CN105788681A - Main steam pipeline leakage monitoring system of nuclear power station - Google Patents
Main steam pipeline leakage monitoring system of nuclear power station Download PDFInfo
- Publication number
- CN105788681A CN105788681A CN201610297058.6A CN201610297058A CN105788681A CN 105788681 A CN105788681 A CN 105788681A CN 201610297058 A CN201610297058 A CN 201610297058A CN 105788681 A CN105788681 A CN 105788681A
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- China
- Prior art keywords
- main steam
- monitoring system
- steam line
- nuclear power
- power station
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/002—Detection of leaks
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention provides a main steam pipeline leakage monitoring system of a nuclear power station. The main steam pipeline leakage monitoring system comprises an air suction device, a hygrometer and a processor, wherein the processor is used for receiving a humidity signal, calculating the leakage rate of a main steam pipeline according to the humidity signal, outputting data, and sending out a leakage alarming signal when the main steam pipeline leaks, so as to prompt an operator to pay attention to the operation state of an unit, and perform correct judgment. The main steam pipeline leakage monitoring system of the nuclear power station has the advantages that the gas humidity is measured by the hygrometer, and the processor is used for comparing the humidity and the reference value, calculating the leakage rate, and sending out the leakage alarming signal, so as to prompt the operator to pay attention to the operation state of the unit, and perform correct judgment; when necessary, certain measures can be taken, so as to support the safety operation of the unit.
Description
Technical field
The present invention relates to the main steam line leakage monitoring system of a kind of nuclear power station.
Background technology
In design of nuclear power plant, it is desirable to reactor coolant loop and important tubing are had leak detection capabilities.For reactor coolant pressure boundary, its leakage monitoring method mainly has containment sump level monitoring, reactor coolant loop loading amount balance and the monitoring of containment atmospheric radioactivity.Additionally, power plant can also pass through the householder methods such as containment atmospheric pressure, temperature and humidity, visual examination detects the leakage of safe shell-side fluid.Liquid for reactor pressure border leaks, and being used alone or in combination of above-mentioned detection method can reach reasonable effect.
For the main steam line in containment, due to the existence of heat-insulation layer, leak fluid is possible all or part of to be condensate in heat-insulation layer, and above-mentioned monitoring method, certainty of measurement and the response time mentioned all has some limitations.
Summary of the invention
The present invention is directed to the deficiencies in the prior art, it is proposed to the main steam line leakage monitoring system of a kind of nuclear power station.
The main steam line leakage monitoring system of nuclear power station includes:
Air extractor, described air extractor is configured to be extracted out the gas in main steam line and heat-insulation layer gap；
Drimeter；Described drimeter is configured the humidity measuring the gas extracted out through described air extractor and produces moisture signal；
Processor；Described processor is configured the described moisture signal of acceptance, and calculate the slip of main steam line according to described moisture signal and export data, and send leakage alarm signal when leakage occurs main steam line, thus reminding operator to pay close attention to the running status of unit, in order to make correct judgement.
Preferably, described air extractor is ejector；The driving source of the gas of described ejector is compression air.
Preferably, also including regulating valve, described adjustment valve is arranged on the upstream of described ejector, is used for controlling described compression air.
Preferably, measuring chamber is also included；Described drimeter is configured the humidity of the gas measured in described measuring chamber.
Preferably, exhaust line is also included；Described exhaust line connects with described measuring chamber, is configured for discharging the gas in described measuring chamber
Compared with prior art, the method have the advantages that
1, the main steam line leakage monitoring system of nuclear power station provided by the invention, adopt compression air as the driving source of the gas of ejector by the gas extraction in main steam line and heat-insulation layer gap, introduce a measuring chamber, drimeter is utilized to measure gas humidity, within a processor humidity is compared with reference value, calculate slip, and send leakage alarm signal, thus reminding operator to pay close attention to the running status of unit, to make correct judgement, taking certain measure if desired, supporting thus providing for unit safety operation.
