern of the instrument control equipment providing for the embodiment of the present invention.
Table 2
Table 3
Can obtain according to the corresponding relation shown in table 2 and table 3:
Detect the concrete steps whether electrochemical capacitor is aging as follows:
Detect the electrolytical loss of electrochemical capacitor, whether electrochemical capacitor ruptures, whether electrochemical capacitor sealing lost efficacy, and whether electrochemical capacitor exists open fault, and whether electrochemical capacitor exists one or more in short trouble, when the electrolytical loss of electrochemical capacitor reaches predetermined threshold value, electrochemical capacitor fracture, electrochemical capacitor seal failure, there is open fault in electrochemical capacitor, when electrochemical capacitor exists one or more situations in short trouble, judge that electrochemical capacitor is aging.
Detect the concrete steps whether fuse is aging as follows:
Detect the fuse electromigration of whether metallizing, whether fuse there is evaporation of metal phenomenon, whether fuse corrodes, one or more during whether the encapsulant of fuse is aging, when metallization electromigration occurs fuse, there is evaporation of metal phenomenon in fuse, and fuse corrodes, when one or more during the encapsulant of fuse is aging, judge that fuse is aging.
For other short life components and parts and other instrument control equipment, its aging detection principle is the same, illustrates no longer one by one at this.
S303, according to the corresponding relation between default aging grade and aging Check processing mode, obtains the aging Check processing mode corresponding with the aging grade of each instrument control equipment.Its detailed process is described above, does not repeat them here.
S304, adopts the aging Check processing mode corresponding with the aging grade of each instrument control equipment to carry out aging control to the each instrument control equipment in nuclear power station.Its detailed process is described above, does not repeat them here.
In embodiments of the present invention, whether aging by the instrument control equipment using in automatic detection nuclear power station, in the time of instrument control ageing equipment, the aging grade of identification instrument control equipment, and adopt the aging Check processing mode corresponding with this aging grade to carry out aging control to instrument control equipment, thereby make the aging control and management of instrument control equipment more convenient, flexible.
Fig. 4 shows the structure of the ageing control device of instrument control equipment in the nuclear power station that the embodiment of the present invention provides, and only shows for convenience of explanation the part relevant to the embodiment of the present invention.This device comprises:
Aging stage unit 1 carries out aging classification processing for the instrument control equipment to nuclear power station, obtains the aging grade of each instrument control equipment.
In another embodiment of the present invention, this aging stage unit 1, specifically for requiring the instrument control equipment in nuclear power station to carry out aging classification processing according to the safety requirements of instrument control equipment in nuclear power station and the available rate of nuclear power generating sets, obtains the aging grade of each instrument control equipment.
In another embodiment of the present invention; this aging stage unit 1 is specifically for being divided into the instrument control equipment in nuclear power station A level, B level and three aging grades of C level; wherein in nuclear power station the instrument control equipment relevant to nuclear safety or single failure can to cause the aging grade of the instrument control equipment of shutting down shutdown be A level; in nuclear power station, be B level because the inefficacy of instrument control equipment can cause the aging grade of the instrument control equipment of unit available rate reduction, the aging grade of all the other the instrument control equipment in nuclear power station is C level.
In another embodiment of the present invention, this device also comprises classification subelement 4.This classification subelement 4 is further divided into A1 level and A2 level for whether contain the instrument control equipment that short life components and parts are A level by aging grade according to instrument control equipment, the instrument control equipment that is B level by aging grade is further divided into B1 level and B2 level, wherein aging grade is that the aging grade of the instrument control equipment that contains short life components and parts in the instrument control equipment of A level is A1 level, the aging grade that does not contain the instrument control equipment of short life components and parts is A2 level, aging grade is that the aging grade of the instrument control equipment that contains short life components and parts in the instrument control equipment of B level is B1 level, the aging grade that does not contain the instrument control equipment of short life components and parts is B2 level.
