CN105741893A - Reactor coolant pump flow monitoring system of nuclear power plant - Google Patents
Reactor coolant pump flow monitoring system of nuclear power plant Download PDFInfo
- Publication number
- CN105741893A CN105741893A CN201610297482.0A CN201610297482A CN105741893A CN 105741893 A CN105741893 A CN 105741893A CN 201610297482 A CN201610297482 A CN 201610297482A CN 105741893 A CN105741893 A CN 105741893A
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- CN
- China
- Prior art keywords
- pump
- signal
- reactor coolant
- monitoring system
- nuclear power
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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Links
- 239000002826 coolant Substances 0.000 title claims abstract description 33
- 238000012544 monitoring process Methods 0.000 title claims abstract description 20
- 238000010835 comparative analysis Methods 0.000 claims description 17
- 239000000523 sample Substances 0.000 claims description 9
- 230000004044 response Effects 0.000 abstract description 3
- 238000000034 method Methods 0.000 description 6
- 230000008901 benefit Effects 0.000 description 5
- 230000004048 modification Effects 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000008859 change Effects 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 230000007257 malfunction Effects 0.000 description 2
- 230000007812 deficiency Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000008676 import Effects 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000010338 mechanical breakdown Methods 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 230000001052 transient effect Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/032—Reactor-coolant flow measuring or monitoring
-
- 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
Abstract
The invention provides a reactor coolant pump flow monitoring system of a nuclear power plant. The reactor coolant pump flow monitoring system comprises a rotary speed sensor, differential pressure sensors and a comparison and analysis module, wherein the rotary speed sensor is arranged on a pump and is used for configuring a rotary speed of the pump for measuring and transmitting a rotary speed signal; the differential pressure sensors is arranged at the inlet and the outlet of the pump and are used for configuring differential pressure between the inlet and the outlet of the pump for measuring and transmitting a differential pressure signal; the comparison and analysis module is used for receiving the rotary speed signal and the differential pressure signal, and calculating the flow of the pump through the rotary speed signal and the differential pressure signal. According to the reactor coolant pump flow monitoring system of the nuclear power plant, provided by the embodiment of the invention, supports are provided for safety operation of a set by calculating a flow signal through really measured signals, and transmitting an alarming signal; the reactor coolant pump flow monitoring system has the characteristics of rapid response, accuracy and high reliability.
Description
Technical field
The present invention relates to nuclear power plant reactor coolant system, be specifically related to the reactor coolant pump flow monitoring system of a kind of nuclear power station.
Background technology
In design of nuclear power plant, it is desirable to the coolant flow in reactor coolant loop is monitored in real time, to consider the situation of reactor coolant pump cisco unity malfunction the transient analysis.The reason causing reactor coolant pump cisco unity malfunction has multiple, such as loss of power, pump mechanical breakdown, pump card rotor and off-axis etc..After pump can not work, will result directly in reactor coolant flow reduction, directly affect the safe and stable operation of reactor.Therefore, the duty monitoring reactor coolant pump is particularly important.In traditional nuclear power plant reactor coolant system, the flow that can pass through monitoring reactor coolant judges the duty of pump.During some heap-type is designed, reactor coolant loop is likely to be not provided with effusion meter, therefore needs to design other means and judge the running status of pump.
Summary of the invention
The present invention is directed to the deficiencies in the prior art, it is proposed to the reactor coolant pump flow monitoring system of a kind of nuclear power station.
The reactor coolant pump flow monitoring system of nuclear power station includes:
Speed probe；Described speed probe is arranged on pump, is configured for measuring the rotating speed of pump, and sends tach signal；
Differential pressure pickup；Described differential pressure pickup is arranged on the inlet and outlet of pump；It is configured for measuring the pressure differential of the inlet and outlet of pump, and sends pressure difference signal；
Comparative analysis module；Described comparative analysis module is configured to accept described tach signal and pressure difference signal, and by the flow of described tach signal and pressure difference signal calculating pump, thus judging whether pump low discharge occurs.
Preferably, described comparative analysis module is configured output flow signal.
Preferably, the running status that when described comparative analysis module is configured in the flow of pump lower than alarming value, output alarm signal pays close attention to unit to remind operator, in order to make correct judgement.
Compared with prior art, the method have the advantages that
1, the reactor coolant pump flow monitoring system of nuclear power station provided by the invention, different from the method adopting flowmeter survey flow in traditional core power station, speed probe is adopted to measure the tach signal of pump, and measure the pressure difference signal that pump is imported and exported, and two signals are introduced comparative analysis module, flow signal is extrapolated by measured signal, and send alarm signal, thus reminding operator to pay close attention to the running status of unit, to make correct judgement, there is provided for unit safety operation and support, have the advantages that response is fast, accurate and reliability is high.
Accompanying drawing explanation
Fig. 1 is the schematic diagram of the reactor coolant pump flow monitoring system of the nuclear power station meeting the preferred embodiment of the present invention.
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 reactor coolant pump flow monitoring system of nuclear power station includes:
Speed probe 6；Described speed probe 6 is arranged on pump 1, is configured for measuring the rotating speed of pump, and sends tach signal 7；
Differential pressure pickup 4；Described differential pressure pickup 4 is arranged on import 2 and the outlet 3 of pump 1；It is configured for measuring the pressure differential of the inlet and outlet of pump, and sends pressure difference signal 5；
Comparative analysis module 8；Described comparative analysis module 8 is configured to accept described tach signal 7 and pressure difference signal 5, and is calculated the flow of pump by described tach signal 7 and pressure difference signal 5, thus judging whether pump low discharge occurs.
