CN107767975A - A kind of nuclear power unit closes the monitoring and fault diagnosis method of heavy parts capability and performance - Google Patents
A kind of nuclear power unit closes the monitoring and fault diagnosis method of heavy parts capability and performance Download PDFInfo
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- CN107767975A CN107767975A CN201710964695.9A CN201710964695A CN107767975A CN 107767975 A CN107767975 A CN 107767975A CN 201710964695 A CN201710964695 A CN 201710964695A CN 107767975 A CN107767975 A CN 107767975A
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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
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- 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 discloses a kind of structural vibration response signal analysis under being encouraged using determination to determine the method for nuclear power unit pass heavy parts capability and performance problem and failure,According to the analysis for the most common failure or possible potential capability and performance problem that heavy parts are closed to nuclear power unit different type,Primarily determine that excitation and response point position,It is required that the run mode formed can cover possible quality problems and failure across a frequency response function,The pumping signal and vibration response signal of heavy parts run mode are closed to the nuclear power unit gathered in real time,Make nuclear power unit and close multiple run modes of heavy parts across a frequency response function curve,Analyze different type and close each run mode of heavy parts across the crest frequency in a frequency response function,Fissipation factor and its changing rule,Extract the characteristic parameter of each run mode Frequency Response curve,Quantitative description corrodes,Crackle,Abrasion,Loosen,Leakage and jam faults characteristic,Experiment determines the influence of each failure and its degree to each rank characteristic parameter.
Description
Technical field
A kind of nuclear power unit of the present invention closes the monitoring and fault diagnosis method of heavy parts capability and performance, belongs to nuclear power system
System fault diagnosis technology field.
Background technology
Fault diagnosis technology is one of important component of nuclear power unit operation support technology, fault diagnosis technology
Study has great significance to the security and economy of nuclear power unit, can strengthen the security performance of nuclear power unit,
Reduce the probability of operating personnel's maloperation.
At present, method for diagnosing faults can substantially be divided into two classes：Empirical model method based on data-driven and based on mathematics
The physical model method of equation, both approaches respectively have advantage and disadvantage.The former only needs the historical data of diagnosed object and in line number
According to the latter can provide more significant information, gradually correct monitoring model to improve precision.
In warship atomic marine plant primary Ioops system, safety injection system, boron and water make-up system, control rod and fuel
Involucrum is the larger key factor of risk, steam flow control system, steam feed pump system in secondary coolant circuit system, electronic is given
Water pump system and high-pressure feed-water heater system are the larger key factor of risk, are significantly shaken with collision, stranded and multiple degrees of freedom
Put and research is carried out to nuclear power unit for external excitation can tackle potential risks.
Nuclear power unit is the power set using nuclear energy as thrust power, is mainly used in nuclear ship or latent at present
Ship.Because the safety and reliability of presurized water reactor is higher, at present worldwide, presurized water reactor is using the widest in power reactor
General heap-type.Many equipment operating environments are very severe in presurized water reactor nuclear power unit (PWRNPP), to be subjected to high temperature, high pressure,
The test of height radiation.Even an element breaks down and cannot get timely processing in PWRNPP, it is also possible to trigger chain
Reaction, or even cause a serious accident.PWRNPP maintenance supports are very cumbersome, and quite time-consuming effort consumption wealth.It is traditional afterwards
Maintenance or periodic maintenance can not meet requirement of the present user to PWRNPP securities, reliability and economy.Failure predication
With health control（PHM）Technology can realize PWRNPP condition maintenarnces, can facilitate the transformation of PWRNPP maintenance support methods.
With China's national defense and economic development, the development of energy security and the "Oceanic" strategy proposes higher demand.By land
Nuclear power is recovered and while size expansion, and atomic marine plant technology is also constantly being advanced, its go for ship power,
Island power supply, desalinization, marine resources development etc..The development of floating nuclear power plant, nuclear merchant ship equal power device is got over
Paid attention to get over by various countries, including International Atomic Energy Agency, Britain, Russia in interior developed country have all carried out marine floating
The development of platform.And the more nuclear energy in China exploitation unit, including in wide core, center, middle ship heavy industry etc. all promote sea with all strength
The research and development and construction of upper floating platform.