Accompanying drawing explanation
Fig. 1 is the schematic diagram of the main steam line leakage monitoring system of the nuclear power station meeting the preferred embodiment of the present invention.
Wherein, 1 main steam line；2 heat-insulation layers；3 annular gaps；4 bleed pipeline；5 ejectors；6 drive gas line；7 regulate valve；8 compression air；9 ejector outlet lines；10 measuring chambers；11 drimeters；12 exhaust lines；13 moisture signals；14 processors；15 data outputs；16 alarm signals
Detailed description of the invention
Understandable for enabling the above-mentioned purpose of the present invention, feature and advantage to become apparent from, below in conjunction with the drawings and specific embodiments, the present invention is further detailed explanation.
As it is shown in figure 1, the main steam line leakage monitoring system of nuclear power station includes:
Air extractor, described air extractor is configured to be extracted out the gas in main steam line 1 and heat-insulation layer 2 gap；
Drimeter 11；Described drimeter 11 is configured the humidity measuring the gas extracted out through described air extractor and produces moisture signal；
Processor 14；Described processor 14 is configured the described moisture signal 13 of acceptance, and calculate the slip of main steam line 1 according to described moisture signal 13 and export data 15, and send leakage alarm signal 16 when leakage occurs main steam line, thus reminding operator to pay close attention to the running status of unit, in order to make correct judgement.
Preferably, described air extractor is ejector 5；The driving source of the gas of described ejector 5 is compression air 8.
Preferably, also including regulating valve 7, described adjustment valve 7 is arranged on the upstream of described ejector 5, is used for controlling described compression air 8.
Preferably, measuring chamber 10 is also included；Described drimeter 11 is configured the humidity of the gas measured in described measuring chamber.
Preferably, exhaust line 12 is also included；Described exhaust line 12 connects with described measuring chamber 10, is configured for discharging the gas in described measuring chamber
Compared with prior art, the present embodiment has the advantages that
1, the main steam line leakage monitoring system of the nuclear power station that the present embodiment provides, adopt compression air as the driving source of the gas of ejector by the gas extraction in main steam line and heat-insulation layer gap, introduce a measuring chamber, drimeter is utilized to measure gas humidity, within a processor humidity is compared with reference value, calculate slip, and send leakage alarm signal, thus reminding operator to pay close attention to the running status of unit, to make correct judgement, taking certain measure if desired, supporting thus providing for unit safety operation.
The operation principle of the main steam line leakage monitoring system of the nuclear power station of the present embodiment is as follows: the leakage of main steam line 1 is monitored by the main steam line leakage monitoring system of nuclear power station, mainly includes extract system, measures system and computation analysis module.Annular gap 3 is there is between main steam line 1 and heat-insulation layer 2.During the work of monitoring system, regulating the intermittent opening and closing of valve 7, when regulating valve 7 and opening, compression air 8 is through entering to drive gas line 7 to enter ejector 5, gas in annular gap 3 is extracted out through pipeline 4 of bleeding, and enters measuring chamber 10 through ejector outlet line 9.The moisture signal 13 of measurement is sent into processor 14 by drimeter 11, compares with normal environmental criteria humidity, it is judged that whether jet chimney has leakage.
When there is leakage in jet chimney 1, gas humidity in annular gap 3 increases, finally it is measured in measuring chamber 10, and in processor 14, after computational analysis, obtain slip, processor 14 will leak out rate by data output 15 and is delivered to main control room, and sends warning by alarm signal 16, thus reminding operator to pay close attention to the running status of unit, to make correct judgement, take certain measure if desired.
In this specification, each embodiment adopts the mode gone forward one by one to describe, and what each embodiment stressed is the difference with other embodiments, between each embodiment identical similar portion mutually referring to.For system disclosed in embodiment, owing to corresponding to the method disclosed in Example, so what describe is fairly simple, relevant part illustrates referring to method part.
Those skilled in the art specifically can should be used for using different methods to realize described function to each, but this realization is it is not considered that beyond the scope of this invention.
