CN212840070U - Anti-seismic vibration isolation support of nuclear power station - Google Patents
Anti-seismic vibration isolation support of nuclear power station Download PDFInfo
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- CN212840070U CN212840070U CN202021274777.4U CN202021274777U CN212840070U CN 212840070 U CN212840070 U CN 212840070U CN 202021274777 U CN202021274777 U CN 202021274777U CN 212840070 U CN212840070 U CN 212840070U
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- guide rod
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Abstract
The utility model discloses an anti-seismic vibration isolation support of a nuclear power station, which comprises a pre-compression system, a vibration isolation system and a hydraulic system; the precompression system comprises a guide rod (3) fixed on a guide rod support (2) by a threaded positioning pin (1); the vibration isolation system comprises a vibration isolation system supporting rod (4) which penetrates out of a vibration isolation system shell (5) and supports the guide rod (3), and metal rubber (6) is filled in the vibration isolation system shell (5); and a cylinder body (8) of the hydraulic system is fixedly connected with the guide rod (3). Under the normal operation working condition of pipelines and equipment of a nuclear power station, the vibration isolation support can bear the self weight, the thermal expansion and the mechanical load and can also isolate the propagation of vibration energy; under the accident condition of pipelines and equipment, the vibration isolation support is automatically in a rigid state, can bear large load generated by earthquake, and protects the safety and integrity of the pipelines and the equipment.
Description
Technical Field
The utility model belongs to the technical field of antidetonation, especially, relate to antidetonation type vibration isolation support that nuclear power station was used.
Background
A plurality of high-energy pipelines are designed in the nuclear power station, the medium is high-temperature high-pressure steam with extremely high flow speed, the pipeline is improperly arranged, vibration and noise of the pipelines are easily caused, a severe working environment is formed, and physical and psychological health of workers in the nuclear power station is influenced.
In the civil industry, vibration isolation mounts are commonly used to isolate vibration in pipes and equipment capable of generating vibration, preventing the transmission of vibration energy from the pipes and equipment to walls or floors, thereby isolating the propagation of vibration energy. Vibration isolation supports in the civil industry often utilize the damping characteristics of materials such as rubber, springs and the like to achieve the vibration isolation effect. In the nuclear power plant at the present stage, the same type of vibration problem is treated, the common method is to additionally increase the rigidity constraint of the pipeline and the equipment and inhibit the vibration of the pipeline and the equipment, and the treatment method can reduce the vibration and prevent the pipeline and the equipment from being damaged due to the vibration. The method is to transmit the vibration energy of the pipeline and the equipment to the wall and the floor, and the transmission of the vibration energy cannot be eliminated or isolated, but on the contrary, because the rigid constraint is added, more vibration energy is transmitted through the wall and the floor, and vibration and noise are formed in other areas or in the room pipe.
The vibration isolation support is less adopted in the nuclear power station, on one hand, the existing vibration isolation material cannot be used in the nuclear power station for a long time due to the high-temperature, high-humidity and radiation environment of the nuclear power station, on the other hand, the safety requirement of the nuclear power station is high, the working condition is complex, the pipelines and equipment usually require vibration resistance, and the conventional vibration isolation support cannot be sufficient.
Therefore, an anti-seismic vibration isolation support needs to be designed, and the vibration isolation material can adapt to the severe environment of the nuclear power station for a long time and can meet the complex working condition requirement of the nuclear power station. The anti-seismic vibration isolation support can bear the dead weight, thermal expansion, mechanical load and the like of pipelines and equipment under the normal operation working condition, and can isolate the propagation of vibration energy and prevent the vibration from being propagated to walls and the ground; in addition, the vibration isolation support can bear large loads such as earthquake, pipeline breakage and the like of the pipeline and the equipment under accident conditions, and the safety and integrity of the pipeline and the equipment are guaranteed.
SUMMERY OF THE UTILITY MODEL
The utility model provides an anti-seismic vibration isolation support for a nuclear power station, which can bear the dead weight, thermal expansion and mechanical load and can also isolate the propagation of vibration energy under the normal operation working condition of pipelines and equipment of the nuclear power station; under the accident condition of pipelines and equipment, the vibration isolation support is automatically in a rigid state, can bear large load generated by earthquake, and protects the safety and integrity of the pipelines and the equipment.
An anti-seismic vibration isolation support of a nuclear power station comprises a pre-compression system, a vibration isolation system and a hydraulic system;
the precompression system comprises a guide rod (3) fixed on a guide rod support (2) by a threaded positioning pin (1);
the vibration isolation system comprises a vibration isolation system supporting rod (4) which penetrates out of a vibration isolation system shell (5) and supports the guide rod (3), and metal rubber (6) is filled in the vibration isolation system shell (5);
the hydraulic system comprises a hydraulic system shell (12) at the bottom and a cylinder body (8) sleeved above the hydraulic system shell (12), a piston (9) is arranged in the cylinder body (8), and the piston (9) penetrates through the cylinder body (8) and is fixed on the inner side of the bottom of the hydraulic system shell (12); a silicon oil (10) is arranged between the piston (9) and the cylinder body (8), and the silicon oil (10) can flow back and forth in the cylinder body (8) separated by the piston (9) through a small hole throttle valve (11) on the piston (9);
the cylinder body (8) is fixedly connected with the guide rod (3).
