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Nuclear power plant flow-induced vibration test data acquisition device

A technology for data acquisition and vibration testing, applied in the field of nuclear power plants, can solve the problems of inability to realize multi-platform data analysis system data processing reliability, high risk of human and equipment failure, and chaotic cable path layout. Improve the effectiveness of real, enhanced analytics

Pending Publication Date: 2021-06-01
中广核工程有限公司 +2
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] (1) The fault tolerance of the device is poor. Once the tape recorder equipment fails or is misoperated, all measurement data is easily lost, and the risk of human factors and equipment failure is high;
[0006] (2) The reliability of the data results is low, the data can only be analyzed using a dedicated device, and the multi-platform data analysis system cannot be compared to verify the reliability of data processing;
[0007] (3) The data synchronous acquisition capacity is small, and it is difficult to increase redundant acquisition channels;
[0008] (4) The layout of the measurement system is scattered, and different types of signals need to be adjusted separately, which takes up a large test space and the layout of cable paths is easy to be confused.

Method used

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  • Nuclear power plant flow-induced vibration test data acquisition device
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Embodiment Construction

[0034] The following will clearly and completely describe the technical solutions in the embodiments of the present invention with reference to the accompanying drawings in the embodiments of the present invention. Obviously, the described embodiments are only some, not all, embodiments of the present invention. Based on the embodiments of the present invention, all other embodiments obtained by persons of ordinary skill in the art without making creative efforts belong to the protection scope of the present invention.

[0035] see figure 1 and figure 2 , the embodiment of the present invention provides a nuclear power plant flow-induced vibration test data acquisition device, including a first cabinet 100, a second cabinet 200 and a remote workstation 300; wherein, the first cabinet 100 includes a first cabinet 110 and a set The data acquisition host 120 and a plurality of signal conditioners 130 on the first cabinet 110; the second cabinet 200 includes a second cabinet 210...

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Abstract

The invention discloses a nuclear power plant flow-induced vibration test data acquisition device, which comprises a first cabinet, a second cabinet and a remote workstation, wherein the first cabinet comprises a first cabinet body, a data acquisition host, a main clock and a plurality of signal conditioners, the second cabinet comprises a second cabinet body, a data analysis host, a switch, a first photoelectric interface converter and a power supply, the output ends of the plurality of signal conditioners are connected to the data acquisition host and the data analysis host, the data acquisition host and the data analysis host are synchronized through the main clock, the data acquisition host and the data analysis host are connected to the remote workstation, and the power supply is connected with the data analysis host, the switch, the main clock and the data acquisition host. According to the invention, the reliability and authenticity of test data can be improved, the integrated design architecture of the device improves the capacity of channel measurement quantity, the difficulty of device management is reduced, and the risk of delaying project progress is reduced.

Description

technical field [0001] The invention relates to the field of nuclear power plants, in particular to a data acquisition device for flow-induced vibration tests of nuclear power plants. Background technique [0002] During the operation of a nuclear power plant reactor, the flow of coolant will cause structural vibration of the internal components of the reactor, and the flow-induced vibration may cause fatigue damage to the structure or loosening or wear damage to the connecting parts, resulting in accidents that may force the nuclear power plant to shut down for maintenance, resulting in Huge economic loss. Therefore, during the thermal functional test of the first nuclear power plant, on-site measurement of flow-induced vibration of reactor internals is required to evaluate the structural characteristics of reactor internals, verify the structural integrity of reactor internals, and determine the Safety margins associated with steady-state and anticipated transient conditi...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01H17/00
CPCG01H17/00
Inventor 周念陆柏松张鹏汤帅
Owner 中广核工程有限公司
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