Nuclear Power System is the heart and sustainer of nuclear ship, and its is safe and reliable to operation, and to have influence on nuclear ship remote
The existence of even naval vessel and crewman are completed in ocean work, project, are the centers of gravity of nuclear ship safety, to be met ship power, be supplied
The load variations such as electricity, adapt to marine environment bring the influence that burn into waves, it is also contemplated that space requirement, runnability, reliably
The multinomial performance index such as property and maintainability.
Nuclear power unit closes heavy parts capability and performance and the aiming at for positioning and quantitative diagnosis of failure judges whether it locates
In normal condition, if there is abnormal, analysis failure Producing reason, position and the order of severity, and the trend of development is predicted；It is logical
The size and changing rule for the vibratory response that analysis measures in execution and drive device are crossed, makes across dot frequency response curve,
Signal characteristic, Classification and Identification failure are further extracted, probes into its degree and the position occurred.Nuclear power unit closes heavy parts to be made more
For nuclear ship system, structure is sufficiently complex, and wherein primary Ioops system is by reactor, cooling pump, steam generator, pressurization
Device and corresponding pipeline and valve etc. form；Cooling agent in loop takes the heat that disintegration energy changes out of out-pile and in steam
Heat is transmitted to secondary circuit working medium in generator；The capital equipment of the whole primary Ioops circulatory system installs the peace in sealing concentratedly
In full housing, naval reactor containment is steel closed housing, and it can bear certain pressure, can prevent that radiogen is outside
Diffusion, protect crewman and marine environment；The secondary circuit circulatory system by steam turbine, generator, condenser, condensate pump, feed pump,
The equipment such as feed-water heater and middle heating vapour-water separator forms；The working medium of secondary circuit is also water, is condensed from condenser
Water pass through deoxygenation, after heating by feed pump pumping over to steam generator, feed water in evaporator be heated, vaporization produce
Steam, by steam-water separator, steam quality is improved, steam turbine is sent to by main steam pipe, pushing turbine blade is rotated and done
Work(.The tightness and the smooth degree of relative motion that are connected between parts not only influence the intrinsic spy of each structure composition system
Property, the vibratory response characteristic in loop is also influenceed, turns into the risk factor that nuclear power unit closes some failures of heavy parts.Using multiple
Transmission characteristic when frequency response function relation between point, particularly medium exchange between several pumps, device, carry out nuclear power dress
Capability and performance and fault diagnosis when putting operation, make full use of and close the change of heavy parts structure inherent characteristic and carry out fault diagnosis
Classic applications, its applicability are mainly：
（1）For nuclear power unit uses operation, because nuclear power unit is sufficiently complex, modular construction is compact, and part seals
In Safety shell, trouble location is not easy to discover, and is typically only possible by the indirect faults of change of control system detection parameters
As a consequence it is difficult to accurately determine trouble location and degree, fault rootstock is found accurately, thus, the on-line testing in nuclear power unit operation
Carrying out quality diagnosis has important practical significance.
（2）From the point of view of nuclear power unit operation principle, running and parts assembly relation, nuclear power unit structure is answered
It is miscellaneous compact, it is highly integrated, including power drive, medium transmission and the several aspects of Mechatronic Systems detection control, early-stage weak fault
It is difficult to find, security incident can be caused after fault progression quickly.On-line checking capability and performance can be early in progress plant running
Pinpoint the problems, avoid development of defects from critical failure occur after developing.
（3）The multispan point frequency response function that nuclear power unit respectively closes heavy parts is the inherent characteristic of system, nuclear power unit one
Enter working condition through installation and operation, will just determine completely.The nuclear power unit structure of a set of good stable operation of installation quality
Inherent characteristic can completely obtain in Installation and trial run, in fact it could happen that capability and performance deterioration can be solid by obtaining it in advance
Individual difference is quantitatively described, and its feature and rule can be stored in separate diagnostic device, can also pass through communication interface
Into in the failure diagnosis unit of nuclear power control system.Diagnostic model and diagnostic method can at the end of nuclear power unit is developed
To complete in advance, and as a part for Nuclear Power System, walked one time by program in nuclear power unit operation, you can find matter
Performance issue is measured to exclude early.
