CN217873400U - Bearing chamber of steam-driven auxiliary water-feeding pump of nuclear power station - Google Patents
Bearing chamber of steam-driven auxiliary water-feeding pump of nuclear power station Download PDFInfo
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- CN217873400U CN217873400U CN202221352045.1U CN202221352045U CN217873400U CN 217873400 U CN217873400 U CN 217873400U CN 202221352045 U CN202221352045 U CN 202221352045U CN 217873400 U CN217873400 U CN 217873400U
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The utility model provides a bearing room of steam-operated supplementary feed pump of nuclear power station, including bearing room top cap and rotational speed probe sleeve, bearing room top cap has two rows of symmetrical arrangement's waist type flange, waist type flange inclined plane is arranged, all install on the waist type flange rotational speed probe sleeve, install 1 at least rotational speed probe in the rotational speed probe sleeve, the rotational speed probe stretches into the inside of bearing room. The utility model provides a bearing room can install a plurality of speed probes in narrow space, can guarantee to provide a plurality of accurate rotational speed signals for the steam-assisted pump electrical overspeed, guarantees that internal nuclear power station steam-assisted feed water pump realizes applying two sets of electrical overspeed protection device and protects the pump overspeed.
Description
Technical Field
The utility model relates to a nuclear power station steam-driven auxiliary water-feeding pump technical field especially relates to a bearing room of nuclear power station steam-driven auxiliary water-feeding pump.
Background
The nuclear power plant auxiliary water supply system is provided with two electric auxiliary water supply pumps and two steam-driven auxiliary water supply pumps, and the two water supply pumps supply water to the secondary side of the steam generator after the main water supply is lost. The steam-driven auxiliary water feeding pump is used in the event of an accident of a nuclear power plant, and the stable operation of the steam-driven auxiliary water feeding pump is important for the safe and stable operation of the nuclear power plant.
The original design of the steam-driven auxiliary water feeding pump of the domestic nuclear power plant comprises two sets of overspeed protection devices: one set is an electric overspeed protection device, and the principle is that an electromagnetic valve of an exhaust pipeline is opened through an electric signal triggered by the rotating speed, so that the back pressure of a main steam valve is reduced to the atmospheric pressure, the main steam valve is closed, a steam-driven auxiliary water feeding pump stops running, and the rotating speed action range is 9058-9226RPM. One set is a mechanical overspeed protection device, and the principle is that an overspeed flyweight strikes the mechanical tripping device under the action of centrifugal force, the mechanical tripping device acts to open a needle valve of a steam exhaust pipeline, so that the backpressure of a main steam valve is reduced to atmospheric pressure, the main steam valve is closed, a steam-driven auxiliary water feeding pump stops running, and the action range is 9227-9645RPM.
The steam turbine and the water pump of the steam-driven auxiliary water-feeding pump share one shaft, the middle part is provided with a bearing chamber, and the side surface and the top part of the bearing chamber of the domestic steam-driven auxiliary water-feeding pump are respectively provided with a device of a rotating speed probe, and the device is provided with two rotating speed probes in total. And the side surface of the bearing chamber of the steam-driven auxiliary water feeding pump at the inlet is provided with a device for installing a rotating speed probe, and only one rotating speed probe can be installed. The rotating speed probe is selected from Hall type magnetic resistance measuring rotating speed probes.
In order to realize the replacement of the original designed mechanical overspeed device by using the second set of electric overspeed protection device for the steam-driven auxiliary water feed pump, and the second set of electric overspeed protection device uses a logic function of 'two out of three' and forms redundancy with the first set of electric overspeed protection device of the original steam-driven auxiliary pump, the original mechanical overspeed device needs to be improved and the number of rotating speed probes needs to be increased. The 'two out of three' protection logic has three protection channels, the three sets of protection carry out the calculation of logical 'AND' in pairs, and then carry out the calculation output of logical 'OR'; the second set of electric overspeed protection device of the steam-driven auxiliary water feed pump is designed and provided with three rotating speed probes, and after the signals of any two rotating speed probes reach a set rotating speed value, the logic action of overspeed protection is triggered.
The steam-driven auxiliary water feeding pump is very compact in assembly, the rotating speed probe cannot bear high temperature due to the fact that the steam turbine part is a high-temperature high-pressure part, and the water pump part belongs to a water feeding pressure boundary and cannot realize arrangement of the rotating speed probe. The steam turbine part and the water pump part of the steam-assisted pump which are operated and designed in the active nuclear power station can not be designed with a rotating speed measuring device, and the steam-assisted pump has no rotor part which leaks. The arrangement of the speed probe can only be taken into account in the intermediate bearing chamber.