Preferably, the orifice throttle valve (11) is characterized in that a spring (11-2) is arranged in the middle of an orifice throttle valve base (11-1), an orifice throttle valve core (11-3) is arranged below the spring (11-2), and the orifice throttle valve core (11-3) transmits the flow speed pressure of the silicone oil (10) to the spring (11-2) to adjust the flow speed of the silicone oil (10).
The utility model provides an anti-seismic vibration isolation support that nuclear power station was used has following key feature:
the anti-seismic vibration isolation support can be in an elastic state under the normal operation working condition of the nuclear power station, and can be in a rigid state under the accident working condition.
The vibration isolation support adjusts the initial load of the vibration isolation support through a precompression system before installation, and is used for offsetting the dead weight load of pipelines and equipment.
The vibration isolation support is made of novel vibration isolation materials such as metal rubber and the like, and a vibration isolation system of the vibration isolation support is formed. Under the normal working condition of the pipeline and the equipment, the vibration isolation system utilizes the rigidity characteristic of the metal rubber to bear the thermal expansion, the mechanical load and the like of the pipeline and the equipment of the nuclear power station, and utilizes the large damping characteristic of the metal rubber to isolate the vibration of the pipeline and the equipment, so that the vibration of the pipeline and the equipment is prevented from being transmitted to a wall body or a floor slab.
The vibration isolation support adopts components such as silicone oil, valves and pistons to form a hydraulic system of the vibration isolation support, when pipelines and equipment of the nuclear power station bear dead weight, thermal expansion and mechanical load under normal working conditions, the displacement speed is slow, the silicone oil can slowly flow through small holes in the pistons, the valves on the small holes cannot be closed, and the hydraulic system does not work. Under the earthquake working condition, large-amplitude displacement is generated, silicon oil flows through the small hole in the piston rapidly, the valve in the small hole is closed automatically, and the pressing system forms a rigid support to prevent the pipeline and equipment from being damaged due to overlarge earthquake load.
Drawings
FIG. 1 is a simplified diagram of a nuclear power plant seismic isolation mount;
FIG. 2 is a schematic diagram of a precompression system for a nuclear power plant;
FIG. 3 is a schematic view of a vibration isolation system for a nuclear power plant;
FIG. 4 is a schematic diagram of a nuclear power plant hydraulic system;
FIG. 5 is a schematic view of a small bore throttle valve for a nuclear power plant;
wherein: 1-a threaded locating pin; 2-guide rod support; 3, a guide rod; 4-a vibration isolation system support bar; 5, a vibration isolation system shell; 6-metal rubber; 7, a support; 8, a cylinder body; 9-a piston; 10-silicone oil; 11-orifice throttle valve; 12-hydraulic system housing; 11-1-orifice throttle valve base; 11-2-spring; 11-3-orifice throttle valve core.
Detailed Description
In order to make the above objects, features and advantages of the present invention more comprehensible, the present invention is described in detail with reference to the accompanying drawings and the detailed description.
The utility model discloses a antidetonation type vibration isolation support of nuclear power station, as shown in figure 1 mainly include following component part 1, screw thread locating pin, 2, guide arm support, 3, guide arm, 4, vibration isolation system bracing piece, 5, vibration isolation system shell, 6, metal rubber, 7, support, 8, cylinder body, 9, piston, 10, silicon oil, 11, aperture choke valve, 12, hydraulic system shell, 11-1, aperture choke valve base, 11-2, spring, 11-3, aperture choke valve case. The vibration isolation bracket consists of three parts, as shown in figure 2, parts 1-3 form a precompression system of the vibration isolation bracket; as shown in fig. 3, the parts 4-6 constitute a vibration isolation system of the vibration isolation mount; as shown in fig. 4, the components 7 to 12 constitute a hydraulic system of the vibration isolation mount.
Firstly, self-weight load of pipelines and equipment is calculated by software, and assuming that the self-weight load is 10kN, a load is applied to the vibration isolation support, the metal rubber 6 is compressed by the support rod 4 of the vibration isolation system, the applied load is 10kN, the component 2 is gradually led into the component 3, and the compression amount is clamped by the component 1. The vibration isolation support is arranged on the pipeline and the equipment, the threaded positioning pin 1 is loosened, the compression load can offset the dead weight load of the pipeline and the equipment, and the vibration isolation support bears the dead weight load of the pipeline and the equipment at the moment.
And then the system enters a normal operation working condition, the pipeline and the equipment generate thermal expansion and mechanical load, at the moment, the metal rubber 6 can continue to compress or release the compression amount, the bearing of the metal rubber 6 reaches new balance, and the vibration isolation support bears the load under the normal working condition.