The content of the invention
The invention overcomes the deficiencies of the prior art, and provides a kind of nuclear power unit closes heavy parts capability and performance
Monitoring and fault diagnosis method, data-driven method is combined with physical model method and establishes nuclear power unit distributed fault and examines
Disconnected system, makes fault diagnosis result reliable, it will be appreciated that property is more preferable, and diagnosis speed is fast, solves nuclear power unit and closes heavy parts matter
Measure technical problem present in performance and fault diagnosis.
In order to solve the above-mentioned technical problem, the technical solution adopted by the present invention is：A kind of nuclear power unit closes heavy parts matter
The monitoring and fault diagnosis method of performance is measured, is comprised the following steps：
A, typical nuclear power unit of analyzing and researching closes the main corrosion of heavy parts capability and performance, abrasion, loosening, leakage and bite event
The form of barrier and position, determine prevailing quality performance issue and model quantitative analysis its deteriorate rule；
B, the portable multi-channel data for including encouraging force snesor and vibration acceleration sensor is main monitoring means are set up
Acquisition system, the experiment that heavy parts capability and performance is closed in the nuclear power unit that nuclear power operation scene is carried out the work under state are ground
Study carefully；
C, the multiple run modes of heavy parts are closed across a frequency response function by testing typical nuclear power unit, analyzes run mode frequency response function
Each peak value-frequency, fissipation factor and its changing rule of curve；
D, nuclear power unit is mainly closed to heavy parts and is divided into three classes by running status：Static equipment part, quasi- static equipment part and dynamic
Part of appliance, different Signal Pre-Processing Methods is respectively adopted；
E, the characteristic parameter of each run mode Frequency Response curve, quantitative description corrosion, wear, loosening, leakage and bite event are extracted
Hinder characteristic, experiment determines the influence of each failure and its position to each rank characteristic parameter；
F, time domain, frequency domain and Time-Frequency Analysis are done to the excitation force signal, the vibration response signal that are gathered, entered with entropy-spectrum method
Row various features parameter extracts；
G, for faint early stage corrosion, wear, loosening, leakage and jam faults, by being run to typical nuclear power unit
Response signal under the conditions of state is filtered drop using multiple auto-correlation and bi-spectrum estimation method to dominant shape state initial failure data
Make an uproar processing, provide the generalized space morphology spectrum of time-frequency distributions and main morphological feature, do and multiple batches of quantify experiment and carry out Fault Identification.
The excitation force snesor is sensor excited by impact, and the vibration acceleration sensor is vibration acceleration response
Sensor, the sensor excited by impact and vibratory response sensor are separately positioned on several main pass weight portions of nuclear power unit
The both ends of part possible breakdown point, shaken for sensitive main close caused by heavy parts corrosion, wear, loosening, leakage and jam faults
Sound of something astir induction signal.
The static equipment part is not added with the not additional response of external excitation in operation；The quasi- static equipment part is in operation
Being not added with external excitation also has a small amount of dynamic response, can be eliminated by signal filter method, it is had substantially no effect on run mode across point
The quality of frequency response function；The dynamic part of appliance produces higher vibratory response in operation, need to take it is pre- adopt, inversion in frequency domain is repaiied
Positive measure eliminate to run mode across a frequency response function influence.
The present invention has an advantageous effect in that compared with prior art：The present invention makes full use of nuclear power unit to close heavy parts
Inherent characteristic can be obtained ahead of time after test run is installed or online dynamic access, and the control for being easily stored in Nuclear Power System is soft
In part.Capability and performance monitoring and adjustment not only can be carried out in nuclear power unit installation and debugging process, can also be made in plant running
For routine security inspection, find capability and performance problem and potential faults early, with prevent emerged in operation heavy wear, loosening,
Leakage and jam faults even safety failure.The present invention makes up existing profit under conditions of existing multi information Automatic Control
The deficiency of the correlation technique of fault diagnosis is carried out with outer sensor test response data, there is provided one kind utilizes structure inherent characteristic
Micro to change the technology for indicating structure incipient fault in advance, change only prevents event by setting up monitoring point tracing trouble to check at any time
Hinder the General Troubleshooting method occurred.Nuclear power unit is closed heavy parts inherent characteristic recognition result and checkout and diagnosis by this method
Model, it is added in capability and performance analysis and fault diagnosis system, and then the capability and performance that heavy parts are closed to nuclear power unit enters
Row comprehensive analysis is simultaneously subject to positioning and quantitative diagnosis.
Brief description of the drawings
The present invention is described further below in conjunction with the accompanying drawings.
