CN106678481A - Processing method and processing device of nuclear power station generator set relevant system - Google Patents
Processing method and processing device of nuclear power station generator set relevant system Download PDFInfo
- Publication number
- CN106678481A CN106678481A CN201510760275.XA CN201510760275A CN106678481A CN 106678481 A CN106678481 A CN 106678481A CN 201510760275 A CN201510760275 A CN 201510760275A CN 106678481 A CN106678481 A CN 106678481A
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- pipeline
- nuclear power
- generator
- vibration
- power station
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16L—PIPES; JOINTS OR FITTINGS FOR PIPES; SUPPORTS FOR PIPES, CABLES OR PROTECTIVE TUBING; MEANS FOR THERMAL INSULATION IN GENERAL
- F16L55/00—Devices or appurtenances for use in, or in connection with, pipes or pipe systems
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16L—PIPES; JOINTS OR FITTINGS FOR PIPES; SUPPORTS FOR PIPES, CABLES OR PROTECTIVE TUBING; MEANS FOR THERMAL INSULATION IN GENERAL
- F16L3/00—Supports for pipes, cables or protective tubing, e.g. hangers, holders, clamps, cleats, clips, brackets
- F16L3/08—Supports for pipes, cables or protective tubing, e.g. hangers, holders, clamps, cleats, clips, brackets substantially surrounding the pipe, cable or protective tubing
- F16L3/12—Supports for pipes, cables or protective tubing, e.g. hangers, holders, clamps, cleats, clips, brackets substantially surrounding the pipe, cable or protective tubing comprising a member substantially surrounding the pipe, cable or protective tubing
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- Physics & Mathematics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Supports For Pipes And Cables (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention is applicable to the technical field of nuclear power, and discloses a processing method and a processing device of a nuclear power station generator set relevant system. The method comprises the following steps of A, troubleshooting nuclear power station generator relevant pipelines during power operation to form a fault pipeline list; B, analyzing the reason of higher pipeline vibration in the fault pipeline list from two sides, i.e. an exciting force source and pipeline inherent frequency; and C, if the reason of higher pipeline vibration is the pipeline inherent frequency, designing a vibration reduction support, carrying out trial assembly and assessment, and confirming if the vibration can be effectively reduced and the field installation requirement is met, if yes, carrying out integral installation during overhaul, and if not, improving the arrangement of engine pipelines. According to the processing method and the processing device of the nuclear power station generator set relevant system provided by the invention, through troubleshooting of the pipelines in site, confirmation of a pipeline treatment range, comprehensive analysis of reasons, design of a scheme, and trial assembly and assessment in site, the major defect of high vibration of the engine relevant pipelines is thoroughly overcome, and a certain experiences and a scientific method are accumulated for vibration treatment of important pipelines.
Description
Technical field
The invention belongs to technical field of nuclear power, more particularly to a kind of processing method and processing meanss of generator of nuclear power station group related system.
Background technology
Generating set is one of very important part of nuclear power station, and only under conditions of generating set normally runs, nuclear power station just can normally be run.And generating set is connected with various pipelines, therefore, for the normal operation of generating set, it is necessary to assure the normal work of its related pipeline.
In prior art, generator of nuclear power station group power is big, and generating set accessory system is more, causes and complexity many with the pipeline of generating set interface, and related pipeline is changed in inconvenience in maintenance, and can affect the normal operation of generating set.In this case, when generating set correlation pipeline is affected by generating set itself power frequency vibration, because the line construction design of generating set part itself is unreasonable, easily cause pipeline and being increased dramatically for vibration occur, occur pipe crack, joint leakage etc. when serious.Such as relating to hydrogen_cooling pipeline, interface tube or commissure may be caused in the case where Long-term Vibration is exceeded hydrogen gas leakage occur, in history it has been found that having crackle in the interface tube commissure of hydrogen_cooling pipeline, and therefore and occur hydrogen gas leakage accident, hydrogen gas leakage also can result in hydrogen it is quick-fried wait industry security risk.In addition, such as relating to stator cooling water flow sampling monitoring pipeline, it includes stator cooling water traffic ingress side sampling line and stator cooling water flowexit side sampling line, arm weld seam is easily caused in the case where Long-term Vibration is exceeded for these stator cooling water correlation pipelines or leakage occurs in joint, the accurate measurements of flow are affected, and affects the oxygen content of Generator Stator Cooling water.Additionally, such as relating to generator delivery pipeline, its Long-term Vibration is exceeded easily oil accident occurs in interface tube or commissure, not only affecting the normal operation of generating set, it is also possible to the industry security risks such as blast can be brought.And the industry security risk such as hydrogen can be brought quick-fried.Therefore, it is necessary to provide a kind of technological means to solve drawbacks described above.