As shown in fig. 1, the steam-driven auxiliary feed water pump device for the nuclear power plant is very compact in design layout and narrow in space. The bearing chamber of the steam-driven auxiliary water-feeding pump is positioned in the middle of the nuclear water pump of the steam turbine, the overlooking size is only 180mm × 110mm of a rectangular cavity, and the installation of at least more than three rotating speed probes in the narrow space is difficult.
SUMMERY OF THE UTILITY MODEL
An object of the utility model is to overcome prior art defect to provide a bearing room of nuclear power station steam-driven auxiliary feed water pump, this bearing room can install a plurality of speed probes in narrow space, can guarantee to provide a plurality of accurate rotational speed signals for steam-driven auxiliary pump electrical overspeed, guarantee that domestic nuclear power station steam-driven auxiliary feed water pump realizes applying two sets of electrical overspeed protection device and protects the pump overspeed.
In order to achieve the above object, the present invention provides the following technical solutions:
the utility model provides a bearing room of nuclear power station steam-driven auxiliary feed water pump, includes bearing room top cap and rotational speed probe sleeve, bearing room top cap has two rows of symmetrical arrangement's waist type flange, waist type flange inclined plane is arranged, all install on the waist type flange rotational speed probe sleeve, install 1 at least rotational speed probe in the rotational speed probe sleeve, the rotational speed probe stretches into the inside of bearing room.
As an implementation manner, the rotation speed probe sleeve includes a protective shell and a bracket, the bracket is detachably mounted in the protective shell, and the rotation speed probe is mounted at the bottom of the bracket.
As a practical way, the number of the brackets is 2, and the brackets are symmetrically arranged in the protective shell.
As an implementable manner, the rotational speed probe is fixedly connected to the support by means of a set screw.
As a practical way, the top of the bracket is provided with a metal hose joint and a threaded pipe joint.
As an implementable manner, the protective shell and the bracket are fixedly connected by a first screw, and the protective shell and the bearing chamber top cover are fixedly connected by a second screw.
As a practical way, a gap value S is provided between the bottom of the rotation speed probe and the bottom of the bracket, and the gap value S ranges from 0.1 mm to 0.2mm.
As an implementation mode, an opening is formed in the main shaft in the bearing chamber, a magnetic marker assembly is arranged in the opening, the magnetic marker assembly comprises a middle body, an adjusting plug screw, a fixed plug screw and a magnetic marker, the adjusting plug screw and the fixed plug screw are respectively arranged at two ends of the middle body, and the magnetic marker is installed in the adjusting plug screw.
As a practical way, the rotational speed probe sleeve is 1-2mm from the spindle.
As a practical way, the angle between the axis of the kidney flange and the axis of the bearing chamber top cover is 10 °.
Compared with the prior art, the utility model provides a bearing room of supplementary water-feeding pump of nuclear power station steam-driven has following beneficial effect:
the utility model provides a space office of steam-driven auxiliary water feeding pump design and the steam-driven auxiliary water feeding pump of domestic nuclear power unit of active service is overcome to the bearing room of nuclear power station steam-driven auxiliary water feeding pump, verifies its rotational speed probe installation and rotational speed measurement data result and satisfies steam-driven auxiliary water feeding pump rotational speed measurement requirement and standard completely through the experiment, can guarantee to provide a plurality of accurate rotational speed signals for steam-driven auxiliary pump electrical overspeed, guarantees that domestic nuclear power station steam-driven auxiliary water feeding pump realizes applying two sets of electrical overspeed protection device and protects the pump overspeed and become the reality.
In addition, the bearing chamber meets the requirement that the steam-driven auxiliary water feeding pump of the nuclear power plant increases three rotating speed signals required by a second set of electric overspeed protection device.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the drawings without creative efforts.
FIG. 1 is a cross-sectional view of a prior art nuclear power plant steam-assisted feedwater pump;
fig. 2 is a schematic structural diagram of a magnetic scale assembly according to an embodiment of the present invention;
fig. 3 is a schematic structural diagram of a bearing chamber top cover according to an embodiment of the present invention;
fig. 4 is a schematic structural diagram of a rotational speed probe sleeve according to an embodiment of the present invention;
fig. 5 is a schematic diagram illustrating an assembly of a sleeve of a rotational speed probe according to an embodiment of the present invention.