Burin-in process mode acquiring unit 2, for according to the corresponding relation between default aging grade and aging Check processing mode, obtains the aging Check processing mode corresponding with the aging grade of each instrument control equipment.Its detailed process is described above, does not repeat them here.
Burin-in process unit 3 is for adopting the described aging Check processing mode corresponding with the aging grade of each instrument control equipment to carry out aging control to each instrument control equipment of nuclear power station.
In the preferred embodiment of the present invention, this burin-in process unit 3 specifically for
In the time that the aging grade of instrument control equipment is A1 level, regularly replace aging instrument control equipment, and the performance parameter of periodic monitoring instrument control equipment;
In the time that the aging grade of instrument control equipment is A2 level, regularly detect, change and agingly degrade or the components and parts of degradation failure;
In the time that the aging grade of instrument control equipment is B1 level, regularly replace the components and parts in aging instrument control equipment or aging instrument control equipment;
In the time that the aging grade of instrument control equipment is B2 level, regularly detect, change and agingly degrade or the components and parts of degradation failure;
In the time that the aging grade of instrument control equipment is C level, keep in repair as main take correction property, for the short equipment that stops production, replace or transformation and upgrade.
Fig. 5 shows the structure of the ageing control device of instrument control equipment in the nuclear power station that another embodiment of the present invention provides, and only shows for convenience of explanation the part relevant to the embodiment of the present invention.This device, on the basis of the device shown in Fig. 4, has increased following part:
This device also comprises aging grade recognition unit 5.This aging grade recognition unit 5 is for identifying the aging grade of instrument control equipment of nuclear power station.Wherein the detailed process of concrete aging grade identification is described above, does not repeat them here.
In another embodiment of the present invention, this device also comprises aging detecting unit 6.Whether this aging detecting unit 6 is aging for detection of the instrument control equipment in nuclear power station, and in the time detecting instrument control ageing equipment, carries out the aging grade of this instrument control equipment in described identification nuclear power station.
It should be noted that said system, included unit is just divided according to function logic, but is not limited to above-mentioned division, as long as can realize corresponding function; In addition, the concrete title of each functional unit also, just for the ease of mutual differentiation, is not limited to protection scope of the present invention.
One of ordinary skill in the art will appreciate that, the all or part of step realizing in above-described embodiment method is can carry out the hardware that instruction is relevant by program to complete, described program can be being stored in a computer read/write memory medium, described storage medium, as ROM/RAM, disk, CD etc.
In embodiments of the present invention, carry out aging classification processing by the instrument control equipment to using in nuclear power station, for the instrument control equipment of the aging grade of difference, adopt different aging Check processing modes to process, thereby the burin-in process cost of controlling nuclear power plant instrument control equipment improves nuclear power plant instrument control equipment reliability of operation simultaneously.
The foregoing is only preferred embodiment of the present invention, not in order to limit the present invention, all any modifications of doing within the spirit and principles in the present invention, be equal to and replace and improvement etc., within all should being included in protection scope of the present invention.
Claims (14)
1. an aging control method for instrument control equipment in nuclear power station, is characterized in that, described method comprises:
Instrument control equipment in nuclear power station is carried out to aging classification processing, obtain the aging grade of each instrument control equipment;
According to the corresponding relation between default aging grade and aging Check processing mode, obtain the aging Check processing mode corresponding with the aging grade of each instrument control equipment;
Adopt the described aging Check processing mode corresponding with the aging grade of each instrument control equipment to carry out aging control to the each instrument control equipment in nuclear power station.
2. the method for claim 1, is characterized in that, described instrument control equipment in nuclear power station is carried out to aging classification processing, and the aging grade that obtains each instrument control equipment specifically comprises:
Require the instrument control equipment in nuclear power station to carry out aging classification processing according to the safety requirements of instrument control equipment in nuclear power station and the available rate of nuclear power generating sets, obtain the aging grade of each instrument control equipment.
