CN211788197U - Nuclear power station liquid level measuring device - Google Patents

Nuclear power station liquid level measuring device Download PDF

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Publication number
CN211788197U
CN211788197U CN201922221360.5U CN201922221360U CN211788197U CN 211788197 U CN211788197 U CN 211788197U CN 201922221360 U CN201922221360 U CN 201922221360U CN 211788197 U CN211788197 U CN 211788197U
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China
Prior art keywords
liquid level
nuclear power
negative pressure
measuring device
pipeline
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CN201922221360.5U
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Chinese (zh)
Inventor
陈光毅
周富涛
徐万年
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China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
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China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
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Application filed by China General Nuclear Power Corp, CGN Power Co Ltd, Daya Bay Nuclear Power Operations and Management Co Ltd, Lingdong Nuclear Power Co Ltd, Guangdong Nuclear Power Joint Venture Co Ltd, Lingao Nuclear Power Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN201922221360.5U priority Critical patent/CN211788197U/en
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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Measurement Of Levels Of Liquids Or Fluent Solid Materials (AREA)

Abstract

The utility model belongs to the technical field of nuclear power station nuclear auxiliary systems, and discloses a nuclear power station liquid level measuring device, which comprises a differential pressure type liquid level meter, a positive pressure pipeline, a negative pressure pipeline and a condensed water tank; the positive pressure measuring end of the differential pressure type liquid level meter is connected with the bottom end of the pressure container through a positive pressure pipeline, and the negative pressure measuring end of the differential pressure type liquid level meter is connected with the top end of the pressure container through a negative pressure pipeline; the top of condensation water pitcher is provided with the end of intaking, and the condensation water pitcher is connected with the negative pressure pipeline through the end of intaking, and the incoming end that condensation water pitcher and negative pressure pipeline are connected is in the minimum of negative pressure pipeline. The utility model provides a nuclear power station liquid level measurement device can improve the accuracy of differential pressure type level gauge reading, solves the problem that the differential pressure type level gauge makes mistakes easily effectively, reduces the maintenance frequency of differential pressure type level gauge.

