Leaked steam collecting device for shaft seal of high-pressure module of nuclear power high-temperature reactor steam turbine
By designing a shaft seal steam leakage collection device including an annular baffle, a steam exhaust pipe group, a baffle seal and a locking connection, the problem of leaking steam in the high-pressure module of a nuclear power high-temperature reactor steam turbine is solved, and the safe collection and emission of steam is achieved to meet the needs of safe operation of the unit.
Patent Information
- Application Number
- CN202411903157.5
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2024-12-23
- Publication Date
- 2025-03-25
AI Technical Summary
In the high-pressure module of the nuclear power high-temperature reactor steam turbine, there is an unscheduled shaft seal steam leakage phenomenon, resulting in steam leakage. Due to the modular design and space limitations, it is impossible to replace the steam seal teeth without removing the cylinder, and it is difficult for the existing technology to effectively collect and deal with leaked steam.
A shaft sealing steam leakage collection device including an annular baffle, a steam exhaust pipe group, a baffle seal and a locking connection is designed. The annular baffle is installed on the high-pressure outer cylinder shell and a high-pressure rotor through the annular baffle, and combined with the steam exhaust pipe group and a baffle seal, the collection and discharge of leaked steam is achieved.
Effectively collect and discharge leaked steam at both ends of the power regulating module of the turbine, meets the requirements of safe operation of the unit, and is easy to disassemble and is easy to use during the maintenance of the high-voltage module.
Smart Images
Figure CN119686814A_ABST
Abstract
Description
Technical Field
[0001] The invention relates to a steam turbine shaft seal leakage collection device, in particular to a steam turbine shaft seal leakage collection device for a high-pressure module of a nuclear power high-temperature reactor. The invention is used in the field of steam turbines. Background Art
[0002] With the design and development of high-temperature reactors in the nuclear power market, new nuclear power steam turbine units have adopted modular design, pre-installed in the factory, and the high-pressure module is shipped as a whole. After the unit has been in continuous operation and reaches the refueling cycle, it is overhauled synchronously with the nuclear island. In view of the fact that there are peak-shaving, industrial steam extraction and other working conditions in the current domestic unit operation cycle, and the pursuit of a more efficient maintenance cycle. There is a phenomenon of shaft seal steam leakage outside the maintenance plan. Due to the modular design, the on-site space is small and the structure is compact, it is impossible to handle the on-site shaft seal steam leakage by replacing the steam seal teeth without opening the cylinder. The only compromise solution is to temporarily use a high-power fan to blow away the leaked steam. It is necessary to provide a shaft seal leakage steam collection device so that the end steam seals at both ends of the power regulation of the steam turbine high-pressure module can collect the leaked steam when leakage occurs, so as to meet the requirements of safe operation of the unit. There is no equipment that meets this requirement in the existing technology. Summary of the invention
[0003] The purpose of the present invention is to provide a nuclear power high-temperature reactor steam turbine high-pressure module shaft seal steam leakage collection device so that when leakage occurs at the end steam seals at both ends of the power regulation of the steam turbine high-pressure module, the leaked steam can be collected to meet the requirements of safe operation of the unit.
[0004] The technical solution adopted by the present invention to solve the above problems is:
[0005] A steam leakage collection device for a shaft seal of a high-pressure module of a nuclear power high-temperature reactor steam turbine, comprising an annular baffle, a steam exhaust pipe group, a baffle seal and a plurality of locking connectors;
[0006] The annular baffle is installed on the high-pressure outer cylinder housing through a plurality of locking connectors, and the annular baffle is sleeved on the high-pressure rotor. A baffle seal is provided between the high-pressure rotor and the annular baffle. The steam exhaust pipe group is installed on the annular baffle, and the cavity between the annular baffle and the high-pressure outer cylinder housing is connected to the outlet end of the steam exhaust pipe group.
[0007] Furthermore, the locking connection piece is a connection bolt, and the annular baffle is detachably connected and installed on the high-pressure outer cylinder housing through the connection bolt.
[0008] Furthermore, the annular baffle includes two semicircular annular plates, the two semicircular annular plates are assembled into a combined annular plate, and each semicircular annular plate is fixedly mounted on the high-pressure outer cylinder housing by a plurality of connecting bolts.
[0009] Furthermore, the steam exhaust pipe group includes at least two steam exhaust pipes, each of which is installed on the annular baffle 1 and communicates with the cavity between the annular baffle and the high-pressure outer cylinder shell.
[0010] Furthermore, the baffle seal is a steam seal tooth seal.
[0011] Beneficial effects of the present invention:
[0012] 1. The present invention utilizes the steam leakage pipeline of the steam turbine unit itself, connects the collected steam through pipelines, and discharges it from the branch pipe or main pipe of the shaft seal steam leakage pipeline.
[0013] 2. The present invention adopts connecting bolts for easy disassembly. Considering that the shaft seal steam leakage collection device is installed without disassembling the unit, the shaft seal steam leakage collection device can be removed when the high-pressure module is overhauled.
[0014] 3. In the present invention, a baffle seal 4 is provided between the high-pressure rotor 5 and the annular baffle 1, and a steam seal plate is used for sealing.
[0015] 4. This application collects the leaked steam when the end steam seals at both ends of the steam turbine high-pressure module are leaking, meeting the requirements for safe operation of the unit. The steam leaked from the shaft seals at both ends of the steam turbine high-pressure module is collected by a non-external power supply drive. The structure of this application can collect the leaked steam according to the actual situation on site, and it is easy to disassemble. BRIEF DESCRIPTION OF THE DRAWINGS
[0016] Figure 1 It is a main schematic diagram of the overall structure of this application.
