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.
Helmut Elbel, José LóPez Jiménez
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 88-99
Technical Paper | Fuel | doi.org/10.13182/NT79-A16177
Articles are hosted by Taylor and Francis Online.
The heat transfer coefficient of the interface between the fuel and the cladding of fast reactor fuel rods with different burnups was derived through the analysis of the structure of the UO2-PUO2 fuel A decrease of the heat transfer with increasing burn-up was found, resulting in rising fuel surface temperatures. The predictions of a theoretical heat transfer model agreed well with the experimental result. The deterioration of the heat transfer could be explained by fission gas release into the residual gap between fuel and cladding. Heat transfer through contact spots played a negligible role due to low contact pressure and very early formation of an oxide layer on the cladding.