Preferably, described comparative analysis module 8 is configured output flow signal 9.
Preferably, the running status that when described comparative analysis module 8 is configured in the flow of pump lower than alarming value, output alarm signal 10 pays close attention to unit to remind operator, in order to make correct judgement, takes certain measure if desired.
Compared with prior art, the present embodiment has the advantages that
1, the reactor coolant pump flow monitoring system of the nuclear power station that the present embodiment provides, different from the method adopting flowmeter survey flow in traditional core power station, speed probe is adopted to measure the tach signal of pump, and measure the pressure difference signal that pump is imported and exported, and two signals are introduced comparative analysis module, flow signal is extrapolated by measured signal, and send alarm signal, thus reminding operator to pay close attention to the running status of unit, to make correct judgement, there is provided for unit safety operation and support, have the advantages that response is fast, accurate and reliability is high.
The operation principle of the reactor coolant pump flow monitoring system of the nuclear power station that the present embodiment provides is as follows: the operating condition of reactor coolant pump 1 is monitored by the reactor coolant pump flow monitoring system of nuclear power station, mainly include tachometric survey, inlet outlet pressure differential measurement, comparative analysis and warning.When reactor coolant pump 1 runs well, rotating speed and the inlet outlet pressure differential of reactor coolant pump 1 is monitored by speed probe 6 and differential pressure pickup 4, and tach signal 7 and pressure difference signal 5 are sent to comparative analysis module 8, by extrapolating flow after comparing with the Performance Characteristics of reactor coolant pump 1, and exported by flow signal 9, if flow is lower than warning setting valve, output alarm signal 10.
After reactor coolant pump 1 breaks down, pressure difference signal 4 will reduce rapidly, and after being calculated by comparative analysis module 8, output alarm signal 10, thus reminding operator to pay close attention to the running status of unit, in order 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 (3)
1. the reactor coolant pump flow monitoring system of a nuclear power station, it is characterised in that including:
Speed probe；Described speed probe is arranged on pump, is configured for measuring the rotating speed of pump, and sends tach signal；
Differential pressure pickup；Described differential pressure pickup is arranged on the inlet and outlet of pump；It is configured for measuring the pressure differential of the inlet and outlet of pump, and sends pressure difference signal；
Comparative analysis module；Described comparative analysis module is configured to accept described tach signal and pressure difference signal, and by the flow of described tach signal and pressure difference signal calculating pump, thus judging whether pump low discharge occurs.
2. the reactor coolant pump flow monitoring system of nuclear power station as claimed in claim 1, it is characterised in that described comparative analysis module is configured output flow signal.
3. the reactor coolant pump flow monitoring system of nuclear power station as claimed in claim 1, it is characterized in that, the running status that when described comparative analysis module is configured in the flow of pump lower than alarming value, output alarm signal pays close attention to unit to remind operator, in order to make correct judgement.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610297482.0A CN105741893A (en) | 2016-05-06 | 2016-05-06 | Reactor coolant pump flow monitoring system of nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610297482.0A CN105741893A (en) | 2016-05-06 | 2016-05-06 | Reactor coolant pump flow monitoring system of nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN105741893A true CN105741893A (en) | 2016-07-06 |
Family
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610297482.0A Pending CN105741893A (en) | 2016-05-06 | 2016-05-06 | Reactor coolant pump flow monitoring system of nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN105741893A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110047602A (en) * | 2019-05-16 | 2019-07-23 | 江苏利核仪控技术有限公司 | Dedicated speed probe of pressurized-water reactor nuclear power plant reactor main coolant pump and preparation method thereof |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS58137794A (en) * | 1982-02-10 | 1983-08-16 | 株式会社日立製作所 | Device for detecting abnormal flowrate of reactor cooling system |
| JPS6361190A (en) * | 1986-09-01 | 1988-03-17 | 株式会社日立製作所 | Cooling-water circulating flow measuring device in nuclear reactor |
| US5118461A (en) * | 1989-02-17 | 1992-06-02 | Kabushiki Kaisha Toshiba | Flow rate measuring apparatus |
| JP2000046994A (en) * | 1998-07-31 | 2000-02-18 | Toshiba Corp | Device for preventing pump for reactor coolant purification system from tripping |
| CN205722814U (en) * | 2016-05-06 | 2016-11-23 | 上海核工程研究设计院 | A kind of reactor coolant pump flow monitoring system of nuclear power station |
-
2016
- 2016-05-06 CN CN201610297482.0A patent/CN105741893A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS58137794A (en) * | 1982-02-10 | 1983-08-16 | 株式会社日立製作所 | Device for detecting abnormal flowrate of reactor cooling system |
| JPS6361190A (en) * | 1986-09-01 | 1988-03-17 | 株式会社日立製作所 | Cooling-water circulating flow measuring device in nuclear reactor |
| US5118461A (en) * | 1989-02-17 | 1992-06-02 | Kabushiki Kaisha Toshiba | Flow rate measuring apparatus |
| JP2000046994A (en) * | 1998-07-31 | 2000-02-18 | Toshiba Corp | Device for preventing pump for reactor coolant purification system from tripping |
| CN205722814U (en) * | 2016-05-06 | 2016-11-23 | 上海核工程研究设计院 | A kind of reactor coolant pump flow monitoring system of nuclear power station |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110047602A (en) * | 2019-05-16 | 2019-07-23 | 江苏利核仪控技术有限公司 | Dedicated speed probe of pressurized-water reactor nuclear power plant reactor main coolant pump and preparation method thereof |
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| SE01 | Entry into force of request for substantive examination | ||
| CB02 | Change of applicant information | ||
| CB02 | Change of applicant information |
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 |