CN215217949U - Device for detecting sealing performance of gas chamber of bypass exhaust valve of steam turbine of nuclear power plant - Google Patents
Device for detecting sealing performance of gas chamber of bypass exhaust valve of steam turbine of nuclear power plant Download PDFInfo
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- CN215217949U CN215217949U CN202121186982.XU CN202121186982U CN215217949U CN 215217949 U CN215217949 U CN 215217949U CN 202121186982 U CN202121186982 U CN 202121186982U CN 215217949 U CN215217949 U CN 215217949U
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Abstract
The utility model relates to a pneumatic valve maintenance field of nuclear power plant especially relates to other row valve air chamber leakproofness detection device of nuclear power plant's steam turbine. Other discharge valve air chamber leakproofness detection device of nuclear power plant steam turbine includes: the device comprises a manual ball valve, an instrument copper pipe, a pressure reducing valve, a pressure gauge, a special joint, an air inlet hose and a steam turbine bypass valve actuating mechanism cylinder which are sequentially connected. The utility model discloses effectively solve "hualong No. one" and other row valve of M310 nuclear power unit steam turbine and overhaul, debug, performance diagnosis etc. work limitation, improve power plant equipment performance reliability and unit operation security.
Description
Technical Field
The utility model relates to a pneumatic valve maintenance field of nuclear power plant especially relates to other row valve air chamber leakproofness detection device of nuclear power plant's steam turbine.
Background
The steam turbine bypass valve is the most important equipment of a steam turbine bypass system, when a steam turbine is in full-power operation or is in service operation, and a reactor is not stopped, the steam turbine bypass valve can discharge redundant steam to a condenser, so that the temperature and pressure in a nuclear steam supply system are prevented from exceeding a protection threshold value, and the safety of a nuclear power unit is ensured. The number of the by-pass valves of the single-unit steam turbine is 12, and high performance and reliability such as quick opening for 2.5s, quick closing for 5s, full-stroke opening and closing time for 10s, linear adjustment characteristics, full-stroke adjustment, high adjustment precision and the like need to be ensured in the process of putting the equipment into use.
The air chamber tightness of a pneumatic actuating mechanism of a steam turbine bypass valve is one of important parameters for ensuring the performance of the valve, and the air leakage of the air chamber of the pneumatic actuating mechanism can cause the reduction of the valve adjusting performance, the failure of quick opening, overtime opening, full opening and the like, thereby seriously influencing the availability of a steam turbine bypass system and influencing the operation safety of a unit.
At present, a 'Hualongyi' nuclear power unit turbine side exhaust valve does not have a special air chamber tightness detection device and a special air chamber tightness detection tool, leakage can be simply detected by using leakage detection liquid at accessible positions of a lower air cylinder and a diaphragm edge flange of an actuating mechanism when the valve is put into use, leakage quantity cannot be quantitatively detected, leakage of an upper cavity of the actuating mechanism cannot be detected, field equipment is overhauled and debugged to have large limitation, and equipment performance and reliability cannot be guaranteed.
SUMMERY OF THE UTILITY MODEL
The to-be-solved technical problem of the utility model is: the device for detecting the tightness of the gas chamber of the bypass exhaust valve of the steam turbine of the nuclear power plant is provided, the working limitations of overhauling, debugging, performance diagnosis and the like of the bypass exhaust valve of the steam turbine of the nuclear power plant 'Hualong I' are effectively solved, and the performance reliability and the operation safety of the unit of the power plant are improved.
The utility model provides a other row valve air chamber leakproofness detection device of nuclear power plant's steam turbine, include: the device comprises a manual ball valve, an instrument copper pipe, a pressure reducing valve, a pressure gauge, a special joint, an air inlet hose and a steam turbine bypass valve actuating mechanism cylinder which are sequentially connected.
Preferably, the method further comprises the following steps: and one end of the manual ball valve is connected with the first joint, and the other end of the manual ball valve is connected with the copper pipe for the instrument.
Preferably, a second joint and a third joint are sequentially connected between the pressure gauge and the special joint;
preferably, one end of the special joint is a metric male thread joint, the other end of the special joint is an NPT male thread joint, and the middle of the special joint is a hexagonal head;
the metric external thread joint end of the special joint is connected with the air inlet hose,
the NPT external thread joint end of the special joint is connected with the third joint.
Preferably, the first joint is a ferrule type tapered thread elbow joint.
Preferably, the second joint is a ferrule type taper thread straight-through pipe joint.
Preferably, the third joint is a straight through butt joint with an inner taper thread and a constant diameter.
Preferably, the pressure reducing valve is a pressure reducing valve with the range of 0-2 Mpa.
Preferably, the pressure gauge is a digital display pressure gauge.
Preferably, the digital display pressure gauge 5 has the precision of 0.1kPa, the measuring range of 0.1-0.7 MPa and has the pressure display function.