The content of the invention
It is an object of the invention to overcome above-mentioned the deficiencies in the prior art, there is provided the processing method and processing meanss of a kind of generator of nuclear power station group related system, it has processed the high major defect of generator of nuclear power station group correlation pipeline vibration, eliminates the potential safety hazard of the long-standing stator cooling water pipeline leakage of generator unit and hydrogen gas leakage.
The technical scheme is that：A kind of processing method of generator of nuclear power station group related system is provided, is comprised the following steps：
A, during Power operation generator of nuclear power station correlation pipeline is carried out by investigation forms failure pipeline inventory；
B, analyze the reason for pipeline vibration is higher in the failure pipeline inventory from exciting force source and the aspect of pipeline intrinsic frequency two；
If the reason for C, higher pipeline vibration is the pipeline intrinsic frequency, then design damping frame and carry out trial assembly and assessment, it is confirmed whether effectively to lower and vibrates and meet in-site installation demand, be, integral installation is carried out in overhaul, otherwise the arrangement of generator pipeline is improved.
The present invention also provides a kind of processing meanss of generator of nuclear power station group related system, including damping frame described above, the damping frame includes for supporting several support components of failure pipeline, and is horizontally set in the support component and for fastening several railings of the support component.
The processing method of the generator of nuclear power station group related system of the present invention, it is on probation by the investigation of live pipeline, the determination of pipeline treatment range, the comprehensive analysis of reason, the design of scheme and scene and assesses, the high major defect of generator of nuclear power station correlation pipeline vibration is thoroughly processed, eliminate the potential safety hazard of long-standing stator cooling water pipeline leakage and hydrogen gas leakage on generator unit, for the method that the Vibration Treatment of important pipeline have accumulated certain experiences and science, there is certain reference value to processing for Similar Problems in the future.The damping frame of the present invention, its simple structure can effectively mitigate the vibration of generator correlation pipeline, and then significantly reduce potential safety hazard.
Description of the drawings
Technical scheme in order to be illustrated more clearly that the embodiment of the present invention, the accompanying drawing to be used needed for embodiment will be briefly described below, apparently, drawings in the following description are only some embodiments of the present invention, for those of ordinary skill in the art, on the premise of not paying creative work, can be with according to these other accompanying drawings of accompanying drawings acquisition.
Fig. 1 is the process flow figure of generator of nuclear power station group related system provided in an embodiment of the present invention；
Fig. 2 is the structural representation of the damping frame that one embodiment of the invention is provided；
Fig. 3 is the structural representation of the damping frame that another embodiment of the present invention is provided.
Specific embodiment
In order that the objects, technical solutions and advantages of the present invention become more apparent, below in conjunction with drawings and Examples, the present invention will be described in further detail.It should be appreciated that specific embodiment described herein is not intended to limit the present invention only to explain the present invention.
It should be noted that when element is referred to as " being fixed on " or " being arranged at " another element, it directly on another element or can may be simultaneously present centering elements.When an element is known as " being connected to " another element, it can be directly to another element or may be simultaneously present centering elements.
Only it is relative concept or be reference with the normal operating condition of product each other also, it should be noted that the orientation term such as left and right, upper and lower in the embodiment of the present invention, and should not be regarded as restrictive.
