Summary of the invention
Based on this, the purpose of this invention is to provide a kind of method of utilizing transient statistic to realize device security is monitored, this method notifies the operation conditions of equipment at once, with the normal operation of service equipment by collection, analysis to device data.
Another object of the present invention provides a kind of transient statistic that utilizes and realizes that this method is especially carried out real-time data acquisition, analysis by computing machine to equipment to the method for device security monitoring, and forms operational report, the ruuning situation of watch-dog.
Thinking of the present invention is:
Practical experience according to the nuclear power station operation, analyze from the nuclear power plant reactor various operating modes that may occur in service, summarize some typical conditions from the angle that produces stress intensity, and, work out out the benchmark transition and provide the occurrence number that each benchmark transition must not surpass in the whole phase in longevity in the power station based on the frequency size that stress analysis and run duration to these typical conditions occur.
In operational process, transient changing (transition) at the reality generation, by analyzing temperature, the pressure and other parameters situation of change of being gathered, compare with the evolution characteristics of temperature, pressure and other parameters under the corresponding operating mode of benchmark transition, actual transition is classified as certain class benchmark transition following under conservative, the content to retain sovereignty over a part of the country full principle.Like this, in the phase in power station longevity,, so just can think that the bearing device of correspondence is in safe condition as long as actual transition is all contained by the benchmark transition and frequency is no more than the permission frequency of each benchmark transition respectively.Surpass the benchmark transition at actual transition content, or frequency surpasses the situation that the benchmark transition allows number of times, must be by the case individual processing: carry out actual stress analysis and analysis result fed back to the range of definition of benchmark transition and allow on the number of times, this second half that is operated in the phase in power station longevity can seem especially important.
Therefore, the present invention is achieved in that
A kind of method of utilizing transient statistic to realize device security is monitored is to utilize the monitoring of computer realization to device security, and this method may further comprise the steps:
A, determine the basic value of transition, set in advance the transition basic value of equipment, also cry basic transition according to equipment permission situation;
B, data acquisition: comprising the data of equipment and instrument are carried out information acquisition, mainly is that all controlled variable in nuclear power plant reactor loop are carried out data acquisition,
C, transient detection: to the various data of gathering, especially real-time physical parameter is carried out statistical study, and contrast has or not the situation that surpasses basic transition,
D, transition sort out: the situation that surpasses basic transition carried out transition sort out, determine its corresponding equipment and type, and judge aforesaid reality a situation arises whether can be contained by basic transition,
E, transition prompting: under the principle of safety, after transition sorted out, the above-mentioned reality situation that a situation arises surpasses basic transition is pointed out, and with this information stores,
F. export the transient statistic result: with above-mentioned information with and corresponding equipment gather, and form report output, handle for carrying out actual analysis and each case.
Described transition being sorted out, is that a situation arises divides according to the type of basic transition with reality, promptly its transition is classified as its most approaching basic transition type under the principle of safety.
Common data acquisition comprises temperature, pressure, flow, the isoparametric chained record of valve switch signal.These records are summarised in the accurate status that can react each equipment together exactly, so that accurately judge the permission situation of each equipment.
The value of basic transition is the transient statistics according to history, union goes out the actual basic transient that does not influence equipment operation that is taken place, this basic transition is as the actual contrast that a situation arises, and allow suitable error (also being threshold values) to exist, if exceed this error, then enter transition prompting step, the prompting monitor staff notes the operation conditions of equipment, and in time safeguards and keep in repair.
Above-mentioned threshold values comprises time threshold values and index threshold values, i.e. the threshold values of the concrete variation in plant parameters of expression such as temperature threshold values, pressure threshold value, flow threshold values.
Above-mentioned threshold values is provided with time threshold and index threshold values and constitutes threshold window; The monitoring actual curve do not surpass threshold window the time do not add up and be transition, surpassing then, statistics is transition.
After transition takes place, can determine the starting point and the terminal point of transition by mobile threshold window, then the starting point of transition and the parameter actual change curve between the terminal point are compared with design transition curve, when the curve of design transition can contain the parameter change curve of actual transition and is that all design the most approaching actual transition curve in transition curves, the transient statistic of reality generation is become this design transition.
