Noise Reduction and Vibration Damping Wall Structure and Vibration Reduction Methods for Nuclear Power Plant Main Control Room

Abstract

This application provides a noise reduction and vibration damping wall structure and vibration reduction method for the main control room of a nuclear power plant. The vibration damping wall structure includes: a first axial wall located on one side of the main control room; and a first span wall located on the side of the first axial wall away from the main control room. A main steam pipe extending from the nuclear island passes through the first axial wall and the first span wall, and the main steam pipe is supported on the first span wall. The noise reduction and vibration damping wall structure and vibration reduction method of this application transfers the vibration generated by fluid flow in the main steam pipe to the first span wall outside the main control room, interrupting the propagation path of vibration to the main control room. This significantly reduces the noise in the main control room, greatly improves the acoustic environment of the main control room, and provides a better acoustic working environment for the main control room staff.

Description

Technical Field

[0001] This application relates to the field of nuclear power plant design technology, and in particular to the design of a noise reduction and vibration damping wall structure and vibration reduction method for the main control room of a nuclear power plant. Background Technology

[0002] The main control room is the control center of a nuclear power plant, where the plant is monitored, controlled, and operated. The acoustic design of the main control room is a key issue in human factors engineering. In recent years, noise levels in the main control room have received increasing attention from nuclear power plant owners and regulatory authorities. In one project, the main control room for four units experienced high noise levels during full power operation. At 100% full power, the measured noise level in the main control room was approximately 62-63 dB. This high noise level negatively impacts the reliability of operations by personnel in the main control room and poses potential adverse health effects.

[0003] Through on-site measurement and analysis of the vibration and noise in the main control room, it can be seen that the noise in the main control room is caused by the vibration of the main steam pipe, which is transmitted to the wall of the main control room through the support position, and finally radiated by the wall of the main control room.

[0004] To address vibration and noise sources, hydrodynamic noise is generally controlled by reducing abrupt changes in flow paths within pipe components. Control methods focus on the following: 1. Modifying the structure of pipe components that act as vibration and noise sources to reduce interference with the fluid. 2. Reducing flow velocity. 3. Optimizing the placement of pipe components or reducing the number of related components within the pipe. 4. Installing hydraulic noise silencers, typically including expansion tubes and Helmholtz resonant cavity structures. These measures involve modifications to the main steam system of nuclear power plants and are also limited by the modification and application of mature nuclear energy system equipment, potentially impacting the safe and stable operation of nuclear power plants.

[0005] To address vibration and noise transmission paths, a common approach is to use flexible installations for system piping. Common methods include using vibration isolators, vibration damping pads, and vulcanized clamps. Inserting flexible connectors into the piping is also a frequently used technique for vibration reduction and noise reduction. However, considering the noise characteristics of the main control room and the seismic requirements of nuclear power plants, the effectiveness of commonly used piping vibration isolation components in controlling the vibration and noise generated by fluid flow within the pipes is quite limited.

[0006] For the control of vibration and noise at the terminal, passive sound-absorbing devices are generally installed to reduce noise. However, due to the large space of the main control room, the low noise frequency band, and the presence of significant strong line spectra, and considering the safety requirements of the main control room, traditional sound-absorbing devices cannot achieve good noise reduction effects.

[0007] In summary, traditional vibration and noise control methods are generally not very effective or adaptable to noise problems in the main control room of nuclear power plants. Therefore, a new control scheme is needed that can effectively reduce noise in the main control room without affecting the safe and stable operation of the nuclear power plant. Summary of the Invention

[0008] In view of the above problems, this application provides a noise reduction and vibration reduction wall structure and vibration reduction method for the main control room of a nuclear power plant, which can significantly reduce the noise in the main control room under the power operation conditions of a nuclear power plant, and fundamentally solve the problem of excessive noise in the main control room.