As shown in figure 1, the processing method of generator of nuclear power station group related system provided in an embodiment of the present invention, it is mainly used in the Vibration Treatment of related pipeline of generator of nuclear power station group.Specifically, the comprehensive processing method is comprised the following steps：
S1, during Power operation generator of nuclear power station correlation pipeline is carried out by investigation forms failure pipeline inventory；
S2, from exciting force source and pipeline intrinsic frequency two aspect analysis failure pipeline inventory in pipeline vibration it is higher the reason for；
If the reason for S3, higher pipeline vibration is the pipeline intrinsic frequency, then design damping frame and carry out trial assembly and assessment, it is confirmed whether effectively to lower and vibrates and meet in-site installation demand, be, integral installation is carried out in overhaul, otherwise the arrangement of generator pipeline is improved.
The processing method of the generator of nuclear power station group related system of the present invention is for generator of nuclear power station part correlation pipeline due to being affected by power frequency vibration, and because pipeline arrangement and design feature cause pipeline to produce resonance, important failure pipeline is determined by the pipeline investigation to generator unit, and Jing after comprehensive analysis, the scheme of the damping frame processed using autonomous Design, solves the long-term exceeded defect of generator related system arm pipeline vibration.
Specifically, in step sl, during Power operation, i.e., during generator unit works, for the failure of arm pipeline vibration, after investigation determines that generator of nuclear power station part correlation pipeline vibration is higher, failure pipeline inventory is formed.Then further classification process can be carried out according to the significance level and hazard of vibration degree of pipeline in failure pipeline inventory.For example, failure pipeline inventory as shown in the table is investigated and generated for the inlet/outlet pipeline of nuclear power station generator unit and classification is processed.
Further, the classification for processing sequence being advised in above table is significance level and hazard of vibration degree according to pipeline in failure pipeline inventory determining.Specifically, it can be divided into three-level, be advised corresponding digital 1,2 and 3 in processing sequence in one-level, two grades and three-level, i.e. table.Wherein, one-level is that pipeline significance level is high and vibration is higher；Two grades is that pipeline significance level is higher, vibration exceedes the universal standard and not less than effective speed value allowable；Three-level is that pipeline significance level is low and vibration exceedes effective speed value allowable.As system is hydrogen for the medium of D2GRV in upper table, Long-term Vibration is exceeded may to cause interface tube or commissure hydrogen gas leakage occur, its significance level it is high and vibrate it is higher, therefore for one-level.
In addition, the D2GSTOO1KD in table is the sampling detection of stator cooling water flow, vibration is exceeded for a long time to cause arm weld seam or joint leakage occur, can affect the accurate measurements of flow, and affects the oxygen content of Generator Stator Cooling water.
Further, during investigating to generator pipeline, in addition to recording maximum vibration value, also including status monitoring, it specifically includes herein below：The apparent condition of arm pipeline is carried out making regular check on tracking, confirmation has No leakage, and failure pipeline inventory is added if having；The vibrational state of arm pipeline is periodically tracked, is determined whether vibrating numerical has degradating trend, failure pipeline inventory is added if having；The root run surface state of arm pipeline is checked, confirmation has flawless to produce, failure pipeline inventory is added if having.
Further, in step s 2, pipeline failure Crack cause is analyzed, wherein, affect the factor of pipeline vibration more, mainly from from the aspect of exciting force source and pipeline intrinsic frequency two, seeking evidence one by one, the reason for analysis lookup causes pipeline vibration higher.Wherein, the resonance for producing for exciting force, is primarily directed to engine block vibration, generator shaft rotation, basic platform vibration and pipeline fluid vibration and is detected, and comparative analysis testing result.For the resonance that intrinsic frequency is produced, being primarily directed to pipeline arrangement affects to be analyzed with pipeline hypopexy.Specifically, affect for pipeline arrangement, screen out arm pipeline and arrange that unit similar with other has more apparent difference, and screen out arm cantilever part and turn round partly longer, in addition, pipeline vibration frequency is power frequency, it is thus determined that pipeline arrangement affects the higher possibility of pipeline vibration high.Additionally, for pipeline fixation aspect, generating motor spindle delivery pipeline is measured in the case of pipeline hypopexy, its pipeline that confluxes is longer, and without fixed support, it is thus determined that pipeline hypopexy affects the higher possibility of pipeline vibration high.