[0017] Figure 2 yes Figure 1 Center A view. DETAILED DESCRIPTION
[0018] Specific implementation method 1: Combination Figure 1-Figure 2 The present embodiment is described as follows: a nuclear power high temperature reactor steam turbine high pressure module shaft seal steam leakage collection device, which comprises an annular baffle 1, a steam exhaust pipe group 3, a baffle seal 4 and a plurality of locking connectors 2;
[0019] The annular baffle 1 is installed on the high-pressure outer cylinder housing through a plurality of locking connectors 2, and the annular baffle 1 is sleeved on the high-pressure rotor 5, a baffle seal 4 is provided between the high-pressure rotor 5 and the annular baffle 1, a steam exhaust pipe group 3 is installed on the annular baffle 1, and a cavity between the annular baffle 1 and the high-pressure outer cylinder housing is connected to the outlet end of the steam exhaust pipe group 3.
[0020] Specific implementation method 2: Combination Figure 1The present embodiment is described as a nuclear power high temperature reactor steam turbine high pressure module shaft seal steam leakage collection device, wherein the locking connector 2 is a connecting bolt, and the annular baffle 1 is disassembled and connected and installed on the high pressure outer cylinder housing by the connecting bolt.
[0021] The connecting bolts facilitate the disassembly of the annular baffle 1, so it is convenient to use when the nuclear power high temperature reactor steam turbine high pressure module shaft seal leakage steam collection device is needed. The connecting bolts are installed in the threaded holes of the high pressure outer cylinder shell during transportation, and no additional threaded holes need to be processed. Other methods are the same as the specific implementation method one.
[0022] Specific implementation method three: Combination Figure 1-Figure 2 The present embodiment describes a nuclear power high temperature reactor steam turbine high pressure module shaft seal steam leakage collection device, wherein the annular baffle 1 comprises two semicircular ring plates, the two semicircular ring plates are assembled into a combined annular plate, and each semicircular ring plate is fixedly mounted on the high pressure outer cylinder housing by a plurality of connecting bolts.
[0023] The two semicircular ring plates can be constructed without disassembling the shaft system, which is convenient to operate and saves installation time. A gap is left at the relative arrangement of the center dividing surfaces of the two semicircular ring plates, through which the outside air enters the cavity between the annular baffle 1 and the high-pressure outer cylinder housing. Other methods are the same as the specific implementation method one.
[0024] Specific implementation method four: Combination Figure 1-Figure 2 This embodiment is described. This embodiment describes a steam leakage collection device for a high-pressure module shaft seal of a nuclear power high-temperature reactor steam turbine. The steam exhaust pipe group 3 includes at least two steam exhaust pipes. Each steam exhaust pipe is installed on the annular baffle 1 and communicates with the cavity between the annular baffle 1 and the high-pressure outer cylinder shell. The steam leaking from the high-pressure cylinder is discharged through the steam exhaust pipe. Other methods are the same as those in the first specific embodiment.
[0025] Specific implementation method five: combination Figure 1-Figure 2 This embodiment is described. In this embodiment, a steam leakage collection device for a high-pressure module of a nuclear power high-temperature reactor steam turbine is described. The baffle seal 4 is a steam seal tooth seal. The steam seal tooth seal is provided to allow outside air to enter the chamber. Other methods are the same as those in the first embodiment.
[0026] The above-mentioned specific implementation can be partially adjusted in different ways by those skilled in the art without departing from the principle and purpose of the present invention. The protection scope of the present invention shall be based on the claims and shall not be limited by the above-mentioned specific implementation. Each implementation scheme within its scope shall be subject to the constraints of the present invention.
Claims
1. A steam leakage collection device for the shaft seal of a high-pressure module of a nuclear power high-temperature reactor steam turbine, characterized in that: It comprises an annular baffle (1), a steam exhaust pipe group (3), a baffle seal (4) and a plurality of locking connectors (2); The annular baffle (1) is mounted on the high-pressure outer cylinder housing via a plurality of locking connectors (2), and the annular baffle (1) is sleeved on the high-pressure rotor (5), a baffle seal (4) is provided between the high-pressure rotor (5) and the annular baffle (1), a steam exhaust pipe group (3) is mounted on the annular baffle (1), and a cavity between the annular baffle (1) and the high-pressure outer cylinder housing is in communication with an outlet end of the steam exhaust pipe group (3).
2. According to claim 1, a nuclear power high temperature reactor steam turbine high pressure module shaft seal steam leakage collection device is characterized in that: The locking connection piece (2) is a connection bolt, and the annular baffle (1) is disassembled and connected to the high-pressure outer cylinder housing through the connection bolt.
3. According to claim 1, a nuclear power high temperature reactor steam turbine high pressure module shaft seal steam leakage collection device is characterized in that: The annular baffle (1) comprises two semi-circular annular plates, the two semi-circular annular plates are assembled into a combined annular plate, and each semi-circular annular plate is fixedly mounted on the high-pressure outer cylinder housing by a plurality of connecting bolts.
4. According to claim 1, a nuclear power high temperature reactor steam turbine high pressure module shaft seal steam leakage collection device is characterized in that: The steam exhaust pipe group (3) comprises at least two steam exhaust pipes, each of which is mounted on the annular baffle (1) and communicates with the cavity between the annular baffle (1) and the high-pressure outer cylinder shell.
5. According to claim 1, a nuclear power high temperature reactor steam turbine high pressure module shaft seal steam leakage collection device is characterized in that: The baffle seal (4) is a steam seal tooth seal.