CN216307404U - Steam trap for nuclear power station - Google Patents

Steam trap for nuclear power station Download PDF

Info

Publication number
CN216307404U
CN216307404U CN202122602390.8U CN202122602390U CN216307404U CN 216307404 U CN216307404 U CN 216307404U CN 202122602390 U CN202122602390 U CN 202122602390U CN 216307404 U CN216307404 U CN 216307404U
Authority
CN
China
Prior art keywords
communication hole
steam trap
nuclear power
valve
valve body
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.)
Active
Application number
CN202122602390.8U
Other languages
Chinese (zh)
Inventor
王远国
苏尚球
王明哲
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
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
Original Assignee
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
Priority date (The priority date 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 date listed.)
Filing date
Publication date
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 CN202122602390.8U priority Critical patent/CN216307404U/en
Application granted granted Critical
Publication of CN216307404U publication Critical patent/CN216307404U/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Landscapes

  • Lift Valve (AREA)
  • Details Of Valves (AREA)

Abstract

The utility model belongs to the technical field of nuclear power station operation optimization, and particularly relates to a steam trap for a nuclear power station. The steam trap for the nuclear power station comprises a valve body, a disc and a heat-insulating cover; the valve body is provided with an accommodating cavity, and an inflow channel and an outflow channel which are communicated with the accommodating cavity; the disc is installed in the accommodating chamber, and the disc is disposed between the inflow channel and the outflow channel; the heat preservation cover is coated on the valve body and used for preserving heat of the medium in the accommodating cavity. In the utility model, the heat-insulating cover can keep the temperature of the medium in the accommodating cavity, so that the stability of the steam trap for the nuclear power station is improved; and the steam trap for the nuclear power station has simple structure and convenient installation.