Description

Nuclear power station liquid level measuring device
Technical Field
The utility model belongs to the technical field of nuclear power station nuclear auxiliary system, more specifically say, relate to a nuclear power station liquid level measurement device.
Background
The existing liquid level measurement methods are various, such as ultrasonic liquid level measurement, radar liquid level measurement, capacitance liquid level measurement, magnetic turning plate type liquid level measurement, differential pressure type liquid level measurement and the like. The differential pressure type liquid level meter used for differential pressure type liquid level measurement is simple in structure principle and convenient to maintain, and is widely applied to nuclear power stations. In nuclear power plants, differential pressure gauges are mainly used for measuring the level of a pressure vessel.
In the process of measuring the liquid level of the pressure container by using the differential pressure type liquid level meter, because the measuring part is directly connected with the high-temperature high-pressure container, a pipeline on the negative pressure side is easy to form condensed water, so that the measurement is easy to make mistakes, and faults are frequent. Therefore, it is necessary to frequently arrange the inspection personnel to perform inspection so as to remove the fault.
However, the differential pressure type liquid level meter is mostly arranged in a radiation area of a nuclear power plant and even a high radiation area. Frequent inspection can greatly increase the radiation dose of inspection personnel, and seriously threatens the health of the inspection personnel.
SUMMERY OF THE UTILITY MODEL
An object of the utility model is to provide a nuclear power station liquid level measurement device to solve the technical problem that the differential pressure formula level gauge that exists makes mistakes easily among the prior art.
In order to achieve the above object, the utility model adopts the following technical scheme: the nuclear power station liquid level measuring device comprises a differential pressure type liquid level meter, a positive pressure pipeline, a negative pressure pipeline and a condensed water tank;
the positive pressure measuring end of the differential pressure type liquid level meter is connected with the bottom end of the pressure container through the positive pressure pipeline, and the negative pressure measuring end of the differential pressure type liquid level meter is connected with the top end of the pressure container through the negative pressure pipeline;
the top of condensation water pitcher is provided with the end of intaking, the condensation water pitcher passes through the end of intaking with negative pressure line connection, just the condensation water pitcher with negative pressure line connection's incoming end is in negative pressure line's minimum.
Optionally, a water outlet is arranged at the bottom of the condensed water tank.
Optionally, the water outlet is provided with a plug or a water outlet valve.
Optionally, a first water stop valve is arranged on the positive pressure pipeline.
Optionally, a second water stop valve is arranged on the negative pressure pipeline.
Optionally, a third water stop valve is arranged between the water inlet end and the access end.
Optionally, the nuclear power plant liquid level measuring device further includes a pipeline fixer for fixing the positive pressure pipeline and the negative pressure pipeline.
Optionally, the volume of the condensed water tank is 3-10L.
Optionally, the volume of the condensed water tank is 3L.
Optionally, the condensed water tank is made of stainless steel.
The utility model provides a nuclear power station liquid level measurement device's beneficial effect lies in: compared with the prior art, the utility model discloses nuclear power station liquid level measurement device can hold the comdenstion water that forms at the negative pressure pipeline condensation through inserting the condensation water pitcher at the negative pressure pipeline, prevents that the negative pressure pipeline from blockking up, has guaranteed the accuracy of differential pressure type level gauge reading, solves the problem that differential pressure type level gauge makes mistakes easily effectively, reduces the maintenance frequency of differential pressure type level gauge.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings required for the embodiments or the prior art descriptions will be briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings without inventive labor.
Fig. 1 is a schematic structural diagram of a nuclear power station liquid level measuring device provided by the embodiment of the present invention.
Detailed Description
In order to make the technical problem, technical solution and advantageous effects to be solved by the present invention more clearly understood, the following description is given in conjunction with the accompanying drawings and embodiments to illustrate the present invention in further detail. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
It will be understood that when an element is referred to as being "secured to" or "disposed on" another element, it can be directly on the other element or be indirectly on the other element. When an element is referred to as being "connected to" another element, it can be directly connected to the other element or be indirectly connected to the other element.
It will be understood that the terms "length," "width," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," and the like are used in an orientation or positional relationship indicated in the drawings for convenience in describing the invention and to simplify the description, and are not intended to indicate or imply that the device or element so referred to must have a particular orientation, be constructed and operated in a particular orientation, and thus should not be construed as limiting the invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of that feature. In the description of the present invention, "a plurality" means two or more unless specifically limited otherwise.
As shown in fig. 1, the liquid level measuring device of the nuclear power station provided by the present invention is now explained. The nuclear power station liquid level measuring device comprises a differential pressure type liquid level meter 03, a positive pressure pipeline 04, a negative pressure pipeline 05 and a condensate water tank 02;
the positive pressure measuring end of the differential pressure type liquid level meter 03 is connected with the bottom end of the pressure container 01 through a positive pressure pipeline 04, and the negative pressure measuring end of the differential pressure type liquid level meter 03 is connected with the top end of the pressure container 01 through a negative pressure pipeline 05;
the top of condensation water pitcher 02 is provided with into water end 021, and condensation water pitcher 02 is connected with negative pressure pipeline 05 through intaking end 021, and the incoming end 022 that condensation water pitcher 02 is connected with negative pressure pipeline 05 is in the minimum of negative pressure pipeline 05.
