Automatic vibration reduction support for suspension type pump of nuclear power station, suspension type pump and vibration reduction method

Abstract

The invention provides a nuclear power plant suspension type pump automatic vibration reduction support, a suspension type pump and a vibration reduction method.The vibration reduction support comprises a data acquisition control mechanism and at least one vibration adjusting assembly, the data acquisition control mechanism comprises a vibration sensor and data acquisition processing equipment, and the vibration sensor is installed at the bottom end of the suspension type pump; the data acquisition and processing equipment is used for receiving vibration signals of the vibration sensor; each vibration adjusting assembly comprises an oil storage tank and an oil cylinder, a control valve is arranged between the oil storage tank and the oil cylinder, a piston is arranged in the oil cylinder, and one end of the piston abuts against the suspension type pump. The data acquisition control mechanism further comprises a valve driving mechanism connected with the control valve, and the valve driving mechanism is used for controlling opening and closing of the control valve, so that the piston is adjusted to be in a free motion state or the suspension type pump is supported and decoupled. The automatic vibration reduction support can change the inherent frequency of the suspension type pump, so that the suspension type pump is decoupled from a vibration excitation load, the suspension type pump is prevented from vibrating excessively, and the safety of the nuclear power station is improved.

Description

Technical Field

[0001] The invention relates to the technical field of safety protection of a coolant pump in a nuclear power plant, and in particular to an automatic vibration reduction support for a suspended pump in a nuclear power plant, a suspended pump and a vibration reduction method. Background Art

[0002] The reactor coolant pump of a nuclear power plant is the most important core component of the primary circuit pressure boundary of the nuclear power plant. It is located at the bottom of the steam generator in the nuclear island building and is used to drive the circulation of coolant inside the reactor. The quality of its operating status directly affects the safe and stable operation of the nuclear power plant.

[0003] The third-generation passive nuclear power plant has two loops, each loop has two steam generators, and two main pumps are installed under each steam generator. Their inlets are connected to the steam generators, and their outlets are connected to the cold section. It is a vertical cantilever beam structure.

[0004] When the suspended pump is in operation, the high-temperature, high-pressure fluid excitation load at its outlet acts on the root area of ​​the pump, causing the pump to produce low-frequency vibrations with the horizontal vibration amplitude at the bottom free end being the largest. When the fluid excitation frequency is coupled with the natural frequency of the suspended pump, a resonance effect will occur. There is a risk of resonance coupling amplification, which will affect the normal operation of nuclear power. Effective measures need to be taken to reduce the vibration of the suspended pump.

[0005] At present, there are two main methods to reduce the vibration of suspended pumps: one is to change the external excitation load of the pump, which can be achieved by adjusting the pump speed, etc., but this method is only effective for some operating conditions of nuclear power plants; the other is to change the natural frequency of the pump, but due to the limitations of the already arranged and solidified nuclear island building and installed and solidified pump components, as well as the thermal expansion displacement of the main coolant circuit due to heating and cooling, it is currently difficult to change the natural frequency of the pump through conventional external intervention vibration reduction measures.

[0006] Based on this, the inventor of the present application proposes an automatic vibration reduction support for a nuclear power plant suspended pump, a suspended pump and a vibration reduction method, in order to solve the above-mentioned technical problems. Summary of the invention

[0007] The technical problem to be solved by the present invention is to overcome the defect of high difficulty in changing the natural frequency of a suspended pump in the prior art, and to provide an automatic vibration reduction support for a nuclear power plant suspended pump, a suspended pump and a vibration reduction method.

[0008] The present invention solves the above technical problems through the following technical solutions:

[0009] The present invention provides an automatic vibration reduction support for a nuclear power plant suspended pump, which is characterized by comprising:

[0010] A data acquisition control mechanism, comprising a vibration sensor and a data acquisition processing device, wherein the vibration sensor is installed at the bottom of the suspended pump, and the data acquisition processing device is used to receive a vibration signal from the vibration sensor;

[0011] At least one vibration regulating assembly, each of which comprises an oil storage tank and an oil cylinder, a control valve is provided between the oil storage tank and the oil cylinder, a piston is provided in the oil cylinder, one end of the piston is in contact with the suspended pump; wherein,

[0012] The data acquisition control mechanism also includes a valve driving mechanism connected to the control valve, and the valve driving mechanism is used to control the opening and closing of the control valve, thereby adjusting the piston to a free motion state or decoupling the suspension pump support.