Description

Steam trap for nuclear power station
Technical Field
The utility model belongs to the technical field of nuclear power station operation optimization, and particularly relates to a steam trap for a nuclear power station.
Background
A steam trap, also called a trap, an automatic drain, a condensate drain, etc., is installed in a steam pipe and functions to continuously drain condensate in the steam pipe out of the pipe. In a nuclear power plant, steam traps are installed in a nuclear power plant steam supply system, a nuclear power plant steam turbine bypass system, and the like. The working principle of the steam trap is as follows: by utilizing the difference of the densities of steam and water, when the steam trap is started, condensed water appears in the pipeline, and the condensed water pushes away the disc of the steam trap by working pressure, so that the condensed water in the pipeline is quickly discharged through the steam trap; when the condensed water is discharged, the steam in the pipeline enters the steam trap, the volume of the steam in the steam trap is rapidly enlarged, and the suction force of the disc at the steam flow velocity is reduced to rapidly close the steam trap because the steam has a flow velocity higher than that of the condensed water.
In the prior art, the steam trap for the nuclear power station has the condition of low running stability when the disc is closed, and the accident of mistaken opening of the disc can be caused frequently.
SUMMERY OF THE UTILITY MODEL
The utility model provides a steam trap for a nuclear power station, aiming at the technical problem that the running stability of the steam trap for the nuclear power station is not high when a disc is closed in the prior art.
In view of the above technical problems, an embodiment of the present invention provides a steam trap for a nuclear power station, including a valve body, a disc, and a heat-insulating cover; the valve body is provided with an accommodating cavity, and an inflow channel and an outflow channel which are communicated with the accommodating cavity; the disc is installed in the accommodating chamber, and the disc is disposed between the inflow channel and the outflow channel; the heat preservation cover is coated on the valve body and used for preserving heat of the medium in the accommodating cavity.
Optionally, the nuclear power plant steam trap further includes a filter mounted in the inflow passage.
Optionally, the valve body comprises a valve seat and a first valve cover and a second valve cover which are installed at two opposite ends of the valve seat, and the accommodating cavity is arranged on the first valve cover;
the inflow passage includes a first communication hole provided on the valve seat, and a second communication hole and a third communication hole both provided on the second valve cover; the first communication hole is communicated between the second communication hole and the third communication hole, and one end, far away from the second communication hole, of the third communication hole is communicated with the accommodating cavity;
the outflow passage includes a fourth communication hole provided in the valve seat and communicating with the accommodation chamber.
Optionally, the second valve cover is provided with a first projection inserted into the third communication hole, and the third communication hole penetrates through the first projection; the valve body further comprises a first sealing element which is sleeved on the first bulge and used for sealing the connection position of the first communication hole and the second communication hole.
Optionally, the valve body further comprises a first fixing piece, a first mounting hole is formed in the first valve cover, a second mounting hole is formed in the valve seat, and the first valve cover is mounted on the valve seat through the first fixing piece inserted into the first mounting hole and the second mounting hole.
Optionally, the valve body further comprises a second fixing member, a third mounting hole is formed in the second valve cover, and the second valve cover is mounted on the valve seat through the second fixing member inserted into the third mounting hole and the second mounting hole.
Optionally, the outflow passage further includes an annular groove provided on the valve seat, the annular groove being provided around an end of the third communication hole remote from the second communication hole, the fourth communication hole communicating with the accommodation chamber through the annular groove.
Optionally, a second protrusion inserted into the accommodating cavity is further disposed on the valve seat, the annular groove is disposed on the second protrusion, and the third communication hole penetrates through the second protrusion.
Optionally, the valve body further comprises a second sealing member sleeved on the second protrusion for sealing and connecting the annular groove and the accommodating cavity.
Optionally, the outflow channel further includes a fifth communication hole provided on the second projection, the fourth communication hole communicating with the annular groove through the fifth communication hole.
In the utility model, the valve body is provided with an accommodating cavity, and an inflow channel and an outflow channel which are communicated with the accommodating cavity; the disc is installed in the accommodating chamber, and the disc is disposed between the inflow channel and the outflow channel; the heat preservation cover is coated on the valve body and used for preserving heat of the medium in the accommodating cavity. The heat-insulating cover can slow down the loss speed of the temperature of a medium (such as steam) in the accommodating cavity, and can better keep the temperature of the steam in the accommodating cavity when the medium in the accommodating cavity is the steam, so that the pressure above the disc is greater than the pressure below the disc, the disc is tightly covered to separate the outflow channel from the outflow channel, and the tight closing function of the steam trap for the nuclear power station is realized. In the utility model, the heat-insulating cover can keep the temperature of the medium in the accommodating cavity, thereby improving the operation stability of the steam trap for the nuclear power station (particularly when a disc is closed); and the steam trap for the nuclear power station has simple structure and convenient installation.
Drawings
The utility model is further illustrated with reference to the following figures and examples.
FIG. 1 is a schematic structural view of a steam trap for a nuclear power plant according to an embodiment of the present invention;
FIG. 2 is an exploded view of a steam trap for a nuclear power plant in accordance with an embodiment of the present invention;
FIG. 3 is a schematic view of a steam trap for a nuclear power plant provided in accordance with another embodiment of the present invention when open;
fig. 4 is a schematic view of a steam trap for a nuclear power plant according to another embodiment of the present invention, when closed.
The reference numerals in the specification are as follows:
1. a valve body; 11. an accommodating chamber; 12. an inflow channel; 121. a first communication hole; 122. a second communication hole; 123. a third communication hole; 13. an outflow channel; 131. a fourth communication hole; 132. an annular groove; 133. a fifth communication hole; 14. a valve seat; 141. a second mounting hole; 142. a second protrusion; 15. a first valve cover; 151. a first mounting hole; 16. a second valve cover; 161. a third mounting hole; 162. a first protrusion; 17. a first seal member; 18. a first fixing member; 19. a second fixing member; 110. a second seal member; 2. a disc; 3. and (4) a filter element.
Detailed Description
In order to make the technical problems, technical solutions and advantageous effects solved by the present invention more clearly apparent, the present invention is further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the utility model and are not intended to limit the utility model.
It is to be understood that the terms "upper", "lower", "left", "right", "front", "rear", "middle", and the like, as used herein, refer to an orientation or positional relationship based on that shown in the drawings, which is for convenience in describing and simplifying the present invention, and do not indicate or imply that the referenced device or element must have a particular orientation, be constructed and operated in a particular orientation, and thus, should not be considered as limiting the present invention.
As shown in fig. 1 and fig. 2, a steam trap for a nuclear power plant according to an embodiment of the present invention includes a valve body 1, a disc 2, and a heat-insulating cover (not shown); the valve body 1 is provided with an accommodating cavity 11, and an inflow channel 12 and an outflow channel 13 which are communicated with the accommodating cavity 11; the disc 2 is mounted in the housing chamber 11 with the disc 2 disposed between the inflow channel 12 and the outflow channel 13; the heat preservation cover is coated on the valve body 1 and used for preserving heat of the medium in the accommodating cavity 11. It can be understood that the end of the inflow channel 12 far from the containing cavity 11 is communicated with a high-pressure pipeline of a nuclear power plant, the end of the outflow channel far from the containing cavity 11 is communicated with a vacuum pipeline of the nuclear power plant, the disc 2 is positioned above the outlet of the inflow channel 12 and the outlet of the outflow channel 13, and when the disc 2 covers the outlet of the inflow channel 12 and the outlet of the outflow channel 13, the inflow channel 12 is not communicated with the outflow channel 13.
Specifically, as shown in fig. 3, when the condensed water having a high pressure flows into the inflow channel 12, the condensed water may jack up the disc 2, so that the inflow channel 12 and the outflow channel 13 communicate through the receiving chamber 11, and the trap for a nuclear power plant may discharge the condensed water. As shown in fig. 4, when the condensed water in the inflow channel 12 is completely discharged, the steam in the nuclear power plant rapidly enters the inflow channel 12, because the flow rate of the steam is greater than that of the condensed water, according to bernoulli's principle, the inflow channel 12 and the outflow channel 13 form a low pressure region, and the upper and lower surfaces of the disc receive pressure, because the force-receiving area under the disc 2 is smaller than that of the upper surface, so that the pressure under the disc 2 is smaller than that of the upper surface, the disc 2 tightly and rapidly covers the outlet of the outflow channel 13 and the inlet of the outflow channel 13, and the steam trap for the nuclear power plant is tightly closed. When the inflow channel 12 is filled with the condensed water again, the steam in the accommodating cavity 11 is condensed into the condensed water due to the temperature reduction, the pressure difference between the upper surface and the lower surface of the disc 2 disappears, so that the condensed water in the inflow channel 12 jacks up the disc 2 by the pressure of the condensed water, the steam trap for the nuclear power station can complete the discharge of the condensed water, and the steam trap for the nuclear power station can realize the functions of circular discharge and intermittent drainage.
In the utility model, an accommodating cavity 11, an inflow channel 12 and an outflow channel 13 which are communicated with the accommodating cavity 11 are arranged on the valve body 1; the disc 2 is mounted in the housing chamber 11 with the disc 2 disposed between the inflow channel 12 and the outflow channel 13; the heat preservation cover is coated on the valve body 1 and used for preserving heat of the medium in the accommodating cavity 11. The heat-insulating cover can slow down the dissipation speed of the temperature of the medium (such as steam) in the accommodating cavity 11, and when the medium in the accommodating cavity 11 is steam, the temperature of the steam in the accommodating cavity 11 can be better maintained, so that the pressure above the disc 2 is greater than the pressure below the disc 2, and the disc 2 is tightly covered to separate the outflow channel 13 and the outflow channel 13, thereby realizing the function of tightly closing the steam trap for the nuclear power station. In the utility model, the heat-insulating cover can keep the temperature of the medium in the accommodating cavity 11, thereby improving the operation stability of the steam trap for the nuclear power station (particularly when a disc is closed); and the steam trap for the nuclear power station has simple structure and convenient installation.
In one embodiment, as shown in fig. 1 and 2, the steam trap for nuclear power plants further includes a filter member 3 installed in the inflow path 12. It will be understood that the filter element 3 includes, but is not limited to, a filter screen, etc., and the first filter element 3 can filter the impurities in the condensed water and steam from the inflow channel 12, thereby preventing the impurities in the inflow channel 12 from entering the vacuum pipe of the nuclear power plant through the outflow channel 13, and the filter element 3 improves the cleanliness of the steam trap for the nuclear power plant and prolongs the service life thereof.
In one embodiment, as shown in fig. 1 and 2, the valve body 1 includes a valve seat 14 and a first valve cover 15 and a second valve cover 16 mounted at opposite ends of the valve seat 14, and the receiving cavity 11 is disposed on the first valve cover 15; as can be appreciated, the valve seat 14 is located between the first valve cover 15 and the second valve cover 16.