For the transition of recurring, statistics is 2 transitions during the time phase difference overtime threshold values of first and second portion, and it is 1 transition that the mistiming was then added up during threshold values less than the time.
For the transition of discontinuous fluctuation, no matter whether the mistiming of its first, second portion is greater than the time threshold values, all by transient statistic independently.
When partial circulating (Sub-Cycle) takes place when, when the mistiming of first, second portion during the overtime threshold values statistics partial circulating be independently transition; Be not transition otherwise do not add up.
Described transition, its occurrence frequency and cumulative number are recorded into data in the lump, and compare with basic transition, if exceed the corresponding record of basic transition, then enter transition prompting step.
Described basic transition, it also is stored in the computing machine at the number of times that normal operation takes place, after the actual actual transition that takes place ranged basic transition, its frequency of computer monitoring was if the number of times that takes place is lower than the frequency of basic transition, determine that then equipment is for safe condition, if exceed the frequency of this basic transition, then send prompting, detect maintenance by the engineering staff, perhaps carry out case and judge, judge whether under safe condition.The frequency of basic transition is to determine according to the different ruuning situations of each equipment.
The described transient statistic that utilizes realizes that it is applied in the monitoring of nuclear power station to the method for device security monitoring, and transition can be divided into 4 classes when sorting out: 1 class is design conditions; 2 classes are general operating condition and middle events of equal probability (as the ascending, descending load); 3 classes are small probability event (as a loop minor break); 4 classes are minimum probability event (as a loop large break).
Described transition and basic transition, its data all are stored in the computing machine, and can read at any time, so that add up and check.
Described output transient statistic result, be that a situation arises gathers with transition, generate report automatically and propose, also can comprise warning to each office terminal, promptly carry out alarm, carry out each case analysis by each office terminal or supvr to surpassing predetermined transition.
The described method of utilizing transient statistic to realize device security is monitored, whether this method constantly will be carried out safety analysis in the transient statistic process, be in a safe condition with judgment device.As long as each benchmark transition accumulative total frequency is lower than permissible value, just can determines that bearing device is safe certainly, otherwise will carry out case analysis as the case may be, and adjust the benchmark transition and allow frequency according to the stress analysis result.Concrete analytical approach is the threshold values and the difference of basic transition and the number of times of transition generation of correlation data transition, if in the covering scope of basic transition, then think safe, if exceeded the covering scope of basic transition, then should be actual the threshold values that takes place of transition carry out each actual case with number of times and make a concrete analysis of, and the actual conditions of bonding apparatus determine whether it exists safety problem.
The present invention adopts above-mentioned method, timely watch-dog operation conditions aborning, especially under the situation that nuclear power plant equipment is not easy to monitor, adopt above-mentioned method, feasible monitoring intelligentization to equipment, and rapidly in time, be convenient to grasp the ruuning situation of all devices, carry out security control.
The result of long term monitoring can gather, and as the reference to the equipment operation monitoring, in time the hidden danger of discovering device can ensure the trouble-free operation of production system.
Embodiment
At first, following enforcement of the present invention is to supervise according to the device security of nuclear power station to propose, and shown in Figure 1, performing step of the present invention is:
1 data acquisition
Under the control of computing machine, adopt the in-line meter system to 45 temperature of reactor-loop, pressure, flow, the isoparametric continuous recording of valve switch signal (this is recorded in 40 year phase in longevity interior realization continuous monitoring in power station), gather raw data, the raw data of gathering feeds back to computing machine and carries out record
2 transient detection
Then the physical parameter of gathering being analyzed, at first is to carry out transient detection: check that promptly the temperature and pressure parameter has or not the situation that defined threshold occurs surpassing, just explanation does not have transition to take place, and has just representative to have transition to take place, and must carry out analytic statistics.
