CN209812190U - Novel nuclear power station bypass discharge valve case extracting tool - Google Patents
Novel nuclear power station bypass discharge valve case extracting tool Download PDFInfo
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- CN209812190U CN209812190U CN201822232059.XU CN201822232059U CN209812190U CN 209812190 U CN209812190 U CN 209812190U CN 201822232059 U CN201822232059 U CN 201822232059U CN 209812190 U CN209812190 U CN 209812190U
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Abstract
The utility model relates to a technical field is dismantled to the governing valve case of pilot valve, specifically discloses a novel nuclear power station bypass discharge valve case extracting tool. A novel tool for disassembling a valve core of a bypass discharge valve of a nuclear power station comprises an upper pressure plate, a base and a threaded pull rod, wherein the base is arranged at the bottom of the valve core and can limit the rotation of the valve core; a threaded pull rod is arranged between the base and the upper pressure plate, and the upper pressure plate can be controlled to move towards or away from the base through the threaded pull rod. A novel nuclear power station bypass discharge valve case extracting tool, can compress tightly the spring of case interior pilot valve, make pilot valve lock nut not receive the effect of spring force, just so can easily dismantle pilot valve lock nut, effectively improve the efficiency and the security that the valve disintegrates.
Description
Technical Field
The invention belongs to the technical field of valve core dismounting of a regulating valve of a pilot valve, and particularly relates to a novel tool for dismounting a valve core of a bypass discharge valve of a nuclear power station.
Background
In a pressurized water reactor nuclear power plant, the adaptability of the reactor to the load cannot keep up with the adaptability of a steam turbine to the reactor. When the load of the nuclear power plant is greatly reduced by the power grid, the steam turbine can quickly close the regulating valve to reduce the output power of the steam turbine, but the reactor cannot greatly reduce the power and only slowly and gradually reduces the power, so that a power difference is generated between the reactor and the steam turbine, and the output steam quantity of the reactor is greater than the input steam quantity of the steam turbine. The bypass discharge valve has the functions of providing an artificial load, balancing the power difference between the reactor and the steam turbine, discharging the redundant steam quantity to the condenser and ensuring the safe operation of the reactor. In order to ensure the normal function of the bypass regulating valve, preventive disintegration inspection work is required to be carried out every two years. If the valve leaks, the valve needs to be disassembled to check. When the valve core pilot valve is disassembled, the pilot valve locking nut is difficult to disassemble due to the action of the spring force, and the thread of the locking nut risks being damaged.
Disclosure of Invention
The invention aims to provide a novel tool for disassembling a valve core of a bypass discharge valve of a nuclear power station, which can solve the problem of disassembling the valve core of the bypass discharge valve and improve the efficiency and the safety of disassembling the valve core of the bypass discharge valve.
The technical scheme of the invention is as follows: a novel tool for disassembling a valve core of a bypass discharge valve of a nuclear power station comprises an upper pressure plate, a base and a threaded pull rod, wherein the base is arranged at the bottom of the valve core and can limit the rotation of the valve core; a threaded pull rod is arranged between the base and the upper pressure plate, and the upper pressure plate can be controlled to move towards or away from the base through the threaded pull rod.
The base is of a disc structure with lugs at two ends, an anti-rotation pin A and an anti-rotation pin B are fixed on the upper end face of the base, and the sizes of the anti-rotation pin A and the anti-rotation pin B and the distance between the sizes of the anti-rotation pin A and the anti-rotation pin B are matched with a hole at the bottom of the valve core to be disassembled.
The lower end face of the base is provided with a clamping seat, and the rotation of the base is limited by the matching of the clamping seat and the bench vice.
The lugs at the two sides of the base are provided with unthreaded holes; the upper pressing plate is provided with a unthreaded hole; the threaded pull rod comprises a threaded pull rod A and a threaded pull rod B, and the lower ends of the threaded pull rod A and the threaded pull rod B are respectively inserted into unthreaded holes of lugs at two ends of the base and are connected with a nut B and a nut C at the lower end of the base; the upper ends of the threaded pull rod A and the threaded pull rod B are connected with a nut A and a nut D above the upper pressure plate after respectively penetrating through the unthreaded holes on the two sides of the upper pressure plate.
The distance between the two unthreaded holes on the base is the same as the distance between the two unthreaded holes on the upper pressing plate.
The center of the upper pressure plate is provided with a threaded hole, and the threaded hole is in threaded connection with a valve rod of the discharge valve to be disassembled.
The invention has the following remarkable effects: the novel tool for disassembling the valve core of the bypass discharge valve of the nuclear power station can compress the spring of the pilot valve in the valve core, so that the locking nut of the pilot valve is not affected by the spring force, the locking nut of the pilot valve can be easily disassembled, and the efficiency and the safety of valve disassembly are effectively improved.
Drawings
FIG. 1 is a schematic structural diagram of a novel nuclear power plant bypass vent valve spool removal tool according to the present invention;
in the figure: 1. a nut A; 2. a threaded pull rod A; 3. a nut B; 4. a clamping seat; 5. a nut C; 6. an upper pressure plate; 7. a nut D; 8. a threaded pull rod B; 9. an anti-rotation pin A; 10. an anti-rotation pin B; 11. a base.
Detailed Description
The invention is described in further detail below with reference to the figures and the embodiments.
