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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.
Jungchung Jung, John V. Foley
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 1998-2009
Technical Paper | Blanket Comparison and Selection Study | doi.org/10.13182/FST85-A24575
Articles are hosted by Taylor and Francis Online.
Three-dimensional, tritium breeding, and energy multiplication analyses were performed for nine tandem mirror reactor (TMR) designs and seven tokamak reactor designs that had evolved as the “rank-1” concept from the latest Blanket Comparison and Selection Study. These designs include a variety of combinations of candidate breeder, coolant, and structural materials that seem most promising for the respective TMR/tokamak concept application. The analysis was performed using a single consistent computational technique, i.e., a continuous energy Monte Carlo transport method based on MCNP with the associated cross-section libraries based on the latest ENDF/B-V data. Through a comparative study of those 16 candidate blanket designs, an attempt is made to rank them from a standpoint of the neutronic blanket performance.