Therefore, determine that failure pipeline arranges and support there is obvious difference with other units in pipeline on the basis of comparative analysis.According to measurement engine block vibration, pipeline fluid analysis, historical vibration data and pipeline support arrangement Structure Comparison, be analyzed to identify cause be the reason for pipeline vibration is higher：Pipeline cantilever part is longer, and fixed underbraced causes the close power frequency of the intrinsic frequency of pipeline, so as to cause pipeline to produce resonance.
Further, the vibration for eliminating pipeline is mainly started with terms of two：One is to eliminate the exciting force for causing pipeline vibration, and two is that, by Design of antivibration Structurn, the supporting construction or arrangement to pipeline is transformed, and changes the intrinsic frequency of pipe-line system structure, it is to avoid produce resonance.Wherein, the surge of resonance derives from power frequency vibration, it is impossible to eliminate, therefore preferential from optimization is improved to piping support structure, as being unsatisfactory for damping requirements if consider the arrangement of change pipeline.
Further, trial assembly and assessment are carried out in above-mentioned steps S3, is confirmed whether effectively to lower and vibrates and meet in-site installation demand, be that integral installation is carried out in overhaul, otherwise the arrangement of generator pipeline is improved specially：Can damping frame described in trial assembly, confirmation effectively lower vibration, assess the effect of damping frame described in trial assembly, and decide whether to need in-site installation；Can assessment meet field requirement with the scheme of the damping frame, using the program as long-term project if meeting；Otherwise the arrangement of arm pipeline is improved.
Specifically, in one embodiment of the invention, as D2GSTOO1KD imports and exports the vibration reducing measure of sampling line, its by the way that damping frame is taken root by GST main pipes after fixed import and export sampling arm.It should be noted that the interface tube of probe tube is pipeline weakness, should avoid that pipe joint is caused to suppress strength.Its specific implementation process is：Main pipe pipe clamp is first installed, the installation of arm pipe clamp under free state on the basis of fastening, implement again when quitting work and treat overhaul if as occurred leakage change in fastener cycle, the situation of change that can measure vibration is installed in daily examination, as vibration is reduced in standard, can be using the measure as long-term measure.
In another embodiment of the present invention, damping frame is installed additional for generating motor spindle oil extraction arm.Specifically, the high oil extraction arm of fixed vibration after damping frame is taken root by platform railing, wherein, being taken root for platform railing fixed using carbon steel structure, and arm is fixed with carbon steel by pipe collar, and pipe collar inside adopts wear-resistant gasket.One damping frame is respectively installed in hydrogen-cooled device delivery pipeline south-north direction and east-west arm, two hydrogen-cooled devices need to install four damping frames altogether.It should be noted that oil extraction branch diameter is less, pipeline is easily deformed；There is the risk of hydrogen gas leakage in Hydrogen Line；Arm pipeline is adjacent with generator casing, and damping frame can affect the insulation against ground of generator.Its specific implementation process is：Strictly by being fastened and fixed for damping frame and arm pipeline is implemented under pipeline free state, pipeline is not applied to pull power；Measuring environment hydrogen content is distinguished before, during and after implementation process；Increase felt pad between pipe collar and arm；Trial assembly damping frame in day-to-day operation, measures the vibrating numerical of pipeline after installation, such as vibrate near controlling value, then implement the measure as long-term vibration reducing measure and in big amendment type.
Present invention also offers a kind of processing meanss of generator of nuclear power station group related system, it is used in the comprehensive regulation of generator correlation pipeline vibration, including damping frame described above.Specifically, as shown in Fig. 2 in one embodiment of the invention, damping frame is included for supporting several support components 2 of failure pipeline 1, and is horizontally set in support component 2 and for several railings 3 of fastening support component 2.Two support components 2 and two railings 3 are shown in Fig. 2.
Further, support component 2 includes horizontally disposed horizon bar 21 and the vertical bar 22 for being vertically arranged and being connected with horizon bar 21.
