Published February 1980 | Version v1
Journal article

Ultrasonic inspection of liquid-metal fast breeder reactor steam generator duplex tubing

  • 1. Argonne National Lab., Idaho Falls

Description

Two ultrasonic inspections of the Experimental Breeder Reactor II steam generator duplex tubing have been completed. Inspections performed on one evaporator in 1976 provided baseline data, and a subsequent inspection in 1978 revealed no change in tube condition. With the completion of the 1978 inspection, all available tubes in one evaporator have been inspected. The steam generator contains duplex tubes fabricated from 2 1/4 Cr-1 Mo ferritic steel. Access to the bore (water) side of the tubes was gained through the steam outlet piping. The inspection included a complete volumertic (100% of the tube material) examination, measurement of wall thickness, and evaluation of the condition of the braze bonding the two walls of the tube together. The test equipment was routinely calibrated against a standard containing artificial flaws. Artificial flaws as small as 1.6 mm long x 0.25 mm deep were readily detected

Additional details

Publishing Information

Journal Title
Nucl. Technol.
Journal Volume
47
Journal Issue
2
Series
Nucl. Technol.
Journal Page Range
257-267
ISSN
0029-5450