[0013] According to one embodiment of the present invention, a supporting mechanism is further included, one end of the vibration adjustment assembly is slidably connected to the supporting mechanism, and the sliding direction is vertically consistent with the suspended pump.

[0014] According to an embodiment of the present invention, a support base is provided at one end of the oil storage tank, and the support base is slidably matched with the support mechanism through a slide rail and a slideway.

[0015] According to one embodiment of the present invention, the number of the vibration adjustment assemblies is at least two, and the two vibration adjustment assemblies are arranged at intervals along the vertical direction of the suspended pump.

[0016] According to one embodiment of the present invention, each of the vibration adjustment components is slidably matched with the support mechanism.

[0017] According to one embodiment of the present invention, the control valve of each vibration adjustment assembly is connected to the valve drive mechanism and is controlled independently of each other.

[0018] According to an embodiment of the present invention, a support member is provided at one end of the piston away from the oil storage tank, and one end of the support member away from the piston abuts against the suspended pump.

[0019] The present invention also provides a nuclear power plant suspension pump, which is characterized by comprising:

[0020] Suspended pump, suspended pump support and automatic vibration reduction support for nuclear power plant suspended pump as described above;

[0021] The top end of the suspension pump is connected to the suspension pump support seat, and one end of the piston of the automatic vibration reduction support of the nuclear power plant suspension pump is abutted against the bottom end of the suspension pump.

[0022] The present invention also provides an automatic vibration reduction method for a nuclear power plant suspended pump, characterized in that the automatic vibration reduction support for the nuclear power plant suspended pump as described above is adopted, and the vibration reduction method comprises:

[0023] Step 1, receiving a vibration signal from a vibration sensor;

[0024] Step 2: When the vibration signal is coupled and amplified with the natural frequency of the suspension pump and exceeds a threshold, the control valve is closed through the valve drive mechanism so that the piston effectively supports the suspension pump for decoupling.

[0025] According to one embodiment of the present invention, a plurality of groups of vibration adjustment components are arranged vertically along the suspended pump, and the natural frequency of the suspended pump can be changed within a certain range by changing the number of the vibration adjustment components.

[0026] The positive and progressive effects of the present invention are:

[0027] The automatic vibration reduction support for the nuclear power plant suspended pump of the present invention is arranged on the outside of the suspended pump through at least one vibration adjustment component, which can release the thermal expansion displacement caused by the heating and cooling of the main cooling circuit without affecting the original stress condition of the main cooling system, the normal operation of the suspended pump, and the layout space of the solidified nuclear power plant.

[0028] The real-time monitoring data of the vibration sensor is collected by the data acquisition and processing equipment to obtain the internal excitation intensity and spectrum of the main cooling circuit. The suspended pump is supported by one end of the piston of the vibration adjustment component to change the natural frequency of the suspended pump. Moreover, the natural frequency of the suspended pump can be dynamically adjusted according to the fluid excitation at different speeds, so that the excitation frequency of the main coolant circuit is decoupled from the natural frequency of the suspended pump, and stable operation of the suspended pump at various speeds is achieved, eliminating excessive stress or fatigue caused by vibration in the main cooling circuit, thereby improving the safety level of the power station. BRIEF DESCRIPTION OF THE DRAWINGS

[0029] The above and other features, properties and advantages of the present invention will become more apparent through the following description in conjunction with the accompanying drawings and embodiments, in which:

[0030] Figure 1 It is a structural schematic diagram of an embodiment of an automatic vibration reduction support for a nuclear power plant suspension pump of the present invention;

[0031] Figure 2 It is a structural schematic diagram of another embodiment of the automatic vibration reduction support of a nuclear power plant suspension pump of the present invention;

[0032] Figure 3 It is a structural schematic diagram of another embodiment of the automatic vibration reduction support of a nuclear power plant suspended pump of the present invention;

[0033] Figure 4 It is a schematic diagram of the vibration amplitude of the suspended pump of the present invention before and after the support is installed;

[0034] Figure 5 The present invention is a flow chart of the automatic vibration reduction method for a suspended pump in a nuclear power plant.

