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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
W. Kernbichlerb, G. H. Miley, M. Heindler
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 1142-1147
Alternate Fuels and Innovative Confinement Concept | doi.org/10.13182/FST89-A39847
Articles are hosted by Taylor and Francis Online.
The intrinsic potential of D-3He as a reactor fuel is investigated for a large range of 3He to D density ratios. A steady-state zero-dimensional reactor model is developed in which much care is attributed to a proper treatment of fast fusion products. Useful ranges of reactor parameters as well as temperature-density windows for driven and ignited operation are identified. Various figures of merit are calculated, such as power densities, net power production, neutron production, tritium load and radiative power. These results suggest several optimistic conclusions about the performance of D-3He as a reactor fuel. aSupported by Fonds zur Foerderung der wissenschaftlichen Forschung, Bundeswirtschaftskammer and Friedrich Schiedel-Stiftung, Austria, Internat. Atomic Energy Agency, Vienna, and US DOE contract No. DEFG02-86ER52127. bPermanent address: Alternate Energy Physics Program, Institute for Theoretical Physics, Graz University of Technology, Austria