As shown in fig. 3 and 4, the inflow channel 12 includes a first communication hole 121 provided on the valve seat 14, and a second communication hole 122 and a third communication hole 123 both provided on the second valve cover 16; the first communication hole 121 communicates between the second communication hole 122 and the third communication hole 123, and one end of the third communication hole 123 remote from the second communication hole 122 communicates with the housing chamber 11; as can be understood, one end of the first communication hole 121, which is far away from the second communication hole 122, communicates with a nuclear power plant high-pressure pipeline; and the shapes of the first communicating hole 121 and the second communicating hole 122 may be designed according to actual requirements. As can be understood, one end of the second communication hole 122, which is far from the first communication hole 121, communicates with a nuclear power plant high-pressure pipeline; and the shapes of the first communication hole 121, the second communication hole 122, and the third communication hole 123 may be designed according to actual requirements. Further, the filter member 3 is mounted in the one-through hole.
The outflow channel 13 includes a fourth communication hole 131 provided on the valve seat 14 and communicating with the accommodation chamber 11. It is understood that an end of the fourth communication hole 131, which is far from the accommodating chamber 11, communicates with a nuclear power plant vacuum pipe, and the shape of the fourth communication hole 131 may be designed according to actual requirements. In this embodiment, the valve body 1 has a simple structure, is convenient to install, and has low manufacturing cost.
In one embodiment, as shown in fig. 2, the second valve seat 14 is provided with a first protrusion 162 inserted into the third communication hole 123, and the third communication hole 123 penetrates through the first protrusion 162; the valve body 1 further includes a first sealing member 17 sleeved on the first protrusion 162 and used for sealing a connection position of the first communication hole 121 and the second communication hole 122. It will be appreciated that the first seal 17 includes, but is not limited to, a seal ring or the like; the first packing 17 may seal the connection position of the valve seat 14 and the second valve cover 16, and the outer ring of the first packing 17 abuts against the inner wall of the third communication hole 123, so that the condensed water or steam in the inflow passage 12 may be prevented from leaking from the connection position of the valve seat 14 and the second valve cover 16.
In an embodiment, as shown in fig. 1 and 2, the valve body 1 further includes a first fixing member 18, the first bonnet 15 is provided with a first mounting hole 151, the valve seat 14 is provided with a second mounting hole 141, and the first bonnet 15 is mounted on the valve seat 14 by the first fixing member 18 inserted into the first mounting hole 151 and the second mounting hole 141. It is understood that the first fastener 18 includes, but is not limited to, a bolt, a screw, etc.; in this embodiment, the first cover 15 is mounted on the valve seat 14 by the first fixing member 18 inserted into the first mounting hole 151 and the second mounting hole 141, and thus, the mounting is simple and the manufacturing cost is low.
In one embodiment, as shown in fig. 1 and 2, the valve body 1 further includes a second fixing member 19, a third mounting hole 161 is formed on the second valve cover 16, and the second valve cover 16 is mounted on the valve seat 14 by the second fixing member 19 inserted into the third mounting hole 161 and the second mounting hole 141. It is understood that the second fixing member 19 includes, but is not limited to, a bolt, a screw, etc.; and the first fixing member 18 and the second fixing member 19 are inserted into opposite ends of the second mounting hole 141, respectively. In this embodiment, the second cover 16 is mounted on the valve seat 14 by the second fixing member 19 inserted into the third mounting hole 161 and the second mounting hole 141, and thus, the mounting is simple and the manufacturing cost is low.
In one embodiment, as shown in fig. 1, the outflow channel 13 further includes an annular groove 132 provided on the valve seat 14, the annular groove 132 is provided around an end of the third communication hole 123 remote from the second communication hole 122, and the fourth communication hole 131 communicates with the housing chamber 11 through the annular groove 132. The outlet of the second communication hole 122 is provided at a central position surrounded by the annular groove 132. Specifically, the disc blocks the inflow passage 12 and the outflow passage 13 by covering the annular groove 132. It can be understood that the medium in the third communication hole 123 flows out from the center position of the annular groove 132 and flows into the third communication hole 123 through the annular groove 132, which improves the stability of the steam trap for a nuclear power plant.
In an embodiment, as shown in fig. 2, the valve seat 14 is further provided with a second protrusion 142 inserted into the accommodating chamber 11, the annular groove 132 is provided on the second protrusion 142, and the third communication hole 123 penetrates through the second protrusion 142. It can be understood that the disc 2 is located above the second protrusion 142, and when the disc 2 covers the second protrusion 142, the third communication hole 123 and the annular groove 132 are not communicated with each other, that is, the trap for a nuclear power plant is in a closed state. In this embodiment, the second protrusion 142 is designed to improve the stability of the steam trap for a nuclear power plant.
In an embodiment, as shown in fig. 2, the valve body 1 further includes a second sealing member 110 sleeved on the second protrusion 142 for sealing and connecting the annular groove 132 and the accommodating chamber 11. It is understood that the second sealing element 110 includes, but is not limited to, a sealing ring, etc., the outer ring of the second sealing element 110 is abutted against the inner sidewall of the accommodating chamber 11, and the second sealing element 110 can prevent the medium in the annular groove 132 and the accommodating chamber 11 from leaking from the position where the first valve cover 15 and the valve seat 14 are connected.
In an embodiment, as shown in fig. 1, the outflow channel 13 further comprises a fifth communication hole 133 provided on the second projection 142, the fourth communication hole 131 communicating with the annular groove 132 through the fifth communication hole 133. In this embodiment, the annular groove 132 communicates with the third communication hole 123 through the fifth communication hole 133, which reduces the manufacturing difficulty of the steam trap for a nuclear power plant, thereby reducing the manufacturing cost thereof.
In one embodiment, the steam trap for nuclear power plants further comprises an alarm device (not shown) for giving an alarm in case of a failure of the inflow channel 12 and/or the outflow channel 13. It is understood that the alarm device comprises an audible and visual alarm and the like, and when the inflow channel 12 is blocked and/or the outflow channel 13 is blocked and the like, the alarm device gives an alarm to promote a maintainer to overhaul the steam trap for the nuclear power station.
The above description is only exemplary of the steam trap for nuclear power plants and should not be construed as limiting the present invention, and any modification, equivalent replacement, or improvement made within the spirit and principle of the present invention should be included in the scope of the present invention.