Fig. 1 is the flow chart schematic diagram of the present invention.
Embodiment
As shown in figure 1, a kind of nuclear power unit of the present invention closes the monitoring and fault diagnosis method of heavy parts capability and performance, bag
Include following steps：
A, typical nuclear power unit of analyzing and researching closes the main corrosion of heavy parts capability and performance, abrasion, loosening, leakage and bite event
The form of barrier and position, determine prevailing quality performance issue and model quantitative analysis its deteriorate rule；
B, the portable multi-channel data for including encouraging force snesor and vibration acceleration sensor is main monitoring means are set up
Acquisition system, the experiment that heavy parts capability and performance is closed in the nuclear power unit that nuclear power operation scene is carried out the work under state are ground
Study carefully；
C, the multiple run modes of heavy parts are closed across a frequency response function by testing typical nuclear power unit, analyzes run mode frequency response function
Each peak value-frequency, fissipation factor and its changing rule of curve；
D, nuclear power unit is mainly closed to heavy parts and is divided into three classes by running status：Static equipment part, quasi- static equipment part and dynamic
Part of appliance, different Signal Pre-Processing Methods is respectively adopted；
E, the characteristic parameter of each run mode Frequency Response curve, quantitative description corrosion, wear, loosening, leakage and bite event are extracted
Hinder characteristic, experiment determines the influence of each failure and its position to each rank characteristic parameter；
F, time domain, frequency domain and Time-Frequency Analysis are done to the excitation force signal, the vibration response signal that are gathered, entered with entropy-spectrum method
Row various features parameter extracts；
G, for faint early stage corrosion, wear, loosening, leakage and jam faults, by being run to typical nuclear power unit
Response signal under the conditions of state is filtered drop using multiple auto-correlation and bi-spectrum estimation method to dominant shape state initial failure data
Make an uproar processing, provide the generalized space morphology spectrum of time-frequency distributions and main morphological feature, do and multiple batches of quantify experiment and carry out Fault Identification.
The excitation force snesor is sensor excited by impact, and the vibration acceleration sensor is vibration acceleration response
Sensor, the sensor excited by impact and vibratory response sensor are separately positioned on several main pass weight portions of nuclear power unit
The both ends of part possible breakdown point, shaken for sensitive main close caused by heavy parts corrosion, wear, loosening, leakage and jam faults
Sound of something astir induction signal.
The static equipment part is not added with the not additional response of external excitation in operation；The quasi- static equipment part is in operation
Being not added with external excitation also has a small amount of dynamic response, can be eliminated by signal filter method, it is had substantially no effect on run mode across point
The quality of frequency response function；The dynamic part of appliance produces higher vibratory response in operation, need to take it is pre- adopt, inversion in frequency domain is repaiied
Positive measure eliminate to run mode across a frequency response function influence.
It is qualitative to determine that nuclear power unit closes heavy parts for structural vibration response signal analysis under the present invention is encouraged using determination
Can be with the method for tracing trouble, building includes encouraging force snesor and vibration acceleration to be calculated as the portable more of main monitoring means
Channel data gathers and Signal Analysis System, according to the pass heavy parts Common Quality performance fault different classes of to nuclear power unit
Or the analysis of possible potential quality problems, primarily determine that excitation and response point position, it is desirable to formed across a frequency response letter
Number, which can cover, closes quality problems and failure that heavy parts are likely to occur.Then method is struck using examination, draws multiple diverse locations
Across a frequency response curve, optimization can cover the exciter response that nuclear power unit mainly closes the incipient fault of heavy parts therefrom
Right, and can covers more relative motion and connecting link.After preferred test and excitation point and response point, to collection in real time
Nuclear power unit close heavy parts pumping signal and vibration response signal, make close heavy parts it is multiple across a frequency response curve；
Analytical structure is respectively across peak value-frequency, fissipation factor and its changing rule in a frequency response curve；Extract each run mode Frequency Response
The characteristic parameter of curve, quantitative description corrosion, wear, loosening, leakage and jam faults characteristic, experiment determine each failure and its position
Put the influence to each rank characteristic parameter；Time domain, frequency domain and Time-Frequency Analysis are done, carrying out various features parameter with entropy-spectrum method carries
Take, for faint early stage burn into mild wear, loosening, leakage and jam faults, do multiple batches of quantization experiment and carry out failure knowledge
Not, and then realize that nuclear power unit closes heavy parts quality-monitoring and quantified with fault location.It the method can be widely used in nuclear power dress
Put and close heavy parts because capability and performance problem causes the inline diagnosis of failure.