Temperature and pressure change threshold commonly used
Reactor cooling system (RCP) temperature variation: Δ T
RCP>5℃/3h
|
Chemistry and volume control system (RCV) temperature variation: Δ T
RCV>20℃/h
|
Waste heat guiding system (RRA) temperature variation: Δ T
RRA>20℃/h
|
Reactor cooling system (RCP) pressure changes: Δ P
RCP>10bar
|
Steam generator (SG) pressure changes: Δ P
SG>5bar
|
Determine that with threshold value the method for transition sees Fig. 2.With the temperature analysis is example, among the figure: t
sBe time threshold (RCP is 3h, and other is 1h) that Ts is a temperature threshold.With t
sBe length, Ts is the high threshold window that constitutes; Do not add up transition when actual curve surpasses threshold window, surpass then statistics.
3 transitions are sorted out
It is exactly characteristics, operation and other supplementary that develops according to parameter that transition is sorted out, determine to belong to which kind of benchmark operating condition, and judge which benchmark transition can contain the evolutionary process of actual transition, classify as corresponding the most approaching benchmark transition following the actual transition that will take place under the complete principle content to retain sovereignty over a part of the country.So-called full principle content to retain sovereignty over a part of the country is exactly to guarantee that the parameter intensity of variation of actual transition necessarily can not be more serious than benchmark transition, and the stress influence that only in this way could guarantee actual transition is littler than benchmark transition.
Change the situation that can not contain by the benchmark transition in case the parameter of actual transition occurs, do not judge blindly, but need carry out case analysis, judge whether it works the mischief to equipment, and adjust the benchmark transition and allow frequency according to the stress analysis result.
And transition judged the standard of judgement has two, and the one, whether its transition threshold values surpasses basic transition, but whether the number of times that is taken place surpasses the frequency of basic transition.
After determining that transition takes place, can determine the starting point and the terminal point of transition by mobile threshold window, then the starting point of transition and the parameter actual change curve between the terminal point are compared with design transition curve, when the curve of design transition can contain the parameter change curve of actual transition and is that all design the most approaching actual transition curve in transition curves, the transient statistic of reality generation is become this design transition.Details are as follows:
Determine the actual change curve of transition
1) judgement of transition Origin And Destination is seen Fig. 3, t
0Be the starting point of transition, t
1Terminal point for transition.
2) Fig. 4 and Fig. 5 are seen in the differentiation of transition continuously.When actual curve variation tendency such as Fig. 4,1st part and 2nd partly differ above t
s2 transitions of Shi Tongji.T in Fig. 5
2-t
1<t
s1 transition of Shi Tongji.
3) Fig. 6 is seen in the differentiation of fluctuation transition, no matter Δ t
1, Δ t
2Whether greater than t
s, all by independent transient statistic.
4) Fig. 7 is seen in the judgement of partial circulating (Sub-Cycle).As Δ T>T
sThe Shi Tongji partial circulating is independent transition; As Δ T<T
sThe time do not add up partial circulating, referring to Fig. 5.
The design transient code
Illustrate and see following form for details.Transition can be divided into 4 classes: 1 class is design conditions; 2 classes are general operating condition and middle events of equal probability (as the ascending, descending load); 3 classes are small probability event (as a loop minor break); 4 classes are minimum probability event (as a loop large break).
