Evaluation of methods for leak detection in reactor primary systems and NDE of cast stainless steel [electronic resource].
- Published
- Argonne, Ill. : Argonne National Laboratory, 1984.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 21 : digital, PDF file
- Additional Creators
- Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- 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.
- Report Numbers
- E 1.99:conf-8410142-76
conf-8410142-76 - Subject(s)
- Other Subject(s)
- Acoustic Testing
- Pipes
- Cracks
- Pwr Type Reactors
- Steam Systems
- Fatigue
- Leak Testing
- Stainless Steels
- Stress Corrosion
- Alloys
- Chemical Reactions
- Chromium Alloys
- Corrosion
- Corrosion Resistant Alloys
- Energy Systems
- Iron Alloys
- Iron Base Alloys
- Materials Testing
- Mechanical Properties
- Nondestructive Testing
- Reactors
- Steels
- Testing
- Water Cooled Reactors
- Water Moderated Reactors
- Note
- Published through SciTech Connect.
01/01/1984.
"conf-8410142-76"
"TI85005056"
12. water reactor safety research information meeting, Gaithersburg, MD, USA, 23 Oct 1984.
Claytor, T.N.; Kupperman, D.S.; Prine, D.W.; Mathieson, T.A. - Funding Information
- W-31-109-ENG-38
View MARC record | catkey: 14802107