Acoustic emission/flaw relationship for in-service monitoring of nuclear pressure vessels. Quarterly report, October 1983-March 1984. Volumes 1 and 2
This report describes technical progress on a program to apply acoustic emission for continuous integrity surveillance of nuclear reactor pressure boundaries. The period is October 1983 to March 1984. Test data from the completed intermediate scale vessel (ZB-1) test is being analyzed to isolate AE from crack growth for the purpose of refining AE signal identification and AE interpretation methods. Fatigue crack growth in the ZB-1 vessel is being characterized by destructive examination. Acoustic data obtained from the No. 2 inlet nozzle during hot functional testing at Watts Bar Unit 1 reactor showed a source concentration. A cooperative effort between TVA and PNL is planned to evaluate the significance of the data. Identification of crack growth AE by pattern recognition is showing much improved results. Fatigue testing of A106B ferritic pipe material is showing mixed AE results related to previous relationships developed for A533B steel. Development of an ASTM Standard Practice for continuous AE monitoring of pressure boundaries has been initiated. A NUREG document on results from AE monitoring at Watts Bar, Unit 1 reactor during hot functional testing has been completed.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6698321
- Report Number(s):
- NUREG/CR-3825-Vol.1-2; PNL-5125-Vol.1-2; ON: DE84015039
- Country of Publication:
- United States
- Language:
- English
Similar Records
Acoustic emission/flaw relationship for in-service monitoring of nuclear pressure vessels. Quarterly report, April-September 1984. Volumes 3, 4
Acoustic emission/flaw relationship for in-service monitoring of nuclear pressure vessels. Progress report, October 1984-March 1985. Volume 1
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