Detailed Description
Although the bearing housing of the steam-operated auxiliary feed water pump of the nuclear power plant of the present invention may be implemented in various different ways, the exemplary embodiments will be described in detail herein with reference to the accompanying drawings, it being understood that the description herein should be considered as illustrating the structure of the bearing housing of the steam-operated auxiliary feed water pump of the nuclear power plant, and the scope of the present invention is not intended to be limited to the exemplary embodiments. Accordingly, the drawings and description of the specific embodiments are to be regarded as illustrative in nature, and not as restrictive.
In the description of the present invention, it should be noted that the terms "upper", "lower", "left", "right", "inner", "outer", and the like herein indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, and are only for convenience of description and simplification of description, but do not indicate or imply that the device or component referred to must have a specific orientation, be constructed and operated in a specific orientation, and thus, should not be construed as limiting the present invention. Furthermore, the terms "first," "second," and the like are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
The following is a more detailed description of the present invention by way of specific embodiments.
For ease of understanding, a steam-driven auxiliary water feed pump in a nuclear power plant in the prior art is first briefly described, and as shown in fig. 1, the steam-driven auxiliary water feed pump in the nuclear power plant comprises a turbine impeller blade 101, a gas seal 102, a first radial bearing 103, a mechanical flyweight 104, a rotation speed measuring device 105, a second radial bearing 106, a water pump outlet 107, a balance disc assembly 108, a balance ring assembly 109, a secondary impeller 110, a primary impeller 111, a guide wheel 112, a water pump inlet 113, an inducer 114, a main shaft 115, and a common chassis 116.
As shown in fig. 2 to 5, the utility model provides a bearing chamber of a steam-driven auxiliary water feeding pump of a nuclear power station, which comprises a bearing chamber top cover 1 and a rotating speed probe sleeve 2. The bearing chamber top cover 1 is provided with two rows of waist-shaped flanges 3 which are symmetrically arranged, the waist-shaped flanges 3 are arranged on an inclined plane, and the waist-shaped flanges 3 are all provided with the rotating speed probe sleeve 2 so as to ensure that the central line of the rotating speed probe sleeve is vertical to the central line of the rotating shaft after being assembled with the waist-shaped flanges, and the measuring gap between the rotating speed probe sleeve and the rotating shaft is ensured to meet the design requirement by using the thickness adjustment of the sealing gasket. At least 1 rotating speed probe 4 is installed in the rotating speed probe sleeve 2, and the rotating speed probe 4 extends into the bearing chamber.
As shown in fig. 3, the angle between the axis of the kidney flange 3 and the axis of the bearing chamber cover 1 is α, which is preferably 10 °. I.e. the angle between the axis of the kidney flange 3 and the axis of the bearing chamber cover 1 is 10 deg.. The bottom surface of the bearing chamber top cover 1 is rectangular, the size of the long side of the bearing chamber top cover is 265mm, and the thickness of the edge of the bearing chamber top cover 1 is 25mm.
As shown in fig. 4, the rotation speed probe sleeve 2 comprises a protective shell 5 and a bracket 6, wherein the bracket 6 is detachably mounted in the protective shell 5, and the rotation speed probe 4 is mounted at the bottom of the bracket 6. The rotating speed probe 4 is fixedly connected with the bracket 6 through a set screw 7. The top of the bracket 6 is designed with pipe threads for protecting the cable of the rotating speed probe.
Preferably, as shown in fig. 4, the number of the brackets 6 is 2, and the brackets are symmetrical in the protective shell 5. Namely, two rotational speed probes 4 can be installed in each rotational speed probe sleeve 2, as shown in fig. 5, the two rotational speed probe sleeves 2 can ensure that four rotational speed probes 4 are installed.
The top of the bracket 6 is provided with a joint assembly comprising a metal hose joint 8 and a threaded pipe joint 9, as shown in fig. 4, the metal hose joint 8 being located below the threaded pipe joint 9. And the metal hose joint 8 and the threaded pipe joint 9 are connected and fixed with the bracket 6 to play a role in protecting the signal cable of the rotating speed probe 4.
The protective shell 5 and the support 6 are fixedly connected through a first screw 10, and the protective shell 5 and the bearing chamber top cover 1 are fixedly connected through a second screw 11.