[0009] The first aspect of this application provides a noise reduction and vibration damping wall structure for the main control room of a nuclear power plant, comprising: a first axial wall located on one side of the main control room; and a first span wall disposed on the side of the first axial wall away from the main control room; wherein a main steam pipe leading from the nuclear island passes through the first axial wall and the first span wall, and the main steam pipe is supported on the first span wall.

[0010] Preferably, the main control room is located on the side of the first axis wall facing the nuclear island.

[0011] Preferably, the first span wall is a nuclear seismic-resistant wall, and its structural form is a shear wall structure.

[0012] Preferably, the seismic input for the first span of the wall is the seismic response spectrum of the envelope site SL-2.

[0013] Preferably, the thickness of the first span wall section is 900mm.

[0014] Preferably, the wall at the location where the first span supports the main steam pipe has a thickness of 1200mm below 10.744m.

[0015] Preferably, the diameter of the hole through the first axial wall of the main steam pipe is larger than the diameter of the main steam pipe.

[0016] The second aspect of this application provides a method for noise reduction and vibration reduction in the main control room of a nuclear power plant, comprising the following steps: setting a first axial wall on one side of the main control room; setting a first cross wall on the side of the first axial wall away from the main control room; and a main steam pipe leading out from the nuclear island passing through the first axial wall and the first cross wall, with the main steam pipe supported on the first cross wall.

[0017] The noise reduction and vibration reduction method for the main control room of a nuclear power plant in this application also includes a step of verifying the vibration and noise of the main control room.

[0018] Preferably, the steps for verifying the vibration and noise of the main control room include: establishing an analysis model of the main control room; taking the support position of the main steam pipe as the vibration source input; taking the noise at the center of the main control room as the evaluation point; and calculating the vibration and noise of the main control room in combination with empirical parameters from the nuclear power plant site.

[0019] The noise reduction and vibration damping wall structure and vibration reduction method of the nuclear power plant main control room of this application transfers the vibration generated by the fluid operation in the main steam pipeline to the first span wall outside the main control room, interrupting the propagation path of the vibration to the main control room. This can significantly reduce the noise in the main control room, greatly improve the acoustic environment of the main control room, and provide a better acoustic working environment for the main control room staff. Attached Figure Description

[0020] To more clearly illustrate the technical solutions of the embodiments of this application, the accompanying drawings used in the embodiments of this application will be briefly introduced below. Obviously, the drawings described below are only specific embodiments of this application. Those skilled in the art can obtain other embodiments based on the following drawings without creative effort.

[0021] Figure 1 This is a schematic diagram of a noise reduction and vibration damping wall structure in the main control room of a nuclear power plant, according to a specific embodiment of this application.

[0022] Figure 2 This is a flowchart of a noise reduction and vibration damping method for the main control room of a nuclear power plant, according to a specific embodiment of this application.

[0023] Figure 3 This is a flowchart illustrating the verification of vibration and noise in the main control room according to a specific embodiment of this application.

[0024] The accompanying drawings, which are incorporated in and form part of this specification, illustrate embodiments consistent with this application and, together with the description, serve to explain the principles of this application. Detailed Implementation

[0025] To better understand the technical solution of this application, the embodiments of this application will be described in detail below with reference to the accompanying drawings.

[0026] It should be understood that the following embodiments are only some embodiments of this application. Based on the following embodiments, all other embodiments obtained by those skilled in the art without inventive effort are within the scope of protection of this application.

[0027] The terminology used in the embodiments of this application is for the purpose of describing particular embodiments only and is not intended to be limiting of this application. The singular forms “a,” “the,” and “the” used in the embodiments of this application and the appended claims are also intended to include the plural forms unless the context clearly indicates otherwise.

[0028] It should be understood that the term "and / or" used in this article is merely a description of the relationship between related objects, indicating that three relationships can exist. For example, A and / or B can represent: A existing alone, A and B existing simultaneously, and B existing alone. Additionally, the character " / " in this article generally indicates that the preceding and following related objects have an "or" relationship.