Obviously, invention can be carried out various change and modification without deviating from the spirit and scope of the present invention by those skilled in the art.So, if these amendments of the present invention and modification belong within the scope of the claims in the present invention and equivalent technologies thereof, then the present invention is also intended to include these change and modification.
Claims (5)
1. the main steam line leakage monitoring system of a nuclear power station, it is characterised in that including:
Air extractor, described air extractor is configured to be extracted out the gas in main steam line and heat-insulation layer gap；
Drimeter；Described drimeter is configured the humidity measuring the gas extracted out through described air extractor and produces moisture signal；
Processor；Described processor is configured the described moisture signal of acceptance, and calculate the slip of main steam line according to described moisture signal and export data, and send leakage alarm signal when leakage occurs main steam line, thus reminding operator to pay close attention to the running status of unit, in order to make correct judgement.
2. the main steam line leakage monitoring system of nuclear power station as claimed in claim 1, it is characterised in that described air extractor is ejector；The driving source of the gas of described ejector is compression air.
3. the main steam line leakage monitoring system of nuclear power station as claimed in claim 2, it is characterised in that also including regulating valve, described adjustment valve is arranged on the upstream of described ejector, is used for controlling described compression air.
4. the main steam line leakage monitoring system of nuclear power station as claimed in claim 1, it is characterised in that also include measuring chamber；Described drimeter is configured the humidity of the gas measured in described measuring chamber.
5. the main steam line leakage monitoring system of nuclear power station as claimed in claim 4, it is characterised in that also include exhaust line；Described exhaust line connects with described measuring chamber, is configured for discharging the gas in described measuring chamber.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610297058.6A CN105788681A (en) | 2016-05-06 | 2016-05-06 | Main steam pipeline leakage monitoring system of nuclear power station |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610297058.6A CN105788681A (en) | 2016-05-06 | 2016-05-06 | Main steam pipeline leakage monitoring system of nuclear power station |
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| CN105788681A true CN105788681A (en) | 2016-07-20 |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106546389A (en) * | 2016-10-27 | 2017-03-29 | 北京科技大学 | The method for detecting subcritical, supercritical or ultra supercritical water vapour environment pipeline micro-crack |
| CN109029829A (en) * | 2018-07-26 | 2018-12-18 | 中广核工程有限公司 | A kind of calculation method and system of Steam Generators in NPP upper section internal pressure |
| CN113065735A (en) * | 2020-12-25 | 2021-07-02 | 泰州可以信息科技有限公司 | Intelligent steam leakage identification platform |
| CN114420324A (en) * | 2022-01-30 | 2022-04-29 | 上海核工程研究设计院有限公司 | Main steam pipeline leakage monitoring system combining spectrometry and condensate level method |
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| US20040200460A1 (en) * | 2003-03-10 | 2004-10-14 | Mitsubishi Denki Kabushiki Kaisha | Apparatus for detecting fuel-vapor gas leaks, and vent valve apparatus applied to this apparatus |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN106546389A (en) * | 2016-10-27 | 2017-03-29 | 北京科技大学 | The method for detecting subcritical, supercritical or ultra supercritical water vapour environment pipeline micro-crack |
| CN109029829A (en) * | 2018-07-26 | 2018-12-18 | 中广核工程有限公司 | A kind of calculation method and system of Steam Generators in NPP upper section internal pressure |
| CN109029829B (en) * | 2018-07-26 | 2020-07-17 | 中广核工程有限公司 | Method and system for calculating internal pressure of upper section of steam generator of nuclear power plant |
| CN113065735A (en) * | 2020-12-25 | 2021-07-02 | 泰州可以信息科技有限公司 | Intelligent steam leakage identification platform |
| CN114420324A (en) * | 2022-01-30 | 2022-04-29 | 上海核工程研究设计院有限公司 | Main steam pipeline leakage monitoring system combining spectrometry and condensate level method |
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |
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