ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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May 2025
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.
Rikizo Watanabe
Nuclear Technology | Volume 66 | Number 1 | July 1984 | Pages 69-74
A. Selection, Production, and Development of Alloys for HTGR Component | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33456
Articles are hosted by Taylor and Francis Online.
A grain boundary precipitation treatment was studied for the purpose of improving the high-temper-ature low-cycle fatigue strength of a Ni-23% Cr- 18% W alloy, SSS113M, which had been developed as an intermediate heat exchanger material of very high temperature reactors and evaluated as the best alloy in the national R&D program of nuclear steelmaking in Japan. A conventional standard solution treatment of 1300°C × 1 h water quenched does not cause any grain boundary precipitation in SSS113M, but an additional heat treatment of 1250°C × 1 h causes discontinuous grain boundary precipitation of the alpha-tungsten phase. This grain boundary precipitation treatment results in two- to fivefold increases of low-cycle fatigue lives at 800°C as well as slight increases of the creep and stress rupture strength at 1000°C.