[0035] 1. Data acquisition control mechanism; 11. Vibration sensor; 12. Data acquisition and processing equipment; 13. Valve drive mechanism;

[0036] 2. Vibration adjustment assembly; 21. Oil storage tank; 211. Support base; 22. Oil cylinder; 23. Control valve; 24. Piston; 25. Support member;

[0037] 3. Support mechanism;

[0038] 4. Suspended pump;

[0039] 5. Suspended pump support. DETAILED DESCRIPTION

[0040] The present invention is further described below in conjunction with specific embodiments and drawings. More details are elaborated in the following description to facilitate a full understanding of the present invention. However, the present invention can obviously be implemented in a variety of other ways different from the description herein. Those skilled in the art can make similar generalizations and deductions based on actual application situations without violating the connotation of the present invention. Therefore, the protection scope of the present invention should not be limited by the content of this specific embodiment.

[0041] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by technicians in the technical field to which this application belongs; the terms used herein are only for the purpose of describing specific embodiments and are not intended to limit this application; the terms "including" and "having" in the specification and claims of this application and the above-mentioned figure descriptions and any variations thereof are intended to cover non-exclusive inclusions.

[0042] Please refer to Figures 1 to 5The present invention proposes an automatic vibration reduction support for a nuclear power plant suspended pump, comprising a data acquisition control mechanism 1 and at least one vibration adjustment component 2. The data acquisition control mechanism 1 comprises a vibration sensor 11 and a data acquisition processing device 12. The vibration sensor 11 is installed at the bottom of the suspended pump 4. The data acquisition processing device 12 is used to receive the vibration signal of the vibration sensor 11. Each vibration adjustment component 2 comprises an oil storage tank 21 and an oil cylinder 22. A control valve 23 is provided between the oil storage tank 21 and the oil cylinder 22. A piston 24 is provided in the oil cylinder 22. One end of the piston 24 abuts against the suspended pump 4. The data acquisition control mechanism 1 also comprises a valve drive mechanism 13 connected to the control valve 23. The valve drive mechanism 13 is used to control the opening and closing of the control valve 23, thereby adjusting the piston 24 to be in a free motion state or decoupling the support of the suspended pump 4.

[0043] It can be seen that the automatic vibration reduction support for the nuclear power plant suspended pump proposed in the present invention is intended to solve the problem that due to the expansion of a circuit itself or the limitation of the layout space, it is difficult to change the structural frequency by adding rigid supports to the main coolant system pipeline and the suspended pump 4, thereby reducing the large horizontal vibration of the suspended pump 4.

[0044] Specifically, the vibration sensor 11 is installed at the bottom end of the suspended pump 4. The vibration sensor 11 is electrically connected to the data acquisition and processing equipment 12. The vibration sensor 11 is used to measure the vibration information at the end of the suspended pump 4. The data acquisition and processing equipment 12 obtains the velocity time course and spectrum of the vibration after processing, and obtains the vibration peak frequency and vibration level at the end of the suspended pump 4.

[0045] The valve drive mechanism 13 is electrically connected to the data acquisition and processing device 12, and is used to open or close the control valve 23. When the valve is in the open state, the piston 24 in the oil cylinder 22 is pulled to push the hydraulic medium through the control valve 23 into the oil storage tank 21, and the piston 24 can move freely in the oil cylinder 22. At this time, one end of the piston 24 does not support the suspended pump 4, and the thermal expansion displacement caused by the temperature rise and fall of the main cooling circuit can be released.

[0046] When the data acquisition and processing device 12 detects that the vibration signal is coupled with the natural frequency of the suspension pump 4 and is amplified, the control valve 23 is closed to activate one end of the piston 24, thereby changing the natural frequency of the suspension pump 4, thereby avoiding resonance between the excitation frequency and the suspension pump 4.

[0047] When the control valve 23 is closed, the oil cylinder 22 is in a closed state, and the position of the piston 24 is in a stationary state under the action of air pressure, thereby forming a stable support for the suspended pump 4, thereby changing the natural frequency of the suspended pump 4.

[0048] Reference Figure 2, and also includes a supporting mechanism 3, one end of the vibration adjustment component 2 is slidably connected to the supporting mechanism 3, and the sliding direction is vertically consistent with the suspended pump 4.

[0049] Specifically, a support base 211 is provided at one end of the oil storage tank 21, and the support base 211 and the support mechanism 3 are slidably matched through a slide rail and a slideway.

[0050] It can be known that the support mechanism 3 can be a wall or other structure that can provide support, which is not limited here.

[0051] The support base 211 is slidably connected to the support mechanism 3, so that the vibration adjustment component 2 can move vertically along the suspended pump 4. By supporting at different positions of the suspended pump 4, the natural frequency of the suspended pump 4 can be changed within a certain range, thereby better avoiding the excitation frequency.

