Device and method for measuring section steam content of tube bundle area of steam generator

A technology of steam generator and steam content, applied in the direction of using radiation for material analysis, etc., can solve the problems of limited circular tube, radiation danger, and the influence of complex structure in the tube is not considered, so as to improve the measurement accuracy and avoid the effect of interference.

Active Publication Date: 2019-03-29
XI AN JIAOTONG UNIV
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Problems solved by technology

Traditional ray measurement methods are limited to round tubes, without considering the influence of complex structures inside the tube
In addition, the operation of radiation has a certain degree of danger, and certain protection against radiation radiation is required to ensure the safety of personnel.
[0010] Based on the above review of traditional cross-section vapor content measurement methods, each method has its advantages, but inevitably has limitations

Method used

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  • Device and method for measuring section steam content of tube bundle area of steam generator
  • Device and method for measuring section steam content of tube bundle area of steam generator
  • Device and method for measuring section steam content of tube bundle area of steam generator

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Embodiment Construction

[0060] The present invention will be described in further detail below in conjunction with the accompanying drawings.

[0061] The embodiment of the present invention provides a method and an experimental device for measuring the steam content in the section of the tube bundle area of ​​a steam generator, figure 1 It is a schematic diagram of the gamma ray scanning mobile measurement structure, which is used to describe the gamma ray emission, reception, data acquisition system, and the driving and control system of the scanning mobile measurement platform. mainly includes 137 Cs radioactive source 1, shielded lead tank 2, stepper motor 3, stepper motor mobile platform 4, guide rail 5, mobile slide table 6, controller 7, driver 8, 24V DC power supply 9, radioactive source side mobile bracket 10, connection Rod device 11, receiver side moving bracket 12, collimator 13, scintillation crystal detector 14, ray collector 15, industrial computer 16, steam generator cylinder 17, ste...

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Abstract

The invention discloses a device and a method for measuring section steam content of a tube bundle area of a steam generator. The measuring device comprises a gamma ray emitting and receiving device,a gamma ray scanning mobile measuring platform, a stepping motor driving and control system and a ray counting rate collecting system. Through a gamma ray scanning method, the section steam content onany chord length between secondary side tube bundles of the steam generator can be obtained continuously; and structure parameters and flow parameters of the steam generator are considered, and a calculation formula is corrected, so that complex geometrical structures of the tube bundles and different fluids on the primary and secondary sides can be distinguished accurately, and the difficult problem of measurement of the section steam content between the secondary side tube bundles of the steam generator is solved.

Description

technical field [0001] The invention relates to the technical field of two-phase flow measurement and reactor thermal hydraulics, in particular to a device and method for measuring the steam content ratio in the section of a tube bundle area of ​​a steam generator. Background technique [0002] As a device for heat exchange between the primary and secondary sides of a nuclear power plant, the steam generator plays a vital role in the entire nuclear power system, and its performance and reliability are directly related to the stable operation of the entire nuclear power plant. The damage of steam generator heat transfer tubes caused by vibration, corrosion, thermal fatigue and other factors has an important impact on the safety and reliability of nuclear power plants. Therefore, it is of great significance to study the boiling heat transfer and flow characteristics of the two-phase flow between the heat transfer tube bundles on the secondary side of the steam generator. [0...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01N23/06G01N23/12
CPCG01N23/06G01N23/12
Inventor 刘朝晖王腾随志强毕勤成
Owner XI AN JIAOTONG UNIV
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