SYMPOSIA PAPER Published: 01 January 1977
STP35592S

Acoustic Emission during Room Temperature Fatigue Crack Growth and Fracture of Zr-2.5Cb Alloy Specimens

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The objective of this investigation was to determine acoustic emission (AE) properties of unhydrided and hydrided Zr-2.5Cb during room temperature fatigue crack growth and fracture. Determination of AE behavior is important as a basis for continuous on-line monitoring in nuclear reactor pressure tubes fabricated from Zr-2.5Cb.

AE was monitored during mechanical loading of notched sheet specimens and during fatigue crack growth of simulated pressure-loaded axially notched tubular specimens. The tubular specimens involved mechanical loading within the tube which produced stress conditions similar to a free-end-cap, fluid-pressurized specimen. The sheet specimens showed AE characteristics related to the stress intensity factor, K, through the notch edge opening displacement and were unaffected by hydrogen level. The simulated pressure tubular specimen AE data were related by a power law to the fatigue crack: growth rate and may be affected by hydrogen level.

Pooling of water around an AE sensor did not alter the AE detected during fatigue loading. Addition of water and penetrating oil to a crack tip both produced significant increases in the indicated AE per load cycle.

The results of this investigation provided encouraging evidence of the feasibility of on-line monitoring of Zr-2.5Cb pressure tubing.

Author Information

Schwenk, EB
Battelle, Pacific Northwest Laboratories, Richland, Wash
Hutton, PH
Battelle, Pacific Northwest Laboratories, Richland, Wash
Igarashi, M
Power Reactor and Nuclear Fuel Development Corporation, Tokai Works, Ibaraki Ken, Japan
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Details
Developed by Committee: B10
Pages: 573–588
DOI: 10.1520/STP35592S
ISBN-EB: 978-0-8031-4705-8
ISBN-13: 978-0-8031-0602-4