3. method as claimed in claim 2, is characterized in that, requires the instrument control equipment in nuclear power station to carry out aging classification processing according to the safety requirements of instrument control equipment in nuclear power station and the available rate of nuclear power generating sets, and the aging grade that obtains each instrument control equipment specifically comprises:
Instrument control equipment in nuclear power station is divided into A level, B level and three aging grades of C level; wherein in nuclear power station the instrument control equipment relevant to nuclear safety or single failure can to cause the aging grade of the instrument control equipment of shutting down shutdown be A level; in nuclear power station, be B level because the inefficacy of instrument control equipment can cause the aging grade of the instrument control equipment of unit available rate reduction, the aging grade of all the other the instrument control equipment in nuclear power station is C level.
4. method as claimed in claim 3, is characterized in that, described method also comprises:
Whether contain according to instrument control equipment the instrument control equipment that short life components and parts are A level by aging grade and be further divided into A1 level and A2 level, the instrument control equipment that is B level by aging grade is further divided into B1 level and B2 level, wherein aging grade is that the aging grade of the instrument control equipment that contains short life components and parts in the instrument control equipment of A level is A1 level, the aging grade that does not contain the instrument control equipment of short life components and parts is A2 level, aging grade is that the aging grade of the instrument control equipment that contains short life components and parts in the instrument control equipment of B level is B1 level, the aging grade that does not contain the instrument control equipment of short life components and parts is B2 level.
5. the method for claim 1, is characterized in that, the aging Check processing mode corresponding with the aging grade of each instrument control equipment carried out aging control to the each instrument control equipment in nuclear power station and specifically comprised described in described employing:
In the time that the aging grade of instrument control equipment is A1 level, regularly replace aging instrument control equipment, and the performance parameter of periodic monitoring instrument control equipment;
In the time that the aging grade of instrument control equipment is A2 level, regularly detect, change and agingly degrade or the components and parts of degradation failure;
In the time that the aging grade of instrument control equipment is B1 level, regularly replace the components and parts in aging instrument control equipment or aging instrument control equipment;
In the time that the aging grade of instrument control equipment is B2 level, regularly detect, change and agingly degrade or the components and parts of degradation failure;
In the time that the aging grade of instrument control equipment is C level, keep in repair as main take correction property, for the short equipment that stops production, replace or transformation and upgrade.
6. the method for claim 1, it is characterized in that, corresponding relation between described basis default aging grade and aging Check processing mode, before obtaining the aging Check processing mode corresponding with the aging grade of each instrument control equipment, described method also comprises:
The aging grade of the instrument control equipment in identification nuclear power station.
7. method as claimed in claim 6, is characterized in that, before the aging grade of the instrument control equipment in described identification nuclear power station, described method also comprises:
Whether the instrument control equipment in detection nuclear power station is aging, and in the time detecting instrument control ageing equipment, carry out the aging grade of this instrument control equipment in described identification nuclear power station.
8. an ageing control device for instrument control equipment in nuclear power station, is characterized in that, described device comprises:
Aging stage unit, carries out aging classification processing for the instrument control equipment to nuclear power station, obtains the aging grade of each instrument control equipment;
Burin-in process mode acquiring unit, for according to the corresponding relation between default aging grade and aging Check processing mode, obtains the aging Check processing mode corresponding with the aging grade of each instrument control equipment;
Burin-in process unit, for adopting the described aging Check processing mode corresponding with the aging grade of each instrument control equipment to carry out aging control to each instrument control equipment of nuclear power station.
9. device as claimed in claim 8, it is characterized in that, described aging stage unit, specifically for requiring the instrument control equipment in nuclear power station to carry out aging classification processing according to the safety requirements of instrument control equipment in nuclear power station and the available rate of nuclear power generating sets, obtains the aging grade of each instrument control equipment.
10. device as claimed in claim 9; it is characterized in that; described aging stage unit is specifically for being divided into the instrument control equipment in nuclear power station A level, B level and three aging grades of C level; wherein in nuclear power station the instrument control equipment relevant to nuclear safety or single failure can to cause the aging grade of the instrument control equipment of shutting down shutdown be A level; in nuclear power station, be B level because the inefficacy of instrument control equipment can cause the aging grade of the instrument control equipment of unit available rate reduction, the aging grade of all the other the instrument control equipment in nuclear power station is C level.
