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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Jean-Louis Bernard, Georges S. Slama
Nuclear Technology | Volume 59 | Number 1 | October 1982 | Pages 136-147
Technical Paper | Material | doi.org/10.13182/NT82-A33059
Articles are hosted by Taylor and Francis Online.
The need exists to define a fatigue crack growth design curve in an air environment for austenitic stainless steels in the temperature range of 300°C, which is the operating temperature range of pressurized water reactors. In the present study, elements to determine such a curve in a deterministic way are developed. In particular, effects of R ratio (Kmin/Kmax) are reviewed, and high R ratio tests, which were lacking, have been performed. To take into account R ratio effects, a relationship giving realistic predictions in accordance with high R ratio experiments is determined. A design curve, defined from a large compilation of results from several laboratories, allows a conservative calculation of all known fatigue crack growth tests on austenitic stainless steels in the temperature range of 300°C.