[0029] It should be noted that the directional terms such as "upper," "lower," "left," and "right" described in the embodiments of this application are used to describe the angles shown in the accompanying drawings and should not be construed as limiting the embodiments of this application. Furthermore, in the context, it should be understood that when it is mentioned that an element is connected "upper" or "lower" to another element, it can be directly connected to the other element "upper" or "lower," or indirectly connected to the other element "upper" or "lower" through an intermediate element.

[0030] The main control room is the control center of a nuclear power plant, where the plant is monitored, controlled, and operated. The acoustic design of the main control room is a key issue in human factors engineering, and in recent years, noise problems in the main control room have received increasing attention from nuclear power plant owners and regulatory authorities.

[0031] On-site measurements and analysis of vibration and noise in the main control room revealed that, during full-power operation, the frequency components of noise within the main control room area are primarily concentrated in the low-frequency range below 500Hz, exhibiting significant strong line spectrum characteristics. In existing nuclear power plant buildings, the main steam pipelines have very high flow velocities, and their supports are located on the first axial wall. The noise in the main control room is highly consistent with the vibration frequencies of the main steam pipelines and nearby walls, and the vibration amplitude of the noise in the main control room and nearby walls increases the closer to the support location of the main steam pipeline. These phenomena indicate that the noise in the main control room is caused by the vibration of the main steam pipelines, transmitted through the support location to the main control room walls, and finally radiated from the main control room walls.

[0032] To address the noise problem in the main control room, a comprehensive approach is needed, addressing the source, transmission path, and endpoint of vibration noise. Solving pipeline vibration engineering problems requires adopting different design principles and methods based on the characteristics of the vibration and noise to achieve satisfactory overall results.

[0033] This application addresses the problem of noise in the main control room caused by vibration of the main steam pipeline by transferring the vibration of the main steam pipeline from the first axis wall to a wall away from the main control room, thereby reducing the vibration noise in the main control room.

[0034] Figure 1 This is a schematic diagram of a noise reduction and vibration damping wall structure in the main control room of a nuclear power plant, according to a specific embodiment of this application.

[0035] like Figure 1As shown, a noise reduction and vibration damping wall structure for the main control room of a nuclear power plant according to an embodiment of this application includes: a first axial wall 2, which is located on one side of the main control room 1; and a first cross wall 3, which is disposed on the side of the first axial wall 2 away from the main control room 1; wherein, the main steam pipe 101 leading out from the nuclear island 100 passes through the first axial wall 2 and the first cross wall 3, and the main steam pipe 101 is supported on the first cross wall 3.

[0036] The distance between the first axis wall 2 and the first span wall 3 is 800-1200mm.

[0037] The first axis wall 2 is connected to the wall of the main control room 1. The original building of the nuclear power plant supports the main steam pipe 101 on the first axis wall 2, which transmits the vibration of the main steam pipe 101 to the main control room 1, causing the main control room 1 to generate high noise, which has an adverse effect on the reliability of operation by personnel in the main control room and has potential adverse effects on their health.

[0038] In order to reduce the transmission of vibration of the main steam pipe 101 to the main control room 1, this application redesigned the first span wall 3 adjacent to the first axial wall 2, and transferred the support point of the main steam pipe 101 to the first span wall 3, thereby transferring the vibration of the main steam pipe 101 to the first span wall 3, thus avoiding the transmission of the vibration of the main steam pipe 101 to the first axial wall 2 connected to the main control room 1, and reducing the noise generated in the main control room 1 due to the vibration of the main steam pipe 101.

[0039] Please continue to refer to this. Figure 1 In one specific embodiment, the main control room 1 is located on the side of the first axial wall 2 facing the nuclear island 100. When designing and laying out the nuclear power plant building, in order to make reasonable use of space, the main control room 1 is located on the side of the first axial wall 2 facing the nuclear island 100, and the first span wall 3 is located on the side of the first axial wall 2 away from the main control room 1. In this way, the main steam pipe 101 is supported on the first span wall 3, and the vibration generated by the fluid operation in the main steam pipe 101 is transferred to an area outside the main control room 1, thus blocking the propagation path of vibration to the main control room 1, thereby significantly reducing the noise of the main control room 1.