As shown in fig. 4, a gap value S is provided between the bottom of the rotation speed probe 4 and the bottom of the bracket 6, and the gap value S ranges from 0.1 mm to 0.2mm.
The mechanical flyweight (overspeed tripping bolt) of a mechanical overspeed protection device on the rotor of the existing steam-driven auxiliary water-feeding pump is cancelled, and a magnetic scale component with the same size and weight is installed at the position of the flyweight. Namely, the main shaft in the bearing chamber is provided with an opening, and the magnetic marker component is arranged in the opening. As shown in fig. 2, the magnetic scale assembly includes a middle body 12, an adjusting screw plug 13, a fixing screw plug 14 and a magnetic scale 15, the adjusting screw plug 13 and the fixing screw plug 14 are respectively disposed at two ends of the middle body 12, and the magnetic scale 15 is installed in the adjusting screw plug 13. The magnetic scale 15 is of a cylindrical structure as a whole.
In order to prevent the main shaft from contacting the rotating speed probe sleeve 2 when moving, the rotating speed probe sleeve 2 is 1-2mm away from the main shaft.
The bearing chamber of the steam-driven auxiliary water-feeding pump is positioned in the middle of the steam turbine and the pump, water bush bearings are respectively arranged at two ends of the bearing chamber, and a manual brake tripping mechanism of the steam-driven auxiliary pump, a rotating speed probe sleeve and a water supply pipeline of the bearing are respectively arranged on two side surfaces of the bearing chamber. The manual brake tripping mechanism and the original overspeed flyweight are connected with the cone valve to form a safety device for mechanical overspeed protection and manual emergency brake opening. The water supply pipeline is provided with two connecting pipes which are respectively a standby water pipeline and a normal operation water pipeline.
The utility model provides a bearing room is guaranteeing under the unchangeable prerequisite of current steam-driven supplementary feed water pump overall dimension, through the bearing room top cap internal design improvement optimization to steam-driven supplementary feed water pump, combines to improve dumped machinery hypervelocity flyweight device (machinery flyweight 104 promptly) to increase rotational speed probe installation quantity. The input of the rotating speed signal required by the second set of electric overspeed protection device of the steam-assisted pump is solved, and the technical requirement of rotating speed measurement precision nuclear is completely met through experimental verification.
The bearing chamber provided by the utility model can meet the requirement of measuring the rotating speed of a plurality of rotating speed probes of the steam-driven auxiliary water feeding pump; the original appearance and structure of the steam-assisted pump are not changed, and the system is suitable for a nuclear active design unit of an operated nuclear power unit; the structure is simple, the sealing performance is good, and the probe can adapt to a standard rotating speed probe; verifying the precision meeting the requirement of the rotating speed of the steam-assisted pump by using a rotating speed experiment table, wherein the precision is consistent with the output rotating speed data of the originally designed probe; the device is well assembled with the second set of electric overspeed protection device of the steam-driven auxiliary water-feeding pump, so that the second set of electric overspeed protection device of the steam-driven auxiliary water-feeding pump of the nuclear power station can correctly execute an overspeed protection function. After the steam-driven auxiliary water feeding pump is improved and the electric overspeed protection is added, the overspeed test time of the steam-driven auxiliary water feeding pump is greatly shortened and the 100 percent success rate of the overspeed test is ensured.
The utility model provides a bearing room utilizes the unit to shut down the overhaul time according to the on-the-spot state of the supplementary water-feeding pump of nuclear power plant's steam-operated, carries out the corresponding spare part of the supplementary water-feeding pump of steam-operated and changes substitution operation, and the step is as follows:
(1) And disassembling the steam-driven auxiliary feed water pump for maintenance.
(2) The rotor member is removed from the pump chamber.
(3) And a mechanical overspeed flyweight device for taking off the rotor.
(4) And after the cleaning is qualified, installing a magnetic mark component.
(5) The rotor system is dynamically balanced and qualified.
(6) The rotor system is back-loaded into the pump chamber.
(7) The bearing chamber top cover is opened.
(8) The new bearing chamber top cover and the sealing gasket are replaced, the distance between the two waist hole flange surfaces and the rotating shaft is measured after the installation is finished (the depth caliper rule is guaranteed at the center of the waist hole during measurement), the gap between the sleeve and the rotating shaft after the installation is calculated, and the gap meets the design requirement.
(9) And (5) installing and fixing the sleeve.