Claims (10)

1. A steam trap for a nuclear power station is characterized by comprising a valve body, a disc and a heat-insulating cover; the valve body is provided with an accommodating cavity, and an inflow channel and an outflow channel which are communicated with the accommodating cavity; the disc is installed in the accommodating chamber, and the disc is disposed between the inflow channel and the outflow channel; the heat preservation cover is coated on the valve body and used for preserving heat of the medium in the accommodating cavity.
2. The nuclear power plant steam trap as recited in claim 1 further comprising a filter mounted in the inflow passage.
3. The steam trap of claim 1, wherein the valve body includes a valve seat and first and second valve covers mounted on opposite ends of the valve seat, the receiving cavity being disposed on the first valve cover;
the inflow passage includes a first communication hole provided on the valve seat, and a second communication hole and a third communication hole both provided on the second valve cover; the first communication hole is communicated between the second communication hole and the third communication hole, and one end, far away from the second communication hole, of the third communication hole is communicated with the accommodating cavity;
the outflow passage includes a fourth communication hole provided in the valve seat and communicating with the accommodation chamber.
4. The steam trap for nuclear power plant according to claim 3, wherein the second valve cover is provided with a first projection inserted into the third communication hole, the third communication hole penetrating the first projection; the valve body further comprises a first sealing element which is sleeved on the first bulge and used for sealing the connection position of the first communication hole and the second communication hole.
5. The steam trap of claim 3, wherein the valve body further comprises a first fixing member, the first valve cover is provided with a first mounting hole, the valve seat is provided with a second mounting hole, and the first valve cover is mounted on the valve seat by the first fixing member inserted into the first mounting hole and the second mounting hole.
6. The steam trap of claim 5, wherein the valve body further comprises a second fixing member, the second valve cover having a third mounting hole formed therein, the second valve cover being mounted to the valve seat by the second fixing member inserted into the third mounting hole and the second mounting hole.
7. The steam trap for nuclear power plant according to claim 3, wherein the outflow passage further includes an annular groove provided on the valve seat, the annular groove being provided around an end of the third communication hole remote from the second communication hole, the fourth communication hole communicating with the accommodation chamber through the annular groove.
8. The steam trap of claim 7, wherein the valve seat is further provided with a second projection inserted into the receiving chamber, the annular groove is provided in the second projection, and the third communication hole penetrates the second projection.
9. The steam trap of claim 8, wherein the valve body further comprises a second seal that is sleeved over the second protrusion for sealingly connecting the annular groove and the containment cavity.
10. The steam trap for nuclear power plant according to claim 8, wherein the outflow channel further includes a fifth communication hole provided on the second projection, the fourth communication hole communicating with the annular groove through the fifth communication hole.
CN202122602390.8U 2021-10-26 2021-10-26 Steam trap for nuclear power station Active CN216307404U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202122602390.8U CN216307404U (en) 2021-10-26 2021-10-26 Steam trap for nuclear power station

