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核电站反应堆压力容器接管安全端焊缝涡流检测

曾玉华, 陈霞, 王家建, 卢威, 陈胜宇

曾玉华, 陈霞, 王家建, 卢威, 陈胜宇. 核电站反应堆压力容器接管安全端焊缝涡流检测[J]. 无损检测, 2014, 36(10): 41-43.
引用本文: 曾玉华, 陈霞, 王家建, 卢威, 陈胜宇. 核电站反应堆压力容器接管安全端焊缝涡流检测[J]. 无损检测, 2014, 36(10): 41-43.
ZENG Yu-hua, CHEN Xia, WANG Jia-jian, LU Wei, CHEN Sheng-yu. Eddy Current Test of the Safe End Welds of Nuclear Power Plant Reactor Pressure Vessel[J]. Nondestructive Testing, 2014, 36(10): 41-43.
Citation: ZENG Yu-hua, CHEN Xia, WANG Jia-jian, LU Wei, CHEN Sheng-yu. Eddy Current Test of the Safe End Welds of Nuclear Power Plant Reactor Pressure Vessel[J]. Nondestructive Testing, 2014, 36(10): 41-43.

核电站反应堆压力容器接管安全端焊缝涡流检测

详细信息
    作者简介:

    曾玉华(1980-), 男, 工程师, 主要从事核设备无损检验技术研究和检查工作。

  • 中图分类号: TL4; TG115.28

Eddy Current Test of the Safe End Welds of Nuclear Power Plant Reactor Pressure Vessel

  • 摘要: 介绍了核电站反应堆压力容器接管安全端焊缝涡流检测方法, 通过试验提出了对接管安全端焊缝运用点探头C扫的涡流检测方法, 以及表面缺陷的准确测长方法, 可弥补在接管安全端焊缝超声检查方法的不足。
    Abstract: Eddy current test technique for nuclear power plant reactor pressure vessel safe end welds was introduced in this paper. C-scan eddy current test technique with point probe was proposed for inspecting the safe end welds of reactor pressure vessel, supplemented with measuring surface defect length to assist the ultrasonic testing of the safe end welds.
  • [1] DIAZ A A, MATHEWS R A, HIXON J, et al. Assessment of eddy current testing for the detection of cracks in cast stainless steel reactor piping components[R], U.S: Nuclear Regulatory Commission, 2007.
    [2] 国防科技工业无损检测人员资格鉴定与认证培训教材编审委员会.涡流检测[M].北京: 机械工业出版社, 2004: 24-48.
    [3] 刘洪杰.核电站核承压设备用刚剖析[J].东方锅炉, 2008, 22(8): 23-27.
    [4] 与聪.316L不锈钢性能[EB/OL].[2014-4-14].http: //wenku.baidu.com/Link.
    [5] ANDERSON M T, CRAWFORD S L, CUMBLIDGE S E, et al. Assessment of crack detection in heavy-walled cast stainless steel piping welds using advanced low-frequency ultrasonic methods[R]. U.S: Nuclear Regulatory Commission, 2007.
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出版历程
  • 收稿日期:  2014-03-19
  • 刊出日期:  2014-10-09

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