Evaluation of Weldment Creep and Fatigue Strength-Reduction Factors for Elevated-Temperature Design

[+] Author and Article Information
J. M. Corum

Oak Ridge National Laboratory, Oak Ridge, TN 37831

J. Pressure Vessel Technol 112(4), 333-339 (Nov 01, 1990) (7 pages) doi:10.1115/1.2929886 History: Received December 01, 1989; Revised May 08, 1990; Online June 17, 2008


New explicit weldment strength criteria in the form of creep and fatigue strength-reduction factors were recently introduced into the American Society of Mechanical Engineers Code Case N-47, which governs the design of elevated-temperature nuclear plant components in the United States. This paper provides some of the background and logic for these factors and their use, and it describes the results of a series of confirmatory creep-rupture and fatigue tests of simple welded structures. The structures (welded plates and tubes) were made of 316 stainless steel base metal and 16-8-2 weld filler metal. Overall, the results provide further substantiation of the validity of the strength-reduction factor approach for ensuring adequate life in elevated-temperature nuclear component weldments.

Copyright © 1990 by The American Society of Mechanical Engineers
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