As shown in FIG. 5, since the displacement speed of the pipeline and the equipment is very slow, when the piston 9 in the hydraulic system moves up and down, the speed of the silicon oil 10 flowing through the orifice throttle valve 11 is very slow, so that the orifice throttle valve core 11-3 does not have enough pressure to counteract the elastic force of the spring 11-2, the silicon oil 10 can smoothly flow through the orifice throttle valve 11, and the hydraulic system has no rigidity and has no supporting effect on the pipeline and the equipment.
Under the condition, when pipelines and equipment vibrate, vibration waves are transmitted to the metal rubber 6 sequentially through the support 7, the cylinder body 8 and the vibration isolation system supporting rod 4, and the metal rubber 6 can isolate vibration well according to the material characteristics, so that the vibration waves can not be transmitted to the base of the vibration isolation support, and the vibration isolation function is realized.
When the pipeline and the equipment are displaced greatly when an earthquake occurs, the speed of the silicon oil 10 flowing through the small-hole throttle valve 11 becomes very high, the generated pressure counteracts the elastic force of the spring 11-2, so that the small-hole throttle valve core 11-3 is led into the small-hole throttle valve base 11-1, the small-hole throttle valve is closed, the silicon oil 10 on the two sides of the piston 9 cannot flow, the hydraulic system becomes a rigid support, the pipeline and the equipment can be completely fixed, and the reverse pipeline and the equipment are damaged under the earthquake load.
It will be apparent to those skilled in the art that various changes and modifications may be made without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims and their equivalents, the present invention is also intended to encompass such modifications and variations. The above-described embodiments or implementations are merely illustrative of the present invention, which may be embodied in other specific forms or arrangements without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be determined by the appended claims, and any changes that are equivalent to the intent and scope of the claims are intended to be embraced therein.
Claims (2)
1. An anti-seismic vibration isolation support of a nuclear power station is characterized by comprising a pre-compression system, a vibration isolation system and a hydraulic system;
the precompression system comprises a guide rod (3) fixed on a guide rod support (2) by a threaded positioning pin (1);
the vibration isolation system comprises a vibration isolation system supporting rod (4) which penetrates out of a vibration isolation system shell (5) and supports the guide rod (3), and metal rubber (6) is filled in the vibration isolation system shell (5);
the hydraulic system comprises a hydraulic system shell (12) at the bottom and a cylinder body (8) sleeved above the hydraulic system shell (12), a piston (9) is arranged in the cylinder body (8), and the piston (9) penetrates through the cylinder body (8) and is fixed on the inner side of the bottom of the hydraulic system shell (12); a silicon oil (10) is arranged between the piston (9) and the cylinder body (8), and the silicon oil (10) can flow back and forth in the cylinder body (8) separated by the piston (9) through a small hole throttle valve (11) on the piston (9);
the cylinder body (8) is fixedly connected with the guide rod (3).
2. The anti-seismic vibration isolation support of the nuclear power station as claimed in claim 1, wherein the orifice throttle valve (11) is formed by arranging a spring (11-2) in the middle of an orifice throttle valve base (11-1), an orifice throttle valve core (11-3) is arranged below the spring (11-2), and the orifice throttle valve core (11-3) transmits the flow velocity pressure of the silicone oil (10) to the spring (11-2) to adjust the flow velocity of the silicone oil (10).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202021274777.4U CN212840070U (en) | 2020-07-02 | 2020-07-02 | Anti-seismic vibration isolation support of nuclear power station |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202021274777.4U CN212840070U (en) | 2020-07-02 | 2020-07-02 | Anti-seismic vibration isolation support of nuclear power station |
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| Publication Number | Publication Date |
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| CN212840070U true CN212840070U (en) | 2021-03-30 |
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| CN202021274777.4U Active CN212840070U (en) | 2020-07-02 | 2020-07-02 | Anti-seismic vibration isolation support of nuclear power station |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113944359A (en) * | 2021-11-08 | 2022-01-18 | 上海核工程研究设计院有限公司 | Novel interlayer shock insulation nuclear power station structure with shock resistance function |
| CN113969619A (en) * | 2021-11-08 | 2022-01-25 | 上海核工程研究设计院有限公司 | Potential energy-based novel nuclear power station with structure self-rotating shock-resistant interlayer shock insulation function |
-
2020
- 2020-07-02 CN CN202021274777.4U patent/CN212840070U/en active Active
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113944359A (en) * | 2021-11-08 | 2022-01-18 | 上海核工程研究设计院有限公司 | Novel interlayer shock insulation nuclear power station structure with shock resistance function |
| CN113969619A (en) * | 2021-11-08 | 2022-01-25 | 上海核工程研究设计院有限公司 | Potential energy-based novel nuclear power station with structure self-rotating shock-resistant interlayer shock insulation function |
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| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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| CP01 | Change in the name or title of a patent holder |