[0052] Please refer to Figure 3 The number of the vibration adjustment components 2 is at least two, and the two vibration adjustment components 2 are arranged at intervals along the vertical direction of the suspended pump 4.

[0053] A plurality of vibration regulating components 2 are connected in parallel and operate independently. By changing the number of active supports, the overall stiffness of the vibration-damping support of the present invention is changed. In this way, the natural frequency of the suspended pump 4 can be changed within a certain range, thereby better avoiding the excitation frequency.

[0054] Furthermore, each vibration adjustment component 2 is slidably matched with the supporting mechanism 3 .

[0055] That is, the number and position of the active vibration adjustment components 2 can be changed simultaneously to avoid the excitation frequency. Both methods are acceptable and can be used together.

[0056] In one embodiment, a support member 25 is provided at one end of the piston 24 away from the oil storage tank 21 , and one end of the support member 25 away from the piston 24 abuts against the suspended pump 4 .

[0057] That is, one end of the piston 24 may directly abut against the suspended pump 4 , or may abut against the suspended pump 4 by means of a support member 25 .

[0058] Furthermore, the length of the support member 25 is adjustable, so that it can be adapted to different suspended pumps 4 .

[0059] The present invention also proposes a nuclear power plant suspended pump 4, comprising a suspended pump 4, a suspended pump support seat 5 and the above-mentioned nuclear power plant suspended pump automatic vibration reduction support; the top end of the suspended pump 4 is connected to the suspended pump support seat 5, and one end of the piston 24 of the nuclear power plant suspended pump automatic vibration reduction support is abutted against the bottom end of the suspended pump 4.

[0060] It should be noted that, by means of at least one vibration adjustment component 2, which is arranged on the outside of the suspended pump 4, the thermal expansion displacement caused by the heating and cooling of the main cooling circuit can be released without affecting the original stress condition of the main cooling system, the normal operation of the suspended pump 4, or the layout space of the solidified nuclear power plant.

[0061] Reference Figure 4 The real-time monitoring data of the vibration sensor 11 is collected by the data acquisition and processing equipment 12 of the automatic vibration reduction support of the nuclear power plant suspension pump, so as to obtain the internal excitation intensity and spectrum of the main cooling circuit, and the suspension pump 4 is supported by one end of the piston 24 of the vibration adjustment component 2 to change the natural frequency of the suspension pump 4; and the natural frequency of the suspension pump 4 can be dynamically adjusted according to the fluid excitation at different speeds, so that the excitation frequency of the main coolant circuit is decoupled from the natural frequency of the suspension pump 4, and the stable operation of the suspension pump 4 at various speeds is achieved, eliminating the excessive stress or fatigue of the main cooling circuit caused by vibration, and improving the safety level of the power plant.

[0062] Reference Figure 5 The present invention also proposes an automatic vibration reduction method for a nuclear power plant suspended pump, which is implemented by using the above automatic vibration reduction support for the nuclear power plant suspended pump. The vibration reduction method includes:

[0063] Step 1, receiving a vibration signal from a vibration sensor;

[0064] Step 2: When the vibration signal is coupled and amplified with the natural frequency of the suspension pump and exceeds a threshold, the control valve is closed through the valve drive mechanism so that the piston effectively supports the suspension pump to decouple.

[0065] Specifically, a plurality of groups of vibration adjustment components are arranged vertically along the suspended pump, and the natural frequency of the suspended pump is changed within a certain range by changing the number of the vibration adjustment components.

[0066] Specifically, the vibration sensor obtains the original vibration data of the suspended pump, and then transmits the data to the data acquisition and processing equipment. The data acquisition and processing equipment processes the data. When the vibration frequency is coupled with the natural frequency of the suspended pump and amplified beyond the threshold, the data acquisition and processing equipment sends a signal to the valve drive mechanism to close the control valve, so that the support member effectively supports the suspended pump, and the natural frequency of the suspended pump is changed to change the vibration decoupling; when the vibration frequency is coupled with the natural frequency of the suspended pump and the amplification does not exceed the threshold, the control valve is in a normally open state, and the support member does not effectively support the suspended pump.