The present invention is explained in detail with reference to specific embodiment：
1st, typical nuclear power unit of analyzing and researching first closes main corrosion, abrasion, loosening, leakage and the card of heavy parts capability and performance
The form of puckery failure and position, determine prevailing quality performance issue and model quantitative analysis its deteriorate rule.
2nd, the portable multi-channel for including encouraging force snesor and vibration acceleration sensor is main monitoring means is set up
Data collecting system, the experiment of heavy parts capability and performance is closed in the nuclear power unit that nuclear power operation scene is carried out the work under state
Research；Excitation force snesor and vibration acceleration meter all select ICP types, and effective analysis frequency range of signal is not less than 1kHz；
Sensor excited by impact and vibratory response sensor are arranged on several main pass heavy parts possible breakdown points of nuclear power unit
Both ends, for vibration response signal caused by sensitive main pass heavy parts corrosion, wear, loosening, leakage and jam faults.
3rd, the multiple run modes of heavy parts are closed across a frequency response function by testing typical nuclear power unit, analyzes run mode frequency response
Each peak value-frequency, fissipation factor and its changing rule of function curve.
4th, nuclear power unit is mainly closed to heavy parts and is divided into three classes by running status：Static equipment part, quasi- static equipment part
With dynamic part of appliance, different Signal Pre-Processing Methods is respectively adopted；Wherein the performance of static equipment part is outside being such as not added with operation
Excitation is then basic without additional response；Quasi- static equipment part performance is to be not added with external excitation in operation also to have a small amount of dynamic response but width
Value is little, can be eliminated by signal filter method, its result is had substantially no effect on run mode across follow-up minute of a frequency response function
Analysis diagnosis；Dynamic part of appliance performance is that higher background vibration response is generated in operation, need to take and pre- adopt analysis, inversion in frequency domain
Correction measure so eliminate background response to run mode across a frequency response function influence.
5th, the characteristic parameter of each run mode Frequency Response curve, including each rank intrinsic frequency fi, dampingratioζ i, peak value are extracted
Ai, spectrum kurtosis ξ i, quality factor q i, singular value δ i etc., quantitative description corrosion, wear, loosening, leakage and jam faults characteristic,
Experiment determines the influence of each failure and its position to each rank characteristic parameter.
6th, time domain, frequency domain and Time-Frequency Analysis are done to the excitation force signal, the vibration response signal that are gathered, with entropy-spectrum side
Method carries out various features parameter extraction；For faint early stage burn into fine crack, mild wear, loosening, leakage and bite event
Barrier, by using multiple auto-correlation and bi-spectrum estimation method pair to response signal of the typical nuclear power unit under the conditions of run mode
Dominant shape state initial failure data are filtered noise reduction process, provide the generalized space morphology spectrum of time-frequency distributions and main morphological feature,
Do multiple batches of quantization experiment and carry out Fault Identification.
The present invention is explained in detail above in conjunction with embodiment, but the present invention is not limited to above-described embodiment, at this
In the those of ordinary skill's possessed knowledge of field, various changes can also be made on the premise of present inventive concept is not departed from
Change.
