Published August 2010 | Version v1
Journal article

Detection and mode identification of axial cracks in the steam generator tube of the nuclear power plant using ultrasonic guided wave

  • 1. Korea Electric Power Research Inst., Daejeon (Korea, Republic of)

Description

For those people who are involved in NDE, there is a growing concern regarding the significant traveling distance of a guided wave in a structure, which ensures the inspection of a large area of the structure from a single location. A significant number of studies on the guided wave have therefore been made to apply the foregoing to a nondestructive evaluation in many different industries and resulted in an increase in the efficiency of practical guided wave inspection. Unlike the previous studies based mainly on the detection of circumferential flaws, this study is focused on the axial flaw detection in the steam generator tubes of Korean standard nuclear power plants by generating the guided wave by changing frequency and selecting the applicable mode from the dispersion curve for the steam generator tube calculated in this study, where the dispersion-based short-time Fourier transform (D-STFT) algorithm is used to enhance mode identification. In conclusion, the L (0,1) mode at 2.25 MHz is found to be most sensitive in detecting axial flaws in a steam generator tube. (author)

Availability note (English)

Available from http://dx.doi.org/10.3327/jnst.47.754

Additional details

Identifiers

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo)
Journal Volume
47
Journal Issue
8
Journal Page Range
p. 754-759
ISSN
0022-3131

Optional Information

Notes
6 refs., 8 figs., 4 tabs.