Transient code | Transition is described | The design number of times |
| One loop transition 1. normally moves | |
1.1 1.2 2 3.1 3.2 3.3 4.1 4.2 4.3 5 6 7.1 7.2 10 11 | After-reactor is uncapped; Do not uncap from RRA cooling shutdown pattern to the hot shutdown pattern from RRA cooling shutdown pattern to hot shutdown pattern-reactor-from RRA cooling shutdown pattern to the hot shutdown pattern-the cooling shutdown pattern from the hot shutdown pattern to RRA; The cooling of reactor pit full water-from the hot shutdown pattern to RRA shutdown pattern-heap power is in the unusual rising of the normal rising 15% and 100% (5%/minute)-heap power between 15% and 100% (5%/minute)-fuel recycle prolongation runtime; Heap power 15% and peak power between rising (5%/minute)-heap power prolong the runtime in the unusual reduction of the normal reduction between 100% and 15% (5%/minute)-heap power between 100% and 15% (5%/minute)-fuel recycle, heap power 15% and peak power between reduction. (5%/minute)-load is unexpected to raise (+10%Pn)-load is unexpected to be reduced (10%Pn)-load and be down to fast house load operation-fuel extended period; Load is down to during house load operation-hot shutdown pattern fast, and a certain cooling loop of water level-reactor of keeping steam generator is unavailable. | 80 120 200 9800 2000 200 9920 2000 80 2000 2000 160 40 2000 80 |
12 13 14 16 17 17.2 | The a certain unavailable cooling loop of-reactor again put into operation-pile power raising between 0% and 15%-heap power reduces-reloads (reactor pit full water)-start the steam turbine-loop final vacuum B. intermediate frequency accident of reloading with main steam system between 15% and 0% | 70 2200 2200 80 10 320 |
18 19 20 | -steam turbine tripping operation, steam turbine pipe system partly open-and loss of off-site power-reactor cooling flow partly loses | 80 40 80 |
Transient code | Transition is described | The design number of times |
21.1 21.2 22 23 24.1 25 26 27 15.1 15.2 9.2 31.1 31.2 31.3 32.1 32.2 33 34 35 36 | Reactor is jumped heap and is jumped heap from normal operating condition; The normal heat conduction condition fuel extended period is arranged; Jump heap from the peak load state; There is normal heat conduction condition to jump heap from normal operating condition; Have and excessively give water cooling but do not have peace and annotate from normal operating condition and jump heap; Simultaneously excessively cause peace to annotate the unusual step-down of action-reactor cooling system-unavailable loop to water cooling unusually putting into operation-emergence core stacking cool system (RIS)-one loop of unusually putting into operation heating up in the single-phase situation and cooling in cooling and superpressure one loop under the RRA cooling shutdown pattern: the transient state of moderate range significantly the intensification under the transient state-loop evaporator cooling shutdown pattern and adapter place of cools stacks cooling system the transition cooling in heap but service loops 1 loop 2 loops 3 of loop by-pass line and sensor change appearance systems (RCV) and fill second lower discharging hole plate of pipeline adapters-charging stream quantitative change increase by 50% maximum stream flow increase minimizing 50%-letdown flow increase and open; Flow increases the minimizing of 100%-letdown flow and closes second lower discharging hole plate; Flow reduces 10%:moderate range is closed second lower discharging hole plate, and flow reduces 100%:significantly | 230 80 160 10 20 10 40 10 2000 200 100 20 20 20 12000 300 12000 12000 12000 800 |
Transient code | Transition is described | The design number of times |
37 38 | -change the stoppage in transit of appearance system to open with enabling down to let out to close again again, let out simultaneously under filling on the charging stream amount remains unchanged and close, open the C. safety injection system simultaneously | 220 200 |
