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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
Melville A. Feraday, Moon T. Foo, Ross D. Davidson, John E. Winegar
Nuclear Technology | Volume 58 | Number 2 | August 1982 | Pages 233-241
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32934
Articles are hosted by Taylor and Francis Online.
The stability of Al-USiAl dispersion fuels and Al-U alloys was examined at temperatures between 200 and 400°C for times up to 93 days. The Al-U alloys, which contained 21 to 37 wt% uranium, did not show any dimensional or metallurgical changes after 93 days at 400°C. After being heated at 200°C, the Al-USiAl fuel showed no dimensional or metallurgical changes. However, between 250 and 400°C, the USiAl particles reacted with the aluminum matrix to form UAl3 and UAl4. The amount of reaction increased with temperature and time. The aluminum diffuses into the USiAl particles along grain boundaries to form the new Al-U compounds. Although the Al-USiAl fuel showed thermal instability at 250°C and above, the in-reactor behavior under normal operation is expected to be satisfactory since fuel temperatures will generally be <200°C.