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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.
C. E. Annese, E. Greenspan
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 958-962
Fusion Diagnostic and Neutronic Experiment and Analysis | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40278
Articles are hosted by Taylor and Francis Online.
The computer time saving attainable by solving the transport equation for the higher neutron energy groups and the diffusion equation for the lower energy groups was investigated for fusion reactor safety applications. For the ARIES-I design considered, it was found that coupled diffusion-transport solutions can provide the activation rates in all the zones excluding the shield to within 2.5 % and 5 % when the transition to the diffusion approximation is, respectively, at 1.4 MeV and 8.8 MeV. The corresponding saving in CPU time relative to an all-transport solution is 31 % and 43 %. For the low order transport approximation used, this CPU time is significantly shorter than that required by ONEDANT, with its built-in diffusion synthetic acceleration.