Claims (3)
1. a kind of nuclear power unit closes the monitoring and fault diagnosis method of heavy parts capability and performance, it is characterised in that including following
Step：
A, typical nuclear power unit of analyzing and researching closes the main corrosion of heavy parts capability and performance, abrasion, loosening, leakage and bite event
The form of barrier and position, determine prevailing quality performance issue and model quantitative analysis its deteriorate rule；
B, the portable multi-channel data for including encouraging force snesor and vibration acceleration sensor is main monitoring means are set up
Acquisition system, the experiment that heavy parts capability and performance is closed in the nuclear power unit that nuclear power operation scene is carried out the work under state are ground
Study carefully；
C, the multiple run modes of heavy parts are closed across a frequency response function by testing typical nuclear power unit, analyzes run mode frequency response function
Each peak value-frequency, fissipation factor and its changing rule of curve；
D, nuclear power unit is mainly closed to heavy parts and is divided into three classes by running status：Static equipment part, quasi- static equipment part and dynamic
Part of appliance, different Signal Pre-Processing Methods is respectively adopted；
E, the characteristic parameter of each run mode Frequency Response curve, quantitative description corrosion, wear, loosening, leakage and bite event are extracted
Hinder characteristic, experiment determines the influence of each failure and its position to each rank characteristic parameter；
F, time domain, frequency domain and Time-Frequency Analysis are done to the excitation force signal, the vibration response signal that are gathered, entered with entropy-spectrum method
Row various features parameter extracts；
G, for faint early stage corrosion, wear, loosening, leakage and jam faults, by being run to typical nuclear power unit
Response signal under the conditions of state is filtered drop using multiple auto-correlation and bi-spectrum estimation method to dominant shape state initial failure data
Make an uproar processing, provide the generalized space morphology spectrum of time-frequency distributions and main morphological feature, do and multiple batches of quantify experiment and carry out Fault Identification.
2. a kind of nuclear power unit according to claim 1 closes the monitoring and fault diagnosis method of heavy parts capability and performance,
Characterized in that, the excitation force snesor is sensor excited by impact, the vibration acceleration sensor is vibration acceleration
Response sensor, the sensor excited by impact and vibratory response sensor are separately positioned on several main passes of nuclear power unit
The both ends of heavy parts possible breakdown point, produced for sensitive main heavy parts corrosion, wear, loosening, leakage and the jam faults of closing
Vibration response signal.
3. a kind of nuclear power unit according to claim 1 closes the monitoring and fault diagnosis method of heavy parts capability and performance,
Characterized in that, the static equipment part is not added with the not additional response of external excitation in operation；The quasi- static equipment part is being transported
External excitation is not added with row also a small amount of dynamic response, can be eliminated by signal filter method, it is had substantially no effect on run mode
Across the quality of a frequency response function；The dynamic part of appliance produces higher vibratory response in operation, need to take it is pre- adopt, frequency domain it is anti-
Drill correction measure eliminate to run mode across a frequency response function influence.
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| CN109444263A (en) * | 2018-11-27 | 2019-03-08 | 山东大学 | A kind of assembling quality detection system and method based on frequency response function |
| CN109506696A (en) * | 2018-12-17 | 2019-03-22 | 湖北工业大学 | A kind of frequency response function calibration method based on sensor mass identification |
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| CN109147978A (en) * | 2018-06-28 | 2019-01-04 | 广东核电合营有限公司 | A kind of circuit loose part monitoring device and its method for nuclear power unit |
| CN109147978B (en) * | 2018-06-28 | 2020-11-24 | 广东核电合营有限公司 | Loop loose part monitoring device and method for nuclear power unit |
| CN110766277A (en) * | 2018-10-24 | 2020-02-07 | 中国核电工程有限公司 | Health assessment and diagnosis system and mobile terminal for nuclear industry field |
| CN110766277B (en) * | 2018-10-24 | 2022-08-09 | 中国核电工程有限公司 | Health assessment and diagnosis system and mobile terminal for nuclear industry field |
| CN109444263A (en) * | 2018-11-27 | 2019-03-08 | 山东大学 | A kind of assembling quality detection system and method based on frequency response function |
| CN109506696A (en) * | 2018-12-17 | 2019-03-22 | 湖北工业大学 | A kind of frequency response function calibration method based on sensor mass identification |
| CN111881176A (en) * | 2020-07-07 | 2020-11-03 | 中国人民解放军海军工程大学 | Marine nuclear power anomaly detection method based on logical distance characterization safety operation domain |
| CN112381181A (en) * | 2020-12-11 | 2021-02-19 | 桂林电子科技大学 | Dynamic detection method for building energy consumption abnormity |
| CN112381181B (en) * | 2020-12-11 | 2022-10-04 | 桂林电子科技大学 | Dynamic detection method for building energy consumption abnormity |
| CN113343528A (en) * | 2021-06-11 | 2021-09-03 | 中北大学 | Shafting fatigue damage prediction method based on cross-point frequency response and dynamic response characteristic fusion |
| CN113343528B (en) * | 2021-06-11 | 2022-07-26 | 中北大学 | Shafting fatigue damage prediction method based on cross-point frequency response and dynamic response characteristic fusion |
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