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RESEARCH PAPERS

Mechanical Properties of Roll Extruded Nuclear Reactor Piping

[+] Author and Article Information
J. M. Steichen, R. L. Knecht

Westinghouse Hanford Co., Richland, Wash.

J. Pressure Vessel Technol 98(2), 105-110 (May 01, 1976) (6 pages) doi:10.1115/1.3454346 History: Received April 02, 1975; Online October 25, 2010

Abstract

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.

Copyright © 1976 by ASME
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