Compared with the prior art, the utility model discloses a other row valve air chamber leakproofness detection device of nuclear power plant's steam turbine has following beneficial effect:
(1) the method is suitable for detecting the air chamber tightness of the exhaust valve actuating mechanism beside the turbine of the nuclear power generating unit of Hualong I or M310, and solves the problem that the air chamber tightness cannot be detected historically by the valves;
(2) the leakage amount of the air chamber can be quantitatively detected, and the air chamber tightness detection is accurate and reliable;
(3) the operation is simple and the operation is stable;
(4) simple structure, low cost, convenient maintenance, safety and reliability.
Drawings
FIG. 1 is a front view of a special connector in the device of the present invention;
FIG. 2 is a left side view of a special fitting in the device of the present invention;
fig. 3 is a schematic structural view of the apparatus according to embodiment 1 of the present invention;
in the figure: 1. a first joint; 2. a manual ball valve; 3. copper tubes for instruments; 4. a pressure reducing valve; 5. a digital display pressure gauge; 6. a second joint; 7. a third joint; 8. a special joint; 9. an air intake hose; 10. and a cylinder of an actuating mechanism of a bypass exhaust valve of the steam turbine.
Detailed Description
For further understanding of the present invention, embodiments of the present invention are described below with reference to examples, but it should be understood that these descriptions are only for the purpose of further illustrating the features and advantages of the present invention, and are not intended to limit the present invention.
An embodiment of the utility model discloses a other row valve air chamber leakproofness detection device of nuclear power plant's steam turbine, include: the device comprises a manual ball valve 2, an instrument copper pipe 3, a pressure reducing valve 4, a pressure gauge 5, a special joint 8, an air inlet hose 9 and a steam turbine bypass valve actuating mechanism cylinder 10 which are connected in sequence.
According to the utility model discloses, preferably, still include: the first joint 1 is a clamping sleeve type taper thread elbow pipe joint, namely an NPT threaded joint. The first joint is used for connecting a gas supply line joint of a positioning device of a bypass valve of a steam turbine, namely, the first joint is connected with a gas source of the device.
The manual ball valve 2 is a manual ball valve with a threaded joint and is used for isolating an air source during a pressure maintaining test of an air chamber of an actuating mechanism.
The copper tube 3 for the instrument is a copper tube used for the instrument and is used for transmitting compressed air.
The pressure reducing valve 4 is preferably a pressure reducing valve with the range of 0-2 Mpa and used for adjusting the air inlet pressure of the air chamber.
The pressure gauge 5 is preferably a digital display pressure gauge, more preferably has the precision of 0.1kPa, the measuring range of 0.1-0.7 Mpa and has a pressure display function.
Preferably, a second joint 6 and a third joint 7 are connected between the pressure gauge and the special joint.
The second joint 6 is a ferrule type taper thread straight-through pipe joint and is used for connecting the copper pipe with the NPT threaded joint 7.
The third joint 7 is an inner-cone thread equal-diameter straight-through butt joint and is used for connecting the NPT threaded joint 6 with the special joint 8.
As shown in fig. 1 and 2, one end of the special joint 8 is a metric male screw joint, the other end is an NPT male screw joint, and the middle is a hexagon;
the metric external thread joint end of the special joint 8 is connected with the air inlet hose,
the NPT male screw joint end of the special joint 8 is connected to the third joint.
Utilize the utility model discloses a method that device carries out gas tightness inspection includes:
firstly, a first connector 1 of the device is connected with a gas supply pipeline connector of a steam turbine bypass valve positioner.
In a second step, the pressure reducing valve 4 is closed manually, i.e. the pressure output after the pressure reducing valve is 0.
And thirdly, manually opening the ball valve 2.
And fourthly, slowly increasing the pressure reducing valve 4, simultaneously observing the value of the pressure gauge 5, and stopping adjusting the pressure reducing valve when the value reaches the rated working pressure of the air chamber of the steam turbine bypass valve actuating mechanism.
And fifthly, manually closing the ball valve 2, and observing and recording the numerical value of the pressure gauge 5.
Sixthly, when the value of the pressure gauge 5 approaches the stability, the pressure drop value delta P in 5 minutes is calculated.
Seventhly, when the pressure drop delta P is smaller than 2.5kPa, the air chamber tightness of the steam turbine bypass exhaust valve actuating mechanism is qualified; when the pressure drop delta P is larger than 2.5kPa, the air chamber sealing performance of the steam turbine bypass exhaust valve actuating mechanism is unqualified, and the steam turbine bypass exhaust valve actuating mechanism needs to be inspected and maintained.
The compressed air source is directly connected with the air supply source of the valve positioner, the air source does not need to be additionally connected and maintained through a pipe, the air bottle does not need to be independently equipped, and a special joint does not need to be manufactured.
For further understanding of the present invention, the following provides a detailed description of the gas chamber tightness detection device of the bypass exhaust valve of the steam turbine of the nuclear power plant with reference to the following embodiments, and the scope of the present invention is not limited by the following embodiments.
Example 1
Nuclear power plant's turbine by-pass discharge valve air chamber leakproofness detection device, as shown in fig. 3, include: the device comprises a first connector 1, a manual ball valve 2, an instrument copper pipe 3, a pressure reducing valve 4, a pressure gauge 5, a second connector 6, a third connector 7, a special connector 8, an air inlet hose 9 and a steam engine bypass exhaust valve actuating mechanism cylinder 10 which are sequentially connected.