As shown in fig. 1, a novel tool for disassembling a valve core of a bypass discharge valve of a nuclear power station comprises an upper pressure plate 6, a base 11 and a threaded pull rod, wherein the base 11 is of a disc structure with lugs at two ends, an anti-rotation pin a9 and an anti-rotation pin B10 are fixed on the upper end surface of the base 11, and the sizes of the anti-rotation pin a9 and the anti-rotation pin B10, as well as the distance between the sizes and the distances are matched with a hole at the bottom of the valve core to be disassembled; two unthreaded holes are respectively formed on lugs at two ends of the base 11; a clamping seat 4 is fixed on the lower end surface of the base 11 and is matched with a bench vice to prevent the base 11 from rotating; the lower ends of the threaded pull rod A2 and the threaded pull rod B8 are respectively inserted into unthreaded holes of lugs at two ends of the base 11 and are connected with a nut B3 and a nut C5 at the lower end of the base 11; the upper ends of the threaded pull rod A2 and the threaded pull rod B8 are respectively connected with a nut A1 and a nut D7 above the upper pressure plate 6 after passing through unthreaded holes on two sides of the upper pressure plate 6 of the flat plate structure; the distance between the two unthreaded holes on the upper pressure plate 6 is the same as that between the two lugs on the base 11, so that a threaded pull rod A2 and a threaded pull rod B8 which are arranged between the base 11 and the upper pressure plate 6 are parallel, and the center of the upper pressure plate 6 is also provided with a threaded hole which can be in threaded connection with a valve rod.
The novel tool for disassembling the valve core of the bypass discharge valve of the nuclear power station has the specific using process that: installing a base 11 at the bottom of the valve core, enabling an anti-rotation pin A9 and an anti-rotation pin B10 on the base 11 to be matched with a hole at the bottom of the valve core, clamping a clamping seat 4 by using a bench vice, and preventing the valve core from rotating along with the pilot valve when a locking nut of the pilot valve is disassembled; the central threaded hole of the upper pressure plate 6 is connected with the valve rod in a screwed mode, the threaded pull rod A2 and the threaded pull rod B8 penetrate through the base 11 and the unthreaded holes on the left side and the right side of the upper pressure plate 6, and the threaded pull rod A2 is fixed between the base 11 and the upper pressure plate 6 through the nut A1 and the nut B3; the threaded pull rod B8 is fixed between the base 11 and the upper pressure plate 6 through a nut C5 and a nut D7; and synchronously screwing in a nut A1 and a nut D7 on two sides of the upper pressure plate 6, so that the upper pressure plate drives the valve rod to move downwards to press a spring in the valve core, screwing out the locking nut after the valve core spring seat is separated from the pilot valve locking nut, synchronously screwing out the nut A1 and the nut D7 on two sides of the upper pressure plate, and unloading the pressure of the spring.
Claims (6)
1. The utility model provides a novel nuclear power station bypass discharge valve case extracting tool which characterized in that: the tool comprises an upper pressure plate (6), a base (11) and a threaded pull rod, wherein the base (11) is arranged at the bottom of a valve core and can limit the rotation of the valve core, and the upper pressure plate (6) is arranged on a discharge valve to be disassembled and is relatively fixed with a valve rod; a threaded pull rod is arranged between the base (11) and the upper pressure plate (6), and the upper pressure plate (6) can be controlled to move towards or away from the base (11) through the threaded pull rod.
2. The novel nuclear power plant bypass vent valve spool removal tool of claim 1, wherein: the base (11) is of a disc structure with lugs at two ends, an anti-rotation pin A (9) and an anti-rotation pin B (10) are fixed on the upper end face of the base (11), and the sizes of the anti-rotation pin A (9) and the anti-rotation pin B (10) and the distance between the sizes and the distance are matched with a hole at the bottom of the valve core to be disassembled.
3. The novel nuclear power plant bypass vent valve spool removal tool of claim 1, wherein: the lower end face of the base (11) is provided with a clamping seat (4), and the rotation of the base (11) is limited by matching the clamping seat (4) with a bench vice.
4. The novel nuclear power plant bypass vent valve spool removal tool of claim 1, wherein: the lugs at two sides of the base (11) are provided with unthreaded holes; the upper pressing plate (6) is provided with a unthreaded hole; the threaded pull rod comprises a threaded pull rod A (2) and a threaded pull rod B (8), the lower ends of the threaded pull rod A (2) and the threaded pull rod B (8) are respectively inserted into unthreaded holes of lugs at two ends of the base (11) and are connected with a nut B (3) and a nut C (5) at the lower end of the base (11); the upper ends of the threaded pull rod A (2) and the threaded pull rod B (8) respectively penetrate through the unthreaded holes on the two sides of the upper pressure plate (6) and then are connected with the nut A (1) and the nut D (7) above the upper pressure plate (6).
5. The novel nuclear power plant bypass vent valve spool removal tool of claim 4, wherein: the distance between the two unthreaded holes on the base (11) is the same as the distance between the two unthreaded holes on the upper pressure plate (6).
6. The novel nuclear power plant bypass vent valve spool removal tool of claim 1, wherein: the center of the upper pressure plate (6) is provided with a threaded hole, and the threaded hole is in threaded connection with a valve rod of the discharge valve to be disassembled.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201822232059.XU CN209812190U (en) | 2018-12-28 | 2018-12-28 | Novel nuclear power station bypass discharge valve case extracting tool |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201822232059.XU CN209812190U (en) | 2018-12-28 | 2018-12-28 | Novel nuclear power station bypass discharge valve case extracting tool |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN209812190U true CN209812190U (en) | 2019-12-20 |
Family
ID=68870116
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201822232059.XU Active CN209812190U (en) | 2018-12-28 | 2018-12-28 | Novel nuclear power station bypass discharge valve case extracting tool |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN209812190U (en) |
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2018
- 2018-12-28 CN CN201822232059.XU patent/CN209812190U/en active Active
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