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202122602390.8U CN216307404U (en) 2021-10-26 2021-10-26 Steam trap for nuclear power station

Publications (1)

Publication Number Publication Date
CN216307404U true CN216307404U (en) 2022-04-15

Family

ID=81116733

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202122602390.8U Active CN216307404U (en) 2021-10-26 2021-10-26 Steam trap for nuclear power station

Country Status (1)

Country Link
CN (1) CN216307404U (en)

Similar Documents

Publication Publication Date Title
CN215985067U (en) Leakage monitoring device for pneumatic steam trap of steam turbine
CN216307404U (en) Steam trap for nuclear power station
JP3919284B2 (en) Anti-freeze type air valve
CN109611567B (en) Collect water regulating, pressure release, drainage, moisturizing function in water inlet joint
CN210770465U (en) Filter system protector capable of automatically closing water path
CN209743615U (en) Water inlet joint integrating functions of water regulation, pressure relief, water drainage and water supplement
JP4080049B2 (en) Freezing prevention valve
CN112747108A (en) Speed reducer with ventilation structure
CN220352984U (en) Water hammer pressure relief device
CN220470722U (en) Steam extraction check valve
JPH0111810Y2 (en)
CN209892787U (en) Combined multifunctional integrated valve telescopic flange connection filter
CN217874373U (en) Explosion-proof safety valve
JPS5927600Y2 (en) steam trap
CN216769041U (en) Free floating ball type steam trap
CN214093130U (en) Pneumatic fluorine-lined ball valve
CN216952581U (en) Combined sealed drainage stop valve
CN215636488U (en) Steam trap
CN215831197U (en) Diaphragm valve with double sealing structure
CN219263264U (en) Closestool and sealing structure of control valve thereof
CN215804889U (en) Motorcycle and external fuel pump assembly structure thereof
CN220749437U (en) Valve assembly, liquid cooling pipeline system and liquid cooling equipment
CN211667223U (en) A bypass valve for water purification unit
CN218094471U (en) Automatic water escape valve
JPH01210697A (en) Float type steam trap

Legal Events

Date Code Title Description
GR01 Patent grant
GR01 Patent grant