In this embodiment, the differential pressure type liquid level meter 03 may be a commercially available differential pressure type liquid level meter 03. The differential pressure type liquid level gauge 03 is a device for measuring the height of a liquid level using the pressure generated by a liquid column. When the water level of the pressure container 01 changes, the differential pressure measured by the differential pressure type liquid level meter 03 changes. The water level and the differential pressure have a linear relationship, so that the differential pressure type liquid level meter 03 can measure the water level change of the pressure vessel 01.
The differential pressure type liquid level meter 03 is provided with a positive pressure measuring end and a negative pressure measuring end. Wherein the positive pressure measuring end is connected with the bottom end of the pressure container 01 through a positive pressure pipeline 04; the negative pressure measuring end is connected with the top end of the pressure container 01 through a negative pressure pipeline 05. Here, the bottom end of the pressure vessel 01 may refer to a side wall position near the bottom of the pressure vessel 01. The top end of the pressure vessel 01 may refer to a location of the sidewall near the top of the pressure vessel 01. Pressure vessel 01 may refer to a storage tank within a nuclear power plant, such as a main pump shaft seal drain tank in an RCP system (reactor coolant system). During overhaul, the main pump shaft seal drain tank needs to be filled with water, and a liquid level reading in the main pump shaft seal drain tank is measured through the differential pressure type liquid level meter 03. Because the temperature of the water in the main pump shaft seal drain tank is higher and the water is greatly overturned during filling, condensed water is easily accumulated in the negative pressure pipeline 05.
At the lowest point of the negative pressure line 05, a condensate tank 02 is connected. The water inlet end 021 of the condensate tank 02 is arranged at the top thereof. The condensed water generated by condensation in the negative pressure pipeline 05 flows into the condensed water tank 02 through the inlet end 022 of the condensed water tank 02 and the negative pressure pipeline 05 and then flows into the condensed water tank 02 through the inlet end 021. Therefore, the negative pressure pipeline 05 can be guaranteed to be smooth, and data errors caused by the fact that the pipeline is blocked by the condensed water and the differential pressure type liquid level meter 03 is avoided. At the position of incoming end 022 place, be provided with the tee bend for negative pressure pipeline 05 both can connect the negative pressure measurement end of differential pressure type level gauge 03, can connect condensation water pitcher 02 again.
The nuclear power station liquid level measuring device that this embodiment provided can hold the comdenstion water that forms at the condensation of negative pressure pipeline 05 through insert condensation water pitcher 02 at negative pressure pipeline 05, prevents that negative pressure pipeline 05 from blockking up, has guaranteed the accuracy of differential pressure type level gauge 03 reading, solves the problem that differential pressure type level gauge 03 made mistakes easily effectively, reduces differential pressure type level gauge 03's maintenance frequency.
Optionally, a water outlet 08 is arranged at the bottom of the condensed water tank 02. The drain port 08 is provided with a plug or a drain valve.
In this embodiment, a drain port 08 is provided at the bottom of the condensate tank 02. When the liquid level of the pressure container 01 is measured normally, the drain port 08 is closed, and the condensed water generated in the negative pressure line 05 flows into the condensed water tank 02 through the water inlet port 021. When the amount of water accumulated in the condensate tank 02 is large, it is necessary to drain the water in the condensate tank 02. At this time, the drain port 08 is in an open state. The drain port 08 is provided with a plug or a drain valve, so that the open/close state of the drain port 08 can be flexibly changed.
Optionally, the positive pressure line 04 is provided with a first water stop valve 06.
In this embodiment, the positive pressure line 04 is provided with a first water stop valve 06. When the liquid level of the pressure vessel 01 is measured normally, the first water stop valve 06 is in an open state. When the differential pressure type liquid level meter 03 needs to be maintained, the first water stop valve 06 can be closed.
Optionally, a second water stop valve 09 is arranged on the negative pressure pipeline 05.
In this embodiment, the negative pressure line 05 is provided with a second water stop valve 09. When the liquid level of the pressure vessel 01 is measured normally, the second water stop valve 09 is in an open state. When the differential pressure type liquid level meter 03 needs to be maintained, the second water stop valve 09 can be closed.
Optionally, a third water stop valve 07 is disposed between the water inlet port 021 and the inlet port 022.
In this embodiment, a third water stop valve 07 is disposed between the inlet port 021 and the inlet port 022. When the liquid level of the pressure vessel 01 is measured normally, the third water stop valve 07 is in an open state. When the condensed water tank 02 needs to be drained, the third water stop valve 07 may be closed.
Optionally, the nuclear power plant liquid level measuring apparatus further includes a line holder (not shown) for fixing the positive pressure line 04 and the negative pressure line 05.
In this embodiment, since the differential pressure type level meter 03 is installed on a wall surface of a nuclear reactor plant, the positive pressure line 04 and the negative pressure line 05 can be fixed by using a line fixer before being connected to the differential pressure type level meter 03. The pipeline fixer is fixed on the wall of a nuclear reactor plant, and can improve the stability of the positive pressure pipeline 04 and the negative pressure pipeline 05.
Optionally, the volume of the condensed water tank 02 is 3-10L. Preferably 3L.
In the embodiment, tests show that the condensed water tank 02 with the volume of 3-10L can meet the use requirements. That is, the volume of condensed water accumulated by the negative pressure line 05 during a maintenance cycle of the nuclear power facility is less than 3L. In particular, the condensate tank 02 has a volume of 3L
Alternatively, the condensate tank 02 is made of stainless steel.
In this embodiment, the condensate tank 02 may be made of stainless steel. The condensate tank 02 made of stainless steel has a long service life.
The above description is only exemplary of the present invention and should not be taken as limiting the scope of the present invention, as any modifications, equivalents, improvements and the like made within the spirit and principles of the present invention are intended to be included within the scope of the present invention.