11. devices as claimed in claim 10, is characterized in that, described device also comprises:
Classification subelement, be further divided into A1 level and A2 level for whether containing according to instrument control equipment the instrument control equipment that short life components and parts are A level by aging grade, the instrument control equipment that is B level by aging grade is further divided into B1 level and B2 level, wherein aging grade is that the aging grade of the instrument control equipment that contains short life components and parts in the instrument control equipment of A level is A1 level, the aging grade that does not contain the instrument control equipment of short life components and parts is A2 level, aging grade is that the aging grade of the instrument control equipment that contains short life components and parts in the instrument control equipment of B level is B1 level, the aging grade that does not contain the instrument control equipment of short life components and parts is B2 level.
12. devices as claimed in claim 8, is characterized in that, described burin-in process unit specifically for
In the time that the aging grade of instrument control equipment is A1 level, regularly replace aging instrument control equipment, and the performance parameter of periodic monitoring instrument control equipment;
In the time that the aging grade of instrument control equipment is A2 level, regularly detect, change and agingly degrade or the components and parts of degradation failure;
In the time that the aging grade of instrument control equipment is B1 level, regularly replace the components and parts in aging instrument control equipment or aging instrument control equipment;
In the time that the aging grade of instrument control equipment is B2 level, regularly detect, change and agingly degrade or the components and parts of degradation failure;
In the time that the aging grade of instrument control equipment is C level, keep in repair as main take correction property, for the short equipment that stops production, replace or transformation and upgrade.
13. devices as claimed in claim 8, is characterized in that, described device also comprises:
Aging grade recognition unit, for identifying the aging grade of instrument control equipment of nuclear power station.
14. devices as claimed in claim 13, is characterized in that, described device also comprises:
Aging detecting unit, whether aging for detection of the instrument control equipment in nuclear power station, and in the time detecting instrument control ageing equipment, carry out the aging grade of this instrument control equipment in described identification nuclear power station.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| 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 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| 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 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN103811087A true CN103811087A (en) | 2014-05-21 |
| CN103811087B CN103811087B (en) | 2016-08-17 |
Family
ID=50707739
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201210457299.4A Active CN103811087B (en) | 2012-11-14 | 2012-11-14 | The aging control method of a kind of nuclear power plant instrument control equipment and device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN103811087B (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109146210A (en) * | 2017-06-16 | 2019-01-04 | 苏州热工研究院有限公司 | A kind of nuclear power plant's substantial equipment assets long-period of management planning method and device |
| 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 |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1191019A (en) * | 1995-06-07 | 1998-08-19 | 格伦·利迪 | Method and apparatus for probing, testing, burn-in, repairing and programming of integrated circuits in a closed environment using a single apparatus |
| CN101713995A (en) * | 2008-09-30 | 2010-05-26 | 韩国电力技术株式会社 | Performance validation apparatus and method for control systems of nuclear power plant |
| CN202421448U (en) * | 2011-12-14 | 2012-09-05 | 中国广东核电集团有限公司 | Relay detecting device for nuclear power stations |
| WO2012151346A1 (en) * | 2011-05-03 | 2012-11-08 | Dermachip Inc. | Expression signatures of genes and gene networks associated with skin aging |
-
2012
- 2012-11-14 CN CN201210457299.4A patent/CN103811087B/en active Active