[0067] In the description of the embodiments of the present application, unless otherwise clearly specified and limited, technical terms such as "install", "connect", "connect", "fixed" and the like should be understood in a broad sense. For example, it can be a fixed connection, a detachable connection, or an integral connection; it can also be a mechanical connection. For ordinary technicians in this field, the specific meanings of the above terms in the embodiments of the present application can be understood according to the specific circumstances.

[0068] The present application uses specific words to describe the embodiments of the present application. For example, "one embodiment", "an embodiment", and / or "some embodiments" refer to a certain feature, structure or characteristic related to at least one embodiment of the present application. Therefore, it should be emphasized and noted that "one embodiment" or "an embodiment" or "an alternative embodiment" mentioned twice or multiple times in different positions in this specification does not necessarily refer to the same embodiment. In addition, some features, structures or characteristics in one or more embodiments of the present application can be appropriately combined.

[0069] Although the present invention is disclosed as above with preferred embodiments, it is not intended to limit the present invention. Any person skilled in the art may make possible changes and modifications without departing from the spirit and scope of the present invention. Therefore, any modification, equivalent change and modification made to the above embodiments according to the technical essence of the present invention without departing from the content of the technical solution of the present invention shall fall within the protection scope defined by the claims of the present invention.

Claims

1. An automatic vibration reduction support for a nuclear power plant suspended pump, characterized in that: include: A data acquisition control mechanism, comprising a vibration sensor and a data acquisition processing device, wherein the vibration sensor is installed at the bottom of the suspended pump, and the data acquisition processing device is used to receive a vibration signal from the vibration sensor; At least one vibration regulating assembly, each of which comprises an oil storage tank and an oil cylinder, a control valve is provided between the oil storage tank and the oil cylinder, a piston is provided in the oil cylinder, one end of the piston is in contact with the suspended pump; wherein, The data acquisition control mechanism also includes a valve driving mechanism connected to the control valve, and the valve driving mechanism is used to control the opening and closing of the control valve, thereby adjusting the piston to a free motion state or decoupling the suspension pump support.

2. The automatic vibration reduction support for a nuclear power plant suspended pump according to claim 1, characterized in that: It also includes a supporting mechanism, one end of the vibration adjustment component is slidably connected to the supporting mechanism, and the sliding direction is vertically consistent with the suspended pump.

3. The automatic vibration reduction support for a nuclear power plant suspended pump according to claim 2, characterized in that: A support base is provided at one end of the oil storage tank, and the support base is slidably matched with the support mechanism through a slide rail and a slideway.

4. The automatic vibration reduction support for a nuclear power plant suspended pump according to claim 2, characterized in that: The number of the vibration adjustment components is at least two, and the two vibration adjustment components are arranged at intervals in the vertical direction of the suspended pump.

5. The automatic vibration reduction support for a nuclear power plant suspended pump according to claim 4, characterized in that: Each of the vibration adjustment components is slidably matched with the support mechanism.

6. The automatic vibration reduction support for a nuclear power plant suspended pump according to claim 4, characterized in that: The control valve of each vibration adjustment assembly is connected to the valve drive mechanism and is controlled independently of each other.

7. The automatic vibration reduction support for a nuclear power plant suspended pump according to claim 1, characterized in that: A support member is provided at one end of the piston away from the oil storage tank, and one end of the support member away from the piston abuts against the suspension pump.

8. A nuclear power plant suspended pump, characterized in that: include: A suspended pump, a suspended pump support seat and an automatic vibration reduction support for a nuclear power plant suspended pump as claimed in any one of claims 1 to 7; The top end of the suspension pump is connected to the suspension pump support seat, and one end of the piston of the automatic vibration reduction support of the nuclear power plant suspension pump is abutted against the bottom end of the suspension pump.

9. An automatic vibration reduction method for a suspended pump in a nuclear power plant, characterized in that: The automatic vibration reduction support for a nuclear power plant suspended pump according to any one of claims 1 to 7 is used, and the vibration reduction method comprises: Step 1, receiving a vibration signal from a vibration sensor; Step 2: When the vibration signal is coupled and amplified with the natural frequency of the suspension pump and exceeds a threshold, the control valve is closed through the valve drive mechanism so that the piston effectively supports the suspension pump for decoupling.

10. The automatic vibration reduction method for a suspended pump in a nuclear power plant according to claim 9, characterized in that: A plurality of groups of vibration adjustment components are arranged vertically along the suspended pump, and the natural frequency of the suspended pump can be changed within a certain range by changing the number of the vibration adjustment components.

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