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蒸汽发生器螺旋传热管超声导波检测技术研究与展望

方志泓 徐安 王理博

核安全2025,Vol.24Issue(3):42-49,8.
核安全2025,Vol.24Issue(3):42-49,8.

蒸汽发生器螺旋传热管超声导波检测技术研究与展望

Research and Prospect of Ultrasonic Guided Wave Testing Technology for Helical Heat Exchange Tubes of Steam Generator in High Temperature Gas-Cooled Reactor

方志泓 1徐安 2王理博1

作者信息

  • 1. 西安热工研究院有限公司,西安 710032
  • 2. 华能山东石岛湾核电有限公司,荣成 264300
  • 折叠

摘要

Abstract

As one of the fourth generation of advanced nuclear power reactors,the heat exchange tubes of the steam generator(SG)of high temperature gas-cooled reactor adopts helical tube assembly structure,and its material,specifications,manufacturing process and layout methods are different from those of traditional pressurized water reactors,resulting in the current commonly used eddy current and ultrasonic detection methods cannot be implemented.To solve this problem,based on ultrasonic guided wave technology,this paper proposes an in-service detection method for helical heat exchange tubes of SG in high temperature gas-cooled reactor.It expounds the technical principle of implementing ultrasonic guided wave detection of this type of heat exchange tubes,and analyzes the structural characteristics and detection difficulties of this type of heat exchange tubes in detail.An automatic ultrasonic guided wave detection system for this type of heat exchange tubes is established and tested.The experimental results indicate that the detection distance of ultrasonic guided waves can cover the entire length of SG heat transfer tubes and effectively identify long-distance defects inside the tubes.Furthermore,in order to implement this technology,it is still necessary to improve its capability verification work from aspects such as sample tube defect processing,parametric test-ing,quantitative evaluation of defects,and inspection procedures and standards.

关键词

高温气冷堆/蒸汽发生器/螺旋传热管/超声导波/在役检测

Key words

high temperature gas-cooled reactor/steam generator/helical heat exchange tubes/ultrasonic guided wave/in-service detection

分类

核科学

引用本文复制引用

方志泓,徐安,王理博..蒸汽发生器螺旋传热管超声导波检测技术研究与展望[J].核安全,2025,24(3):42-49,8.

基金项目

华能集团总部科技项目,项目编号:HNKJ20-H13 ()

核安全

1672-5360

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