[0040] Nuclear power plant properties are classified into three seismic resistance categories: Seismic Resistance Category I, Seismic Resistance Category II, and Non-Seismic Resistance Category. Seismic Resistance Category I applies to safety-related structures, systems, and components, as well as structures, systems, and components that support or protect safety-related structures, systems, and components. Seismic Resistance Category II applies to structures, systems, and components performing non-safety-related functions and functions that are not required to continue performing under a safe shutdown earthquake. Structures, systems, and components not classified as Seismic Resistance Category I or II are considered non-nuclear seismic-resistant structures, systems, and components.

[0041] The original first span wall of the nuclear power plant was a non-nuclear seismic-resistant wall. To ensure the strength of the nuclear power plant building, meet the functional requirements of the support points, and enable the first span wall 3 to stably support the main steam pipe 101, the first span wall 3 was designed as a nuclear seismic-resistant wall, meeting the relevant requirements of the Class I seismic design code for nuclear power plants. Its structural form is a shear wall structure. The first span wall 3, meeting the Class I seismic requirements, ensures the safety of the main steam pipe 101 and complies with stringent regulations and standards.

[0042] The seismic input for the first span of wall 3 is the seismic response spectrum that encloses the site SL-2.

[0043] In some embodiments, the thickness of the first span wall 3 is 900–1200 mm. Preferably, increasing the thickness of the first span wall 3 from 600 mm to 900 mm enhances its structural strength and stability, and improves its safety.

[0044] Furthermore, in order to stably support the main steam pipe 101, the wall of the first span wall 3 supporting the main steam pipe 101 has a thickness of 1200-1500mm below 10.744m, preferably 1200mm.

[0045] In order to prevent the vibration of the main steam pipe 101 from being transmitted to the first axial wall 2, the diameter of the through hole through the main steam pipe 101 in the first axial wall 2 is larger than the diameter of the main steam pipe 101, thereby reducing the possibility of the main steam pipe 101 contacting the first axial wall 2 and transmitting the vibration to the support point of the first cross wall 3 as much as possible, thereby reducing the vibration of the first axial wall 2 and reducing the noise in the main control room 1.

[0046] Figure 2 This is a flowchart of a noise reduction and vibration damping method for the main control room of a nuclear power plant, according to a specific embodiment of this application.

[0047] like Figure 2 As shown, the noise reduction and vibration reduction method for the main control room of a nuclear power plant according to this application includes the following steps:

[0048] Step S1: Set up a first axis wall 2 on one side of the main control room 1.

[0049] Step S2: Set up a first cross wall 3 on the side of the first axis wall 2 away from the main control room.

[0050] In step S3, the main steam pipe 101 leading out from the nuclear island 100 passes through the first axial wall 2 and the first cross wall 3, and the main steam pipe 101 is supported on the first cross wall 3.

[0051] In order to reduce the transmission of vibration from the main steam pipe 101 to the main control room 1, the noise reduction and vibration reduction method for the main control room of the nuclear power plant in this application redesigns the first span wall 3 adjacent to the first axial wall 2, and transfers the support point of the main steam pipe 101 to the first span wall 3, thereby transferring the vibration of the main steam pipe 101 to the first span wall 3, thus avoiding the transmission of the vibration of the main steam pipe 101 to the first axial wall 2 connected to the main control room 1, and reducing the noise generated in the main control room 1 due to the vibration of the main steam pipe 101.

[0052] In some embodiments, the noise reduction and vibration reduction method for the main control room of a nuclear power plant according to this application further includes step S4 of verifying the vibration and noise of the main control room 1.

[0053] Figure 3 This is a flowchart illustrating the verification of vibration and noise in the main control room according to a specific embodiment of this application.

