CN218299390U - Safety valve leakage detection device and nuclear power station primary circuit - Google Patents

Safety valve leakage detection device and nuclear power station primary circuit Download PDF

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Publication number
CN218299390U
CN218299390U CN202221815368.XU CN202221815368U CN218299390U CN 218299390 U CN218299390 U CN 218299390U CN 202221815368 U CN202221815368 U CN 202221815368U CN 218299390 U CN218299390 U CN 218299390U
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China
Prior art keywords
pressure
safety valve
pipe
detection device
tube
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Active
Application number
CN202221815368.XU
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Chinese (zh)
Inventor
蒋勇
张冀兰
赵燕子
柯海鹏
张晓斌
杨强强
洪伟
吴肖
徐广学
杨加东
曹雷涛
刘华
高俊
刘晓红
刘汝卫
吴昊
杨鹏
鲍学斌
武怡明
杨明晓
覃捷
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Huaneng Group Technology Innovation Center Co Ltd
Huaneng Shandong Shidaobay Nuclear Power Co Ltd
Huaneng Nuclear Energy Technology Research Institute Co Ltd
Original Assignee
Huaneng Group Technology Innovation Center Co Ltd
Huaneng Shandong Shidaobay Nuclear Power Co Ltd
Huaneng Nuclear Energy Technology Research Institute Co Ltd
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Application filed by Huaneng Group Technology Innovation Center Co Ltd, Huaneng Shandong Shidaobay Nuclear Power Co Ltd, Huaneng Nuclear Energy Technology Research Institute Co Ltd filed Critical Huaneng Group Technology Innovation Center Co Ltd
Priority to CN202221815368.XU priority Critical patent/CN218299390U/en
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Priority to DE202023102662.1U priority patent/DE202023102662U1/en
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004—Pressure suppression
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
    • G01M3/00—Investigating fluid-tightness of structures
    • G01M3/02—Investigating fluid-tightness of structures by using fluid or vacuum
    • G01M3/04—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point
    • G01M3/20—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material
    • G01M3/202—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material using mass spectrometer detection systems
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
    • G01M3/00—Investigating fluid-tightness of structures
    • G01M3/02—Investigating fluid-tightness of structures by using fluid or vacuum
    • G01M3/26—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors
    • G01M3/28—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds
    • G01M3/2807—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds for pipes
    • G01M3/2815—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds for pipes using pressure measurements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/002—Detection of leaks

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Examining Or Testing Airtightness (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The utility model discloses a relief valve leakage detection device and nuclear power station return circuit, including relief valve, first pipe, pressure relief device and first pressure monitoring device, the relief valve is suitable for and links to each other with pressure vessel, the relief valve is located the one end of first pipe, pressure relief device locates the other end of first pipe, first pressure monitoring device with first pipe intercommunication, it is right to be suitable for gas pressure in the first pipe monitors. The utility model discloses relief valve leakage detection device and nuclear power station return circuit can realize monitoring the leakage condition of helium medium relief valve, have convenient monitoring use, characteristics that the security is good.