Further, damping frame also includes several pipe clamps 4 for connecting fault pipeline 1 and support component 2, and for connecting the runners 5 of horizon bar 21 and vertical bar 22.6 pipe clamps 4 and two runners 5 are shown in Fig. 2.In addition, wherein the horizon bar 21 of a support component 2 is vertically connected with intermediate bar 6 away from one end of vertical bar 22, the intermediate bar 6 is connected by pipe clamp 4 away from one end of horizon bar 21 with failure pipeline 1, and the intermediate bar 6 is connected by two right angle contiguous blocks 7 with horizon bar 21.
As shown in figure 3, in another embodiment of the present invention, damping frame has made corresponding change according to the structure of failure pipeline 1.Specifically, intermediate bar 6 is arranged on the side pipeline for being connected with generator, and other structures are identical with the structure in Fig. 2.
After the processing method and processing meanss of the generator of nuclear power station group related system of the present invention is by the conceptual design of damping frame, voluntarily processing, daily examination are installed, the program is finally formally implemented with field conduct, verify that the effectiveness in vibration suppression of support is obvious after unit Power operation, maximum vibration damping amplitude reaches to be vibrated after 80%, and improvement and is obviously improved.
In addition, the processing method and processing meanss of the generator of nuclear power station group related system of the present invention is on probation by the investigation of live pipeline, the determination of pipeline treatment range, the comprehensive analysis of reason, the design of scheme and scene and assesses, the high major defect of generator of nuclear power station correlation pipeline vibration is thoroughly processed, eliminate the potential safety hazard of long-standing stator cooling water pipeline leakage and hydrogen gas leakage on generator unit, for the method that the Vibration Treatment of important pipeline have accumulated certain experiences and science, there is certain reference value to processing for Similar Problems in the future.
Presently preferred embodiments of the present invention is the foregoing is only, not to limit the present invention, all any modification, equivalent or improvement made within the spirit and principles in the present invention etc., be should be included within the scope of the present invention.
Claims (11)
1. a kind of processing method of generator of nuclear power station group related system, it is characterised in that comprise the following steps：
A, during Power operation generator of nuclear power station correlation pipeline is carried out by investigation forms failure pipeline inventory；
B, analyze pipeline vibration in the failure pipeline inventory from exciting force source and the aspect of pipeline intrinsic frequency two
Higher the reason for；
If the reason for C, higher pipeline vibration is the pipeline intrinsic frequency, designs damping frame and tried
Dress and assessment, are confirmed whether effectively to lower and vibrate and meet in-site installation demand, are carried out in overhaul
Integral installation, is otherwise improved to the arrangement of generator pipeline.
2. the processing method of generator of nuclear power station group related system as claimed in claim 1, it is characterised in that
Methods described also includes the step of being classified to the failure pipeline inventory between step A and step B.
3. the processing method of generator of nuclear power station group related system as claimed in claim 2, it is characterised in that
The classification is carried out according to the significance level and hazard of vibration degree of pipeline in the failure pipeline inventory.
4. the processing method of generator of nuclear power station group related system as claimed in claim 3, it is characterised in that
The classification includes one-level, two grades and three-level, wherein, the one-level is that pipeline significance level is high and vibration is inclined
It is high；Described two grades is that pipeline significance level is higher, vibration exceedes the universal standard and not less than effective speed allowable
Value；The three-level is that pipeline significance level is low and vibration exceedes effective speed value allowable.
5. the processing method of generator of nuclear power station group related system as claimed in claim 1, it is characterised in that
Step A is specially：The apparent condition of arm pipeline is carried out making regular check on tracking, confirmation has No leakage,
The failure pipeline inventory is added if having；The vibrational state of arm pipeline is periodically tracked, it is determined that shaking
Whether dynamic numerical value has degradating trend, and the failure pipeline inventory is added if having；The root of arm pipeline is welded
Seam surface state is checked that confirmation has flawless to produce, and the failure pipeline inventory is added if having.