Claims (10)

1. A nuclear power station liquid level measuring device is characterized by comprising a differential pressure type liquid level meter, a positive pressure pipeline, a negative pressure pipeline and a condensed water tank;
the positive pressure measuring end of the differential pressure type liquid level meter is connected with the bottom end of the pressure container through the positive pressure pipeline, and the negative pressure measuring end of the differential pressure type liquid level meter is connected with the top end of the pressure container through the negative pressure pipeline;
the top of condensation water pitcher is provided with the end of intaking, the condensation water pitcher passes through the end of intaking with negative pressure line connection, just the condensation water pitcher with negative pressure line connection's incoming end is in negative pressure line's minimum.
2. Nuclear power plant liquid level measuring device according to claim 1, characterized in that the bottom of the condensate tank is provided with a drain.
3. Nuclear power plant liquid level measuring device according to claim 2, characterized in that the drain opening is provided with a plug or a drain valve.
4. The nuclear power plant level measuring device of claim 1, wherein a first water stop valve is disposed on the positive pressure line.
5. The nuclear power plant level measuring device of claim 1, wherein a second water stop valve is disposed on the negative pressure line.
6. The nuclear power plant level measuring device of claim 1, wherein a third water stop valve is disposed between the water inlet end and the access end.
7. The nuclear power plant level measuring device of claim 1, further comprising a line holder for holding the positive pressure line and the negative pressure line.
8. Nuclear power plant liquid level measuring device according to claim 1, characterized in that the volume of the condensate tank is 3-10L.
9. The nuclear power plant liquid level measuring device of claim 8, wherein the condensate tank has a volume of 3L.
10. Nuclear power plant liquid level measuring device according to claim 1, characterized in that the condensate tank is made of stainless steel.
CN201922221360.5U 2019-12-11 2019-12-11 Nuclear power station liquid level measuring device Active CN211788197U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201922221360.5U CN211788197U (en) 2019-12-11 2019-12-11 Nuclear power station liquid level measuring device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201922221360.5U CN211788197U (en) 2019-12-11 2019-12-11 Nuclear power station liquid level measuring device

Publications (1)

Publication Number Publication Date
CN211788197U true CN211788197U (en) 2020-10-27

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ID=72982748

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201922221360.5U Active CN211788197U (en) 2019-12-11 2019-12-11 Nuclear power station liquid level measuring device

Country Status (1)

Country Link
CN (1) CN211788197U (en)

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