(10) And a rotating speed probe is arranged on the support, and a gap between the flange surface of the support and the end part of the rotating speed probe to the inner bottom of the sleeve is measured. Depth caliper measurements should be used.
(11) And (5) fastening the bracket by bolts.
(12) The rotating speed probe signal cable is connected to the rotating speed display device.
(13) And (5) completing installation and turning inspection.
The above description is only for the specific embodiments of the present invention, but the scope of the present invention is not limited thereto, and any changes or substitutions that can be easily conceived by those skilled in the art within the technical scope of the present invention should be covered by the present invention. Therefore, the protection scope of the present invention shall be subject to the protection scope of the claims.
Claims (10)
1. The utility model provides a bearing room of nuclear power station steam-driven supplementary feed water pump, its characterized in that, includes bearing room top cap (1) and rotational speed probe sleeve (2), bearing room top cap (1) has two rows of symmetrical arrangement's waist type flange (3), waist type flange (3) inclined plane is arranged, all install on waist type flange (3) rotational speed probe sleeve (2), install 1 at least rotational speed probe (4) in rotational speed probe sleeve (2), rotational speed probe (4) stretch into the inside of bearing room.
2. The bearing chamber of the steam-driven auxiliary feed water pump of the nuclear power plant as recited in claim 1, characterized in that the rotation speed probe sleeve (2) comprises a protective shell (5) and a bracket (6), the bracket (6) is detachably mounted in the protective shell (5), and the rotation speed probe (4) is mounted at the bottom of the bracket (6).
3. Bearing housing of a nuclear power plant steam-driven auxiliary feed water pump according to claim 2, characterized in that the number of brackets (6) is 2 and are symmetrically mounted in the protective casing (5).
4. The bearing chamber of the steam-driven auxiliary feed water pump of the nuclear power plant as claimed in claim 2 or 3, characterized in that the speed probe (4) is fixedly connected with the bracket (6) by a clinch screw (7).
5. Bearing housing of a nuclear power plant steam-operated auxiliary feed water pump according to claim 2 or 3, characterized in that the top of the bracket (6) is provided with a metal hose joint (8) and a threaded pipe joint (9).
6. The bearing housing of the steam-operated auxiliary feed water pump of the nuclear power plant as claimed in claim 2 or 3, characterized in that the protective shell (5) and the bracket (6) are fixedly connected by means of first screws (10), and the protective shell (5) and the bearing housing top cover (1) are fixedly connected by means of second screws (11).
7. The bearing chamber of the steam-driven auxiliary water feeding pump of the nuclear power plant as recited in claim 2 or 3, characterized in that a clearance value S is provided between the bottom of the rotating speed probe (4) and the bottom of the bracket (6), and the clearance value S is in a range of 0.1-0.2 mm.
8. The bearing chamber of the steam-driven auxiliary water feeding pump of the nuclear power plant as recited in claim 1, wherein a main shaft in the bearing chamber is provided with an opening, a magnetic marker assembly is arranged in the opening, the magnetic marker assembly comprises a middle body (12), an adjusting screw plug (13), a fixed screw plug (14) and a magnetic marker (15), the adjusting screw plug (13) and the fixed screw plug (14) are respectively arranged at two ends of the middle body (12), and the magnetic marker (15) is arranged in the adjusting screw plug (13).
9. The bearing housing of a nuclear power plant steam-driven auxiliary feed water pump according to claim 8, characterized in that the rotational speed probe sleeve (2) is 1-2mm from the main shaft.
10. The bearing chamber of the steam-driven auxiliary feed water pump of the nuclear power plant as claimed in claim 1, characterized in that the angle between the axis of the kidney flange (3) and the axis of the bearing chamber top cover (1) is 10 °.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202221352045.1U CN217873400U (en) | 2022-05-31 | 2022-05-31 | Bearing chamber of steam-driven auxiliary water-feeding pump of nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202221352045.1U CN217873400U (en) | 2022-05-31 | 2022-05-31 | Bearing chamber of steam-driven auxiliary water-feeding pump of nuclear power station |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN217873400U true CN217873400U (en) | 2022-11-22 |
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ID=84093657
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202221352045.1U Active CN217873400U (en) | 2022-05-31 | 2022-05-31 | Bearing chamber of steam-driven auxiliary water-feeding pump of nuclear power station |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN217873400U (en) |
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2022
- 2022-05-31 CN CN202221352045.1U patent/CN217873400U/en active Active
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