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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
D. T. Raske, C. F. Cheng
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 101-110
Technical Paper | Material | doi.org/10.13182/NT77-A31834
Articles are hosted by Taylor and Francis Online.
The fatigue crack-growth behavior of Type 304 stainless-steel base metal and Type 308 stainless-steel weld metal at elevated temperature was investigated using axially loaded single-edge-notch specimens. The crack-growth rates were determined and are presented as a function of the stress-intensity factor range. Both the base- and weld-metal specimens were tested in the as-received (or as-welded) and thermally aged condition. The results indicate that the crack-growth rates in the weld metal are significantly lower than in the base metal. In addition, aging at 593°C for 1000 h improved the resistance to fatigue crack growth in both the base and weld metals.