[0054] like Figure 3 As shown, in one specific embodiment, step S4 of verifying the vibration and noise of the main control room 1 includes:

[0055] Step S41: Establish an analysis model of the main control room 1. The analysis model establishes the positional relationship between the main control room 1, the first axis wall 2, and the first span wall 3, and determines the support position of the main steam pipe 101 in the first span wall 3.

[0056] Step S42: Use the support position of the main steam pipe 101 as the vibration source input. After the model is built, use the support position of the main steam pipe 101 as the vibration source input point.

[0057] Step S43: Take the noise at the center of the main control room 1 as the evaluation point.

[0058] Step S44: Based on empirical parameters from the nuclear power plant site, calculate the vibration noise of the main control room 1. When calculating the noise, the classical laws and formulas of vibration transmission and vibration conversion noise are used, combined with empirical parameters from the nuclear power plant site, as the analysis method for vibration noise transmission to calculate the noise reduction effect. Calculations show that after the main steam pipe support position is adjusted, the noise in the main control room 1 decreases significantly.

[0059] The noise reduction and vibration reduction method for the main control room of a nuclear power plant proposed in this application can significantly reduce the noise of the main control room 1 under the power operation conditions of the nuclear power plant, reducing the noise by about 7-8 dB(A), greatly improving the acoustic environment of the main control room 1, and providing a better acoustic working environment for the staff of the main control room 1.

[0060] The above description is merely a preferred embodiment of this application and is not intended to limit this application. Various modifications and variations can be made to this application by those skilled in the art. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of this application should be included within the protection scope of this application.

Claims

1. A nuclear power plant main control room noise reduction and vibration damping wall structure, characterized in that, include: The first axis wall is located on one side of the main control room; The first span wall is located on the side of the first axial wall away from the main control room; The main steam pipe leading from the nuclear island passes through the first axial wall and the first cross wall, and the main steam pipe is supported on the first cross wall, so that the support point of the main steam pipe is transferred to the first cross wall, thus preventing the vibration of the main steam pipe from being transmitted to the first axial wall connected to the main control room.

2. The nuclear power plant main control room noise and vibration reduction wall structure of claim 1, wherein, The main control room is located on the side of the first axis wall facing the nuclear island.

3. The nuclear power plant main control room noise and vibration reduction wall structure of claim 1, wherein, The first span wall is a nuclear seismic-resistant wall, and its structural form is a shear wall structure.

4. The nuclear power plant main control room noise and vibration reduction wall structure according to claim 3, wherein, The thickness of the first span wall section is 900mm.

5. The nuclear power plant main control room noise and vibration reduction wall structure of claim 4, wherein, The wall at the location where the main steam pipe is supported by the first span wall has a thickness of 1200mm below 10.744m.

6. The nuclear power plant main control room noise and vibration reduction wall structure of claim 1, wherein, The diameter of the through hole through which the main steam pipe passes through the first axial wall is larger than the diameter of the main steam pipe.

7. A method for noise reduction and vibration damping in the main control room of a nuclear power plant, characterized in that, Includes the following steps: A first axial wall is installed on one side of the main control room; A first span wall is provided on the side of the first axis wall away from the main control room; The main steam pipe leading from the nuclear island passes through the first axial wall and the first cross wall, and the main steam pipe is supported on the first cross wall, so that the support point of the main steam pipe is transferred to the first cross wall, avoiding the vibration of the main steam pipe from being transmitted to the first axial wall connected to the main control room, thereby reducing the noise generated in the main control room by the vibration of the main steam pipe.

8. The method for noise reduction and vibration damping in the main control room of a nuclear power plant according to claim 7, characterized in that, It also includes a step of verifying the vibration and noise of the main control room.

9. The method for noise reduction and vibration damping in the main control room of a nuclear power plant according to claim 8, characterized in that, The steps for verifying the vibration and noise of the main control room include: Establish an analytical model for the main control room; The vibration source input is the support position of the main steam pipeline; The noise level at the center of the main control room is taken as the evaluation point; Based on empirical parameters from nuclear power plant sites, the vibration noise of the main control room was calculated.

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