Evaluation of methods for leak detection in reactor primary systems and NDE of cast stainless steel

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Six cracks, including two field-induced IGSCC specimens and two thermal-fatigue cracks, have been installed in a laboratory acoustic leak detection facility. The IGSCC specimens produce stronger acoustic signals than the thermal-fatigue cracks at equivalent leak rates. Despite significant differences in crack geometry, the acoustic signals from the two IGSCC specimens, tested at the same leak rate, are virtually identical in the frequency range from 200 to 400 kHz. Thus, the quantitative correlations between the acoustic signals and leak rate in the 300 to 400 kHz band are very similar for the two IGSCC specimens. Also, acoustic background data have been ... continued below

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Pages: 21

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Kupperman, D.S.; Claytor, T.N.; Prine, D.W. & Mathieson, T.A. January 1, 1984.

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Description

Six cracks, including two field-induced IGSCC specimens and two thermal-fatigue cracks, have been installed in a laboratory acoustic leak detection facility. The IGSCC specimens produce stronger acoustic signals than the thermal-fatigue cracks at equivalent leak rates. Despite significant differences in crack geometry, the acoustic signals from the two IGSCC specimens, tested at the same leak rate, are virtually identical in the frequency range from 200 to 400 kHz. Thus, the quantitative correlations between the acoustic signals and leak rate in the 300 to 400 kHz band are very similar for the two IGSCC specimens. Also, acoustic background data have been acquired during a hot functional sensitivity of acoustic leak detection techniques. In addition, cross-correlation techniques have been successfully used in the laboratory to locate the source of an electronically simulated leak signal.

Physical Description

Pages: 21

Notes

NTIS, PC A02/MF A01 - GPO.

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  • 12. water reactor safety research information meeting, Gaithersburg, MD, USA, 23 Oct 1984

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  • Other: TI85005056
  • Report No.: CONF-8410142-76
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 6021020
  • Archival Resource Key: ark:/67531/metadc1098277

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Office of Scientific & Technical Information Technical Reports

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  • January 1, 1984

Added to The UNT Digital Library

  • Feb. 18, 2018, 3:59 p.m.

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  • Feb. 26, 2018, 3:48 p.m.

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Kupperman, D.S.; Claytor, T.N.; Prine, D.W. & Mathieson, T.A. Evaluation of methods for leak detection in reactor primary systems and NDE of cast stainless steel, article, January 1, 1984; United States. (digital.library.unt.edu/ark:/67531/metadc1098277/: accessed November 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.