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Anti-vibration bar structure of steam generator in nuclear power plant

A technology for steam generators and anti-vibration strips, which is applied in the field of anti-vibration strips for steam generators in nuclear power plants, and can solve problems such as the scrapping of heat transfer tubes 10, the decline in efficiency of steam generators, and the impact on thermal and hydraulic characteristics of steam generators, etc. Achieve the effect of increasing the anti-rotation offset ability

Active Publication Date: 2019-03-19
中广核工程有限公司 +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0005] However, the above-mentioned structure does not have a limiting device for the rotation deviation of the anti-vibration strip assembly 14, which leads to deviations in the control of the gap between the heat transfer tube 10 and the anti-vibration strip when the anti-vibration strip assembly 14 is assembled in the factory, and makes the anti-vibration During the manufacture, assembly, long-distance transportation, on-site installation and equipment production and operation of the bar assembly 14, it is easy to rotate due to the combined effect of gravity, inertia, vibration and strong vapor-liquid fluid impact force during operation, for example, figure 1 The uppermost layer anti-vibration strip assembly 14 in the center has just shifted to the right
If the anti-vibration bar assembly 14 deviates seriously, it will affect the thermal-hydraulic characteristics of the steam generator, aggravate the fretting wear of the heat transfer tube 10, cause the heat transfer tube 10 to be scrapped (pipe plugging), and make the efficiency of the steam generator decline

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  • Anti-vibration bar structure of steam generator in nuclear power plant
  • Anti-vibration bar structure of steam generator in nuclear power plant
  • Anti-vibration bar structure of steam generator in nuclear power plant

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Embodiment Construction

[0029] In order to make the purpose, technical solution and beneficial technical effects of the present invention clearer, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific embodiments. It should be understood that the specific implementations described in this specification are only for explaining the present invention, not for limiting the present invention.

[0030] see figure 2 The steam generator anti-vibration bar structure of the present invention includes multiple sets of anti-vibration bar assemblies 20 installed on the bend section of the heat transfer tube 10, holding bars for limiting the radial movement of the anti-vibration bar assembly 20 relative to the bend section, and preventing the anti-vibration bar assembly The vibration bar assembly 20 is an anti-deflection assembly for rotation deflection.

[0031] see Figure 3-5 , each anti-vibration strip assembly 20 includes a plurality of a...

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Abstract

The invention discloses an anti-vibration bar structure of a nuclear power plant steam generator. The structure comprises at least two sets of anti-vibration bar assemblies installed on bent pipe sections of heat transfer pipes, retaining bars for limiting the anti-vibration bar assemblies from moving in the radial direction, and anti-deviation assemblies for preventing the anti-vibration bar assemblies from deviating. The anti-vibration bar assemblies are connected together through the anti-deviation assemblies. Compared with the prior art, according to the anti-vibration bar structure of the nuclear power plant steam generator, the independent anti-vibration bar assemblies are connected together through the anti-deviation assemblies, and the rotation and deviation prevention ability of anti-vibration bars is improved.

Description

technical field [0001] The invention belongs to the anti-vibration field of steam generator heat transfer tubes in nuclear power plants, and more specifically relates to an anti-vibration bar structure for steam generators in nuclear power plants. Background technique [0002] The steam generator is the heat exchange equipment between the first and second loops of the pressurized water reactor nuclear power plant. The U-shaped heat transfer tube is the core component of the steam generator, which plays the role of transferring heat and isolating radioactive coolant between the first and second loops. In a known nuclear power plant, the length of the straight section of the heat transfer tube of a vertical steam generator is about 10m, the maximum bend radius is nearly 2m, the tube diameter is 17-19mm, and the wall thickness is about 1mm; the tube bundle of a steam generator has 4000 ~10000 heat transfer tubes, the tube spacing is about 7~8mm. During operation, the high-spee...

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): F22B37/20
CPCF22B37/205
Inventor 徐明峰毋争娟吴书声
Owner 中广核工程有限公司