Description

Safety valve leakage detection device and nuclear power station primary circuit
Technical Field
The utility model relates to a return circuit technical field specifically, relates to a relief valve leakage detection device and applied this relief valve leakage detection device's high temperature gas cooled reactor nuclear power station return circuit.
Background
The high-temperature gas cooled reactor nuclear power station has the advantages that helium is used as a coolant in a primary loop, the primary loop mainly comprises a reactor pressure vessel, a steam generator, corresponding pipeline components and the like, a safety valve is generally arranged as an overpressure protection device for preventing overpressure of a primary loop system, and due to the fact that helium molecules are small, the helium medium of the primary loop of the high-temperature gas cooled reactor nuclear power station has the characteristic of high penetrability, the high-temperature gas cooled reactor nuclear power station has high requirements for the sealing performance of the primary loop, the leakage condition of the safety valve needs to be monitored specially, and a detection device for the leakage condition of the safety valve is lacked in the related technology.
SUMMERY OF THE UTILITY MODEL
Therefore, the embodiment of the utility model provides a can carry out the relief valve leakage detection device who monitors to the leakage condition of helium medium.
The embodiment of the utility model provides a still provide an applied above-mentioned relief valve leak testing device's a high temperature gas cooled reactor nuclear power station return circuit.
The utility model discloses relief valve leakage detection device, including relief valve, first pipe, pressure relief device and first pressure monitoring device, the relief valve is suitable for and links to each other with pressure vessel, the relief valve is located the one end of first pipe, pressure relief device locates the other end of first pipe, first pressure monitoring device with first pipe intercommunication, it is right to be suitable for gas pressure in the first pipe monitors.
The utility model discloses relief valve leakage detection device can realize monitoring the leakage condition of helium medium relief valve, has the characteristics that convenient monitoring was used, the security is good.
In some embodiments, the safety valve leakage detection device includes a second tube, the second tube is communicated with the first tube, the first pressure monitoring device is disposed on the second tube, the second tube is provided with a leakage detection port, and the leakage detection port is provided with a sealing plug.
In some embodiments, the safety valve leak detection apparatus comprises a helium mass spectrometer adapted to be connected to the leak detection port after removal of the sealing plug.
In some embodiments, the safety valve leakage detection device includes a third pipe adapted to communicate the pressure vessel and the safety valve, and a first isolation device provided to the third pipe so as to be adapted to open and close the third pipe.
In some embodiments, the safety valve leak detection device includes a second isolation device provided to the second pipe to be adapted to open and close the second pipe, the second isolation device being located between the first pressure monitoring device and the first pipe.
In some embodiments, the safety valve leak detection device comprises a fourth tube connected to the pressure relief device adapted to vent gas in the first tube.
In some embodiments, the first pressure monitoring device is a pressure gauge or a pressure transmitter.
In some embodiments, the pressure relief device is a rupture disk device.
The utility model discloses a nuclear power station return circuit includes above-mentioned arbitrary embodiment relief valve leak detection device.
Drawings
Fig. 1 is a schematic view of a connection structure according to an embodiment of the present invention.
Reference numerals:
a pressure vessel 1; a safety valve 2; a first tube 3; a pressure relief device 4; a first pressure monitoring device 5; a second tube 6; sealing the plug 7; a third tube 8; a first isolation device 9; a second isolation device 10; and a fourth tube 11.
Detailed Description
Reference will now be made in detail to embodiments of the present invention, examples of which are illustrated in the accompanying drawings. The embodiments described below by referring to the drawings are exemplary intended for explaining the present invention, and should not be construed as limiting the present invention.
As shown in fig. 1, the utility model provides a relief valve leakage detection device, including relief valve 2, first pipe 3, pressure relief device 4 and first pressure monitoring device 5, relief valve 2 is suitable for and links to each other with pressure vessel 1, relief valve 2 locates the one end of first pipe 3, pressure relief device 4 locates the other end of first pipe 3, first pressure monitoring device 5 with first pipe 3 intercommunication is in order to be suitable for right gas pressure in first pipe 3 monitors.
Specifically, the safety valve 2 may protect the pressure vessel 1 from overpressure, when the air pressure in the pressure vessel 1 exceeds a predetermined value, the excess portion may be automatically discharged through the safety valve 2, the safety valve 2 and the pressure relief device 4 may be respectively installed at two ends of the first pipe 3, a sealed chamber may be formed in the first pipe 3 between the safety valve 2 and the pressure relief device 4, the first pressure monitoring device 5 may be communicated with the sealed chamber and configured to detect the air pressure in the sealed chamber, and the pressure vessel 1 is further provided with a second pressure monitoring device (not shown in the drawings) configured to detect the air pressure in the pressure vessel 1.
Wherein, pressure relief device 4 can be the rupture disk device, and when the atmospheric pressure in the airtight chamber exceeded the setting value, the rupture disk device can take place the blasting action, can be with the gas outgoing in the first pipe 3, and the rupture disk device has the characteristics of low pressure blasting, can not cause the influence to the emission function of relief valve 2.
When this relief valve leakage detection device moves, the atmospheric pressure in the airtight chamber rises to when rising to the detection range that first pressure monitoring devices 5 set for, can judge that relief valve 2 appears leaking, can judge next according to the atmospheric pressure state in the pressure vessel 1 that relief valve 2 leaks or the pressure release action is discharged unusually:
a) When the second pressure monitoring device detects that the air pressure in the pressure container 1 is maintained unchanged, it can be determined that the safety valve 2 has abnormal leakage and the safety valve 2 needs to be repaired and maintained.
b) When the second pressure monitoring device detects that the air pressure in the pressure container 1 is increased and the air pressure is increased to the action pressure of the safety valve 2, the safety valve 2 can be judged to be released by pressure relief action, and when the air pressure in the sealed cavity is increased to a certain pressure value, the rupture disk device can perform rupture action and can discharge the gas in the sealed cavity.
Wherein, the first pressure monitoring device 5 and the second pressure monitoring device can both be a pressure gauge or a pressure transmitter.
The utility model discloses relief valve leakage detection device can realize monitoring the leakage condition of helium medium relief valve 2, has the characteristics that convenient monitoring was used, the security is good.
