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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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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.
Ik Kyu Park, Jong Hwan Kim, Seong Wan Hong
Nuclear Science and Engineering | Volume 176 | Number 3 | March 2014 | Pages 255-272
Technical Paper | doi.org/10.13182/NSE13-16
Articles are hosted by Taylor and Francis Online.
Heat losses, heat remnants, and solidified layer thickness were calculated using a single-sphere film-boiling model. Debris particles of the quenched TROI (Test for Real cOrium Interaction with water) experiments were the target of analyses. The single-sphere film-boiling model can provide the order of triggerability and exponential potential at fuel-coolant interactions of various melt materials. For the triggerability, a system with a small particle size and large thermal conductivity induces a larger heat loss and a more voided mixture, which means a less triggered system. The explosion potentials are dependent not upon the triggerability but upon the heat contents of the mixture melt particles that can participate in a steam explosion. The calculated solidified layer thickness ratio to the radius of the melt particle, defined as a fragility factor of a melt particle in this paper, also maintained consistency with the order of triggerability and was evaluated by the heat loss. The breakup sizes for various melt materials were analyzed with several types of breakup models. A dynamic breakup model to deal with transient velocities can explain the different breakup sizes of various melt materials.