The elevated temperature mechanical properties of large diameter (28 in.) seamless pipe produced by roll extrusion for use as primary piping for sodium coolant in the Fast Flux Test Facility (FFTF) have been characterized. The three heats of type 316H stainless steel piping material used in this study exhibited very consistent mechanical properties and chemical compositions. Tensile and creep-rupture properties exceed values on which the allowable stresses for ASME Code Case 1592 on Nuclear Components in Elevated Temperature Service were based. Tensile strength and ductility were essentially unchanged by aging in static sodium at 1050°F (566°C) for times to 10,000 hr. High strain rate tensile tests showed that tensile properties were insensitive to strain rate at temperatures to 900°F (482°C) and that for temperatures of 1050°F (566°C) and above both strength and ductility significantly increased with increasing strain rate. Fatigue-crack propagation properties were comparable to results obtained on plate material and no differences in crack propagation were found between axial and circumferential orientations.
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Mechanical Properties of Roll Extruded Nuclear Reactor Piping
J. M. Steichen,
J. M. Steichen
Westinghouse Hanford Co., Richland, Wash.
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R. L. Knecht
R. L. Knecht
Westinghouse Hanford Co., Richland, Wash.
Search for other works by this author on:
J. M. Steichen
Westinghouse Hanford Co., Richland, Wash.
R. L. Knecht
Westinghouse Hanford Co., Richland, Wash.
J. Pressure Vessel Technol. May 1976, 98(2): 105-110 (6 pages)
Published Online: May 1, 1976
Article history
Received:
April 2, 1975
Online:
October 25, 2010
Citation
Steichen, J. M., and Knecht, R. L. (May 1, 1976). "Mechanical Properties of Roll Extruded Nuclear Reactor Piping." ASME. J. Pressure Vessel Technol. May 1976; 98(2): 105–110. https://doi.org/10.1115/1.3454346
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