In some embodiments, the safety valve leakage detection device includes a second tube 6 and a helium mass spectrometer (not shown), the second tube 6 is communicated with the first tube 3, the first pressure monitoring device 5 is disposed on the second tube 6, the second tube 6 is provided with a leakage detection port (not shown), the leakage detection port is provided with a sealing plug 7, and the helium mass spectrometer is suitable for being connected with the leakage detection port after the sealing plug 7 is removed.
Specifically, as shown in fig. 1, one end of the second tube 6 may be in communication with the sealed chamber in the first tube 3, the leakage detection port may be provided at the other end of the second tube 6, when the safety valve leakage detection device operates normally, the sealing plug 7 is detachably plugged at the leakage detection port, the first tube 3 and the second tube 6 are in a communicating state, and the first pressure monitoring device 5 may obtain the air pressure in the sealed chamber by detecting the air pressure in the second tube 6.
When first pressure monitoring device 5 detects the atmospheric pressure rise in the airtight chamber, when second pressure monitoring device detects the atmospheric pressure in pressure vessel 1 and maintains unchangeably, can demolish sealed end cap 7, and install helium mass spectrometer in leak detection mouth department, when helium mass spectrometer detects helium composition, then can judge that relief valve 2 has unusual the leakage, if helium mass spectrometer does not detect helium composition, then can judge that the atmospheric pressure rise in the airtight chamber is the gas expansion that the temperature rises and causes, can judge that relief valve 2 does not have unusual the leakage, the design of this structure, can effectually get rid of because the influence of the gas expansion that the difference in temperature caused to relief valve 2 leak monitoring.
In some embodiments, the safety valve leakage detection device comprises a third pipe 8 and a first isolation device 9, the third pipe 8 is suitable for communicating the pressure vessel 1 and the safety valve 2, and the first isolation device 9 is arranged on the third pipe 8 and is suitable for opening and closing the third pipe 8.
Specifically, as shown in fig. 1, one end of the third pipe 8 may be communicated with the pressure vessel 1, the other end of the third pipe 8 may be connected to the safety valve 2, the first isolating device 9 may be a valve and is installed on the third pipe 8, when the safety valve leakage detecting device operates normally, the first isolating device 9 is in an open state, so that the third pipe 8 is unblocked, and when the safety valve 2 has abnormal leakage and needs to be overhauled and maintained, or when other elements of the safety valve leakage detecting device need to be overhauled and maintained, the first isolating device 9 may be controlled to be closed, so as to block the third pipe 8, thereby facilitating the overhaul and maintenance.
In some embodiments, the safety valve leakage detection device comprises a second isolation device 10, the second isolation device 10 is disposed on the second pipe 6 and is adapted to open and close the second pipe 6, and the second isolation device 10 is located between the first pressure monitoring device 5 and the first pipe 3.
Specifically, as shown in fig. 1, the second isolating device 10 may be a valve, when the safety valve leakage detecting device operates normally, the second isolating device 10 is in an open state to open the second pipe 6, and when the first pressure monitoring device 5 or the leakage detecting port needs to be repaired or maintained, the second isolating device 10 may be controlled to be closed to block the second pipe 6.
In some embodiments, the safety valve leakage detection means comprises a fourth pipe 11, said fourth pipe 11 being connected to the pressure relief means 4, adapted to vent the gas inside the first pipe 3. Specifically, as shown in fig. 1, when the pressure in the first pipe 3 rises to a certain pressure value and the pressure relief device 4 releases pressure, the fourth pipe 11 can facilitate directional discharge of the gas.
A primary circuit of a nuclear power plant according to an embodiment of the present invention will be described.
The utility model discloses a nuclear power station return circuit includes relief valve leakage detection device, and 2 leakage devices of relief valve can be for 2 leakage devices of relief valve described in the above-mentioned embodiment. Specifically, the nuclear power station primary circuit can monitor the leakage condition of the safety valve 2, and can eliminate the influence of gas expansion on leakage monitoring caused by temperature difference.
In the description of the present invention, it is to be understood that the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential", and the like, indicate the orientation or positional relationship indicated based on the drawings, and are only for convenience of description and simplicity of description, and do not indicate or imply that the device or element referred to must have a particular orientation, be constructed and operated in a particular orientation, and therefore, should not be construed as limiting the present 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 to implicitly indicate the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one of the feature. In the description of the present invention, "a plurality" means at least two, e.g., two, three, etc., unless expressly specified otherwise.
In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," and "fixed" are to be construed broadly and may, for example, be fixedly connected, detachably connected, or integrally formed; may be mechanically coupled, may be electrically coupled or may be in communication with each other; they may be directly connected or indirectly connected through intervening media, or they may be interconnected within two elements or in a relationship where two elements interact with each other unless otherwise specifically limited. The specific meaning of the above terms in the present invention can be understood according to specific situations by those skilled in the art.
In the present application, unless expressly stated or limited otherwise, the first feature may be directly on or directly under the second feature or indirectly via intermediate members. Also, a first feature "on," "above," and "over" a second feature may be directly on or obliquely above the second feature, or simply mean that the first feature is at a higher level than the second feature. A first feature being "under," "below," and "beneath" a second feature may be directly under or obliquely under the first feature, or may simply mean that the first feature is at a lesser elevation than the second feature.
In the description herein, references to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the invention. In this specification, the schematic representations of the terms used above are not necessarily intended to refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Moreover, various embodiments or examples and features of various embodiments or examples described in this specification can be combined and combined by one skilled in the art without being mutually inconsistent.
While embodiments of the present invention have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention, and that variations, modifications, substitutions and alterations of the above embodiments may be made by those of ordinary skill in the art without departing from the scope of the present invention.