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1191019A (en) * | 1995-06-07 | 1998-08-19 | 格伦·利迪 | Method and apparatus for probing, testing, burn-in, repairing and programming of integrated circuits in a closed environment using a single apparatus |
| CN101713995A (en) * | 2008-09-30 | 2010-05-26 | 韩国电力技术株式会社 | Performance validation apparatus and method for control systems of nuclear power plant |
| WO2012151346A1 (en) * | 2011-05-03 | 2012-11-08 | Dermachip Inc. | Expression signatures of genes and gene networks associated with skin aging |
| CN202421448U (en) * | 2011-12-14 | 2012-09-05 | 中国广东核电集团有限公司 | Relay detecting device for nuclear power stations |
Non-Patent Citations (4)
| Title |
|---|
| INTERNATIONAL ATOMIC ENERGY AGENCY: "Ageing Management for Nuclear Power Plants", 《IAEA SAFETY STANDARDS FOR PROTECTING PEOPLE AND THE ENVIRONMENT》, 31 December 2009 (2009-12-31) * |
| 卢文跃 等: "核电站设备可靠性管理体系的探索与运作", 《核动力工程》, vol. 26, no. 6, 31 December 2005 (2005-12-31) * |
| 王伟 等: "核电站老化分析及延寿管理方法研究", 《机电产品开发与创新》, vol. 22, no. 3, 31 May 2009 (2009-05-31) * |
| 高立刚 等: "大亚湾核电站设备可靠性管理体系创新", 《核科学与工程》, vol. 26, no. 2, 30 June 2006 (2006-06-30) * |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109146210A (en) * | 2017-06-16 | 2019-01-04 | 苏州热工研究院有限公司 | A kind of nuclear power plant's substantial equipment assets long-period of management planning method and device |
| 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 |
Also Published As
| Publication number | Publication date |
|---|---|
| CN103811087B (en) | 2016-08-17 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN101782746B (en) | Monitoring device and monitoring method | |
| CN105449831A (en) | Main-auxiliary power supply automatic switching system and method | |
| CN107276036B (en) | A kind of CS sampling resistor short-circuit protection of Switching Power Supply | |
| CN100373575C (en) | Method for monitoring abnormality of technology process in semiconductor equipment | |
| KR102371197B1 (en) | Protection system of energy storage system | |
| CN103811087A (en) | Aging control method and device of nuclear power station instrument control equipment | |
| CN104412480A (en) | In-car power supply apparatus | |
| CN102780207B (en) | voltage protection system and method | |
| CN100517261C (en) | Fan working condition detection method and detection device | |
| CN110360064B (en) | Wind generating set control method and wind generating set | |
| CN206353706U (en) | A kind of electric equipment and its power-down protection circuit | |
| CN109884878B (en) | Control circuit with switching function and switching method of control circuit | |
| CN214404144U (en) | Speed regulation oil system of water turbine | |
| CN104331061A (en) | Test method and test device of core board of distribution network terminal device | |
| CN102237712A (en) | Multi-power system and power failure processing method | |
| CN105022329A (en) | Water leakage prompting system and control method thereof | |
| US10566833B2 (en) | External battery backup unit | |
| CN106291086A (en) | A kind of electric energy meter metering abnormality detection and restoration methods | |
| CN102644307B (en) | Method forcontrolling equipment for realizing simple operation of single-pump variable-frequency unit | |
| CN109524132B (en) | Control method and control system applied to spent fuel pool cooling branch | |
| CN104198203A (en) | Method and device for detecting operation of air-conditioners | |
| CN103439950B (en) | A kind of automatic start-stop detection method and system being applied to water system | |
| CN208752958U (en) | The under-voltage protecting circuit and embedded system of storage chip | |
| CN103529824A (en) | Stability test method and system | |
| CN113299418A (en) | Safety injection triggering method, device and system for nuclear power plant under shutdown working condition after shutdown of main pump |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C53 | Correction of patent of invention or patent application | ||
| CB02 | Change of applicant information |
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. |
|
| COR | Change of bibliographic data |
Free format text: CORRECT: APPLICANT; FROM: CHINA GUANGDONG NUCLEAR POWER GROUP CO., LTD. TO: CHINA GENERAL NUCLEAR GROUP CO., LTD. |
|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| TR01 | Transfer of patent right |
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 |
|
| TR01 | Transfer of patent right | ||
| TR01 | Transfer of patent right | ||
| TR01 | Transfer of patent right |
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 |