41 41.2 41.3 42 42.2 42.3 43 44 45 52.1 52.2 53 54 | During the cooling of safety injection system (RIS) pressure accumulation case pipeline adapter-reactor; Pressure accumulation case pipeline-one loop minor break-loop large break waste heat guiding system (RRA) outlet line adapter-system of unusually enabling puts into operation-and adjustment puts into operation after the accident: temperature drop (DT=80 ℃) the nuclear island exhaust of-moderate range temperature rise (DT=60 ℃)-moderate range temperature drop (DT=60 ℃)-significantly temperature rise (DT=80 ℃)-significantly and draining system (RPE)-excess letdown pipeline is unexpected when triggering the cooling of auxiliary spray line-a loop that auxiliary spray is triggered until RRA cooling shutdown pattern-lose main pump but when the charging stream amount is arranged; Using auxiliary spray system-accident triggers; Namely losing cooling safety injection system (RIS) behind the main pump starts (relevant with transient state 26)-boric acid in cold section adapter-unusual and injects the case discharging unusual step-down in-one loop-from the normal operating condition shutdown, the cold-peace peace occurred and annotate (relevant with No. 23 transient states) | 4 1 200 15 2000 400 50 8 40 40 10 10 |
Transient code | Transition is described | The design number of times |
56.1 56.2 56.3 56.1 56.2 56.3 | -one loop minor break-secondary circuit minor break-Di four class accident safety injection systems (RIS) are in the adapter of hot arc-unusual-one loop minor break (relevant with No. 58 transient states)-one loop large break D. unusual service condition (the 3rd class) that starts | 5 5 1 4 5 1 |
57 58 59 60 61.1 61.2 | The cold moving but stream of single-phase superpressure-a loop ,-one loop minor break-secondary circuit minor break-reactor core completely loses-and main steam stream completely loses-the single pipe fracture of the steam generator minimum probability operating mode of E. (the 4th class) | 4 5 5 5 5 1 |
62 63 64 65 66 | -dehydration thing piece (LOCA)-main steam pipe large break-feed pipe large break-main pump rotor blocks-single control rod ejection accident F. hydraulic testing operating mode | 1 1 1 1 1 |
68 69 70 71 | One hydrostatic circuit is tested the whole hydraulic testing 1.33Pc=229bar.abs in single hydraulic testing 1.33Pc=229bar.abs one loop and is tested again, and 1.20Pc=207bar.abs boosts in one loop and step-down<=1Pc (172.5bar.abs) | 3 3 10 10 |
Transient code | Transition is described | The design number of times |
72.1 72.2 72.3 73.1 73.2 73.3 74.1 74.2 74.3 | 69A (1.33Pc boosts), B (step-down 1.33Pc)/each is 10 times, 70A (1.20Pc boosts), B (step-down 1.20Pc)/each is 15 times, 71A (1Pc boosts), B (step-down 1Pc), B1 (46-111b), B2 (111-46b)/each is 20 times, 71C1 (31-46b), C2 (46-31b)/each 50 secondary circuit hydraulic testing full scales (1.5Pc) steam generator, 1 steam generator, 2 steam generators, 3 part range (1.2Pc) steam generators, 1 steam generator, 2 steam generator 3 are in order to carry out the heat exchanger tube Leak Off Test (LOT), shell pressure rising steam generator 1 steam generator 2 steam generators 3 G. voltage stabilizer SEBIM valves | 3 3 3 10 10 10 80 80 80 |
101 102 103 104 105 106 107 | Carry out equipment (RCP017-020VP) upstream line-P of pressure release function
RCP>165b, cause only once only once several times the 3 and 4 class transitions of 3 and 4 class transitions-cause blowdown valve RCP020VP switch-of several times 2 class transitions of 2 class transitions-cause blowdown valve RCP020VP switch-cause blowdown valve RCP020VP switch of blowdown valve RCP020VP switch in RRA cooling shutdown pattern, upstream and downstream is leaked, tandem SEBIM valve and steam discharge function test-periodicity operability is tested and is identified that again (25bar)-017VP closes, operation blowdown valve RCP020VP-close (6 hours) isolation valve for a long time is in case big leakage appears in upstream and downstream
| 50 20 6 6 6 170 25 5 |
Transient code | Transition is described | The design number of times |
108 109 110 111 112 113 114 115 201 202 203 204 205 206 207 208 209 210 211 | Valve body-P
RCP>165b, cause only once several times 2 class transitions of 2 class transitions-cause blowdown valve (RCP020VP) switch-cause blowdown valve RCP020VP switch once 3 and 4 class transitions-cause blowdown valve RCP020VP switch 3 and 4 class transitions-RRA cooling shutdown pattern several times only of blowdown valve switch, upstream and downstream is leaked, tandem SEBIM valve and steam discharge function test-periodicity operability test and again evaluation-017VP close, operation blowdown valve RCP20VP-close (6 hours) isolation valve for a long time big leakage main safety valve corrugated tube-P occurs to prevent upstream and downstream
RCP>50bars, the operation blowdown valve is carried out equipment (RCP018-021VP) upstream line-P of security function