Claims (9)

1. A safety valve leak detection device, comprising:
a safety valve adapted to be connected to the pressure vessel;
the safety valve is arranged at one end of the first pipe, and the pressure relief device is arranged at the other end of the first pipe;
a first pressure monitoring device in communication with the first tube adapted to monitor a gas pressure within the first tube.
2. The safety valve leakage detection device of claim 1, including a second tube in communication with the first tube, the first pressure monitoring device being disposed in the second tube, the second tube having a leakage detection port, the leakage detection port having a sealing plug.
3. The safety valve leak detection device of claim 2, comprising a helium mass spectrometer adapted to be connected to the leak detection port after removal of the sealing plug.
4. The safety valve leak detection device according to claim 1, comprising a third pipe adapted to communicate the pressure vessel with the safety valve, and a first isolation device provided in the third pipe so as to be adapted to open and close the third pipe.
5. The safety valve leak detection device of claim 2, comprising a second isolation device provided to the second pipe so as to be adapted to open and close the second pipe, the second isolation device being located between the first pressure monitoring device and the first pipe.
6. The safety valve leak detection device of claim 1, comprising a fourth tube connected to the pressure relief device adapted to vent gas in the first tube.
7. The safety valve leak detection device of claim 1, wherein the first pressure monitoring device is a pressure gauge or a pressure transmitter.
8. The safety valve leak detection device of claim 1, wherein the pressure relief device is a rupture disc device.
9. A primary circuit for a nuclear power plant, comprising a safety valve leakage detection device according to any one of claims 1 to 8.
CN202221815368.XU 2022-07-14 2022-07-14 Safety valve leakage detection device and nuclear power station primary circuit Active CN218299390U (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
CN202221815368.XU CN218299390U (en) 2022-07-14 2022-07-14 Safety valve leakage detection device and nuclear power station primary circuit
DE202023102662.1U DE202023102662U1 (en) 2022-07-14 2023-05-16 A leak detection device for safety valve and circuit for nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202221815368.XU CN218299390U (en) 2022-07-14 2022-07-14 Safety valve leakage detection device and nuclear power station primary circuit

Publications (1)

Publication Number Publication Date
CN218299390U true CN218299390U (en) 2023-01-13

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CN202221815368.XU Active CN218299390U (en) 2022-07-14 2022-07-14 Safety valve leakage detection device and nuclear power station primary circuit

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CN (1) CN218299390U (en)
DE (1) DE202023102662U1 (en)

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