6. the processing method of generator of nuclear power station group related system as claimed in claim 1, it is characterised in that
Trial assembly and assessment are carried out in step C, is confirmed whether effectively to lower and is vibrated and meet in-site installation need
Ask, be, integral installation is carried out in overhaul, otherwise the arrangement of generator pipeline is improved specially：
Can damping frame described in trial assembly, confirmation effectively lower vibration, assess the effect of damping frame described in trial assembly
Really, and decide whether to need in-site installation；
Assessment can meet field requirement with the scheme of the damping frame, if meet if using the program as
Long-term project；Otherwise the arrangement of arm pipeline is improved.
7. a kind of processing meanss of generator of nuclear power station group related system, including such as any one of claim 1-6
Described damping frame, it is characterised in that the damping frame include for support failure pipeline several
Support component, and be horizontally set in the support component and for fastening several hurdles of the support component
Bar.
8. processing meanss of generator of nuclear power station group related system as claimed in claim 7, it is characterised in that
The support component includes horizontally disposed horizon bar and is vertically arranged and vertical with what the horizon bar was connected
Bar.
9. processing meanss of generator of nuclear power station group related system as claimed in claim 8, it is characterised in that
The damping frame also includes several pipe clamps for connecting the failure pipeline and the support component, with
And for connecting the runners of the horizon bar and vertical bar.
10. processing meanss of generator of nuclear power station group related system as claimed in claim 8, its feature exists
In the damping frame also includes vertically being connected to centre of the horizon bar away from one end of the vertical bar
Bar.
The processing meanss of 11. generator of nuclear power station group related systems as claimed in claim 10, its feature exists
In the damping frame also includes the right angle contiguous block for connecting the intermediate bar and the horizon bar.
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| CN201510760275.XA CN106678481B (en) | 2015-11-10 | 2015-11-10 | The processing method and processing unit of generator of nuclear power station group related system |
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| CN201510760275.XA CN106678481B (en) | 2015-11-10 | 2015-11-10 | The processing method and processing unit of generator of nuclear power station group related system |
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| CN106678481A true CN106678481A (en) | 2017-05-17 |
| CN106678481B CN106678481B (en) | 2019-09-13 |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113063036A (en) * | 2020-07-09 | 2021-07-02 | 安徽万瑞冷电科技有限公司 | Multichannel inner tube bearing structure |
| CN114576565A (en) * | 2022-03-02 | 2022-06-03 | 西安热工研究院有限公司 | Pipeline leakage detection protection system based on pipeline vibration detection |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1439837A (en) * | 2003-03-14 | 2003-09-03 | 山东中实股份有限公司 | Control method and device for pipeline vibration |
| CN104747808A (en) * | 2015-03-27 | 2015-07-01 | 华电重工股份有限公司 | Method for improving vibration of recirculating pipeline system |
| CN204592579U (en) * | 2015-03-26 | 2015-08-26 | 天津泵业机械集团有限公司 | Combined type tunable medium delivery line support |
| CN204819454U (en) * | 2015-06-16 | 2015-12-02 | 常州拓普森数控机械有限公司 | Pipe fitting rack |
-
2015
- 2015-11-10 CN CN201510760275.XA patent/CN106678481B/en active Active
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1439837A (en) * | 2003-03-14 | 2003-09-03 | 山东中实股份有限公司 | Control method and device for pipeline vibration |
| CN204592579U (en) * | 2015-03-26 | 2015-08-26 | 天津泵业机械集团有限公司 | Combined type tunable medium delivery line support |
| CN104747808A (en) * | 2015-03-27 | 2015-07-01 | 华电重工股份有限公司 | Method for improving vibration of recirculating pipeline system |
| CN204819454U (en) * | 2015-06-16 | 2015-12-02 | 常州拓普森数控机械有限公司 | Pipe fitting rack |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113063036A (en) * | 2020-07-09 | 2021-07-02 | 安徽万瑞冷电科技有限公司 | Multichannel inner tube bearing structure |
| CN113063036B (en) * | 2020-07-09 | 2023-12-19 | 安徽万瑞冷电科技有限公司 | Multichannel inner tube bearing structure |
| CN114576565A (en) * | 2022-03-02 | 2022-06-03 | 西安热工研究院有限公司 | Pipeline leakage detection protection system based on pipeline vibration detection |
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| CN106678481B (en) | 2019-09-13 |
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