RCP>165b, cause only once several times 2 class transitions of 2 class transitions-cause blowdown valve RCP021VP switch-cause blowdown valve RCP021VP switch once 3 and 4 class transitions-cause blowdown valve RCP021VP switch 3 and 4 class transitions-RRA cooling shutdown pattern several times only of blowdown valve RCP021VP switch, upstream and downstream is leaked, tandem SEBIM valve and steam discharge function test-periodicity operability is tested and is identified that again (25bar)-018VP closes, operation blowdown valve RCP021VP-close (6 hours) isolation valve for a long time is in case big leakage valve body-P appears in upstream and downstream
RCP>165b, cause only once several times 2 class transitions of 2 class transitions-cause blowdown valve RCP021VP switch-cause blowdown valve RCP021VP switch once 3 and 4 class transitions-cause blowdown valve RCP021VP switch 3 and 4 class transition RRA cooling shutdown pattern several times only of blowdown valve RCP021VP switch, upstream and downstream is leaked, tandem SEBIM valve and steam discharge function test
| 50 20 6 6 10 170 25 5 100 50 20 6 6 10 170 25 5 50 20 6 6 10 |
Transient code | Transition is described | The design number of times |
212 213 214 215 301 302 303 304 305 306 307 308 309 310 311 312 313 314 315 | -periodically the operability test and again evaluation-018VP close, operation blowdown valve RCP021VP closes (6 hours) isolation valve for a long time, big leakage main safety valve corrugated tube-P occurs to prevent upstream and downstream
RCP>50bars, the operation blowdown valve is carried out equipment (RCP019-022VP) upstream line-P of security function
RCP>165b, cause only once several times 2 class transitions of 2 class transitions-cause blowdown valve RCP022VP switch-cause blowdown valve RCP022VP switch once 3 and 4 class transitions-cause blowdown valve RCP022VP switch 3 and 4 class transitions-RRA cooling shutdown pattern several times only of blowdown valve RCP022VP switch, upstream and downstream is leaked, tandem SEBIM valve and steam discharge function test-periodicity operability is tested and is identified that again (25bar)-019VP closes, operation blowdown valve RCP022VP-close (6 hours) isolation valve for a long time is in case big leakage valve body-P appears in upstream and downstream
RCP>165b, cause only once several times 2 class transitions of 2 class transitions-cause blowdown valve RCP022VP switch-cause blowdown valve RCP022VP switch once 3 and 4 class transitions-cause blowdown valve RCP022VP switch 3 and 4 class transitions-RRA cooling shutdown pattern several times only of blowdown valve RCP022VP switch, upstream and downstream is leaked, tandem SEBIM valve and steam discharge function test-periodicity operability test and again evaluation-019VP close, operation blowdown valve RCP022VP-close (6 hours) isolation valve for a long time big leakage main safety valve corrugated tube P occurs to prevent upstream and downstream
RCP>50bars, the operation blowdown valve
| 170 25 5 100 50 20 6 6 10 170 25 5 50 20 6 6 10 170 25 5 100 |
4 report filings
Because transient statistic work runs through the whole phase in longevity of nuclear power station, the report filing of therefore carrying out science is very important.The method that adopts is to generate daily paper, monthly magazine and annual report, and per year with the report filing that is generated, carries out unified file administration.Complete report filing system also for phase in the longevity potentiality analysis of carrying out bearing device after for many years provides may.
5 safety analyses
Constantly to carry out safety analysis in the transient statistic process, whether be in a safe condition with judgment device.As long as each benchmark transition accumulative total frequency is lower than permissible value, just can determines that bearing device is safe certainly, otherwise will carry out case analysis as the case may be, and adjust the benchmark transition and allow frequency according to the stress analysis result.
Monitoring of the present invention can be finished in computer system automatically, rather than finish by the complicate statistics analysis.Computing machine is existing technology, does not repeat them here.
The present invention adopts above-mentioned method, timely watch-dog operation conditions aborning, especially under the situation that nuclear power plant equipment is not easy to monitor, adopt above-mentioned method, feasible monitoring intelligentization to equipment, and rapidly in time, be convenient to grasp the ruuning situation of all devices, carry out security control.
And enforcement of the present invention not only is confined to the device security monitoring of nuclear power station, also can be applicable to the high industries of mechanical automation degree such as chemical industry, electronics.