The method for performing the airtightness inspection using the apparatus includes:
firstly, a first connector 1 of the device is connected with a gas supply pipeline connector of a steam turbine bypass valve positioner.
In a second step, the pressure reducing valve 4 is closed manually, i.e. the pressure output after the pressure reducing valve is 0.
And thirdly, manually opening the ball valve 2.
And fourthly, slowly increasing the pressure reducing valve 4, simultaneously observing the value of the pressure gauge 5, and stopping adjusting the pressure reducing valve when the value reaches the rated working pressure of the air chamber of the steam turbine bypass valve actuating mechanism.
And fifthly, manually closing the ball valve 2, and observing and recording the numerical value of the pressure gauge 5.
Sixthly, when the value of the pressure gauge 5 approaches the stability, the pressure drop value delta P in 5 minutes is calculated.
Seventhly, when the pressure drop delta P is smaller than 2.5kPa, the air chamber tightness of the steam turbine bypass exhaust valve actuating mechanism is qualified; when the pressure drop delta P is larger than 2.5kPa, the air chamber sealing performance of the steam turbine bypass exhaust valve actuating mechanism is unqualified, and the steam turbine bypass exhaust valve actuating mechanism needs to be inspected and maintained.
The above description of the embodiments is only intended to help understand the method of the present invention and its core ideas. It should be noted that, for those skilled in the art, without departing from the principle of the present invention, the present invention can be further modified and modified, and such modifications and modifications also fall within the protection scope of the appended claims.
The previous description of the disclosed embodiments is provided to enable any person skilled in the art to make or use the present invention. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the generic principles defined herein may be applied to other embodiments without departing from the spirit or scope of the invention. Thus, the present invention is not intended to be limited to the embodiments shown herein but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.
Claims (10)
1. Other row valve air chamber leakproofness detection device of nuclear power plant's steam turbine, its characterized in that includes: the device comprises a manual ball valve, an instrument copper pipe, a pressure reducing valve, a pressure gauge, a special joint, an air inlet hose and a steam turbine bypass valve actuating mechanism cylinder which are sequentially connected.
2. The device for detecting the tightness of the gas chamber of the bypass exhaust valve of the steam turbine of the nuclear power plant as claimed in claim 1, further comprising:
and one end of the manual ball valve is connected with the first joint, and the other end of the manual ball valve is connected with the copper pipe for the instrument.
3. The device for detecting the tightness of the gas chamber of the bypass valve of the steam turbine of the nuclear power plant as claimed in claim 2, wherein a second joint and a third joint are sequentially connected between the pressure gauge and the special joint.
4. The device for detecting the tightness of the gas chamber of the bypass valve of the steam turbine of the nuclear power plant according to claim 3, wherein one end of the special joint is a metric male thread joint, the other end of the special joint is an NPT male thread joint, and the middle of the special joint is a hexagonal joint;
the metric external thread joint end of the special joint is connected with the air inlet hose,
the NPT external thread joint end of the special joint is connected with the third joint.
5. The device for detecting the tightness of the air chamber of the bypass valve of the steam turbine of the nuclear power plant according to claim 2, wherein the first joint is a cutting sleeve type taper thread elbow joint.
6. The device for detecting the tightness of the air chamber of the bypass valve of the steam turbine of the nuclear power plant according to claim 3, wherein the second joint is a ferrule type taper thread straight-through pipe joint.
7. The device for detecting the tightness of the air chamber of the bypass valve of the steam turbine of the nuclear power plant as claimed in claim 3, wherein the third joint is an inner-tapered threaded straight-through butt joint.
8. The device for detecting the tightness of the gas chamber of the bypass exhaust valve of the steam turbine of the nuclear power plant according to claim 1, wherein the pressure reducing valve is a pressure reducing valve with a range of 0-2 Mpa.
9. The device for detecting the tightness of the gas chamber of the bypass valve of the steam turbine of the nuclear power plant according to claim 1, wherein the pressure gauge is a digital display pressure gauge.
10. The device for detecting the tightness of the gas chamber of the bypass valve of the steam turbine of the nuclear power plant according to claim 9, wherein the digital display pressure gauge has the accuracy of 0.1kPa, the measuring range of 0.1-0.7 Mpa and the pressure display function.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202121186982.XU CN215217949U (en) | 2021-05-31 | 2021-05-31 | Device for detecting sealing performance of gas chamber of bypass exhaust valve of steam turbine of nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202121186982.XU CN215217949U (en) | 2021-05-31 | 2021-05-31 | Device for detecting sealing performance of gas chamber of bypass exhaust valve of steam turbine of nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN215217949U true CN215217949U (en) | 2021-12-17 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202121186982.XU Active CN215217949U (en) | 2021-05-31 | 2021-05-31 | Device for detecting sealing performance of gas chamber of bypass exhaust valve of steam turbine of nuclear power plant |
Country Status (1)
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| CN (1) | CN215217949U (en) |
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2021
- 2021-05-31 CN CN202121186982.XU patent/CN215217949U/en active Active
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