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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.
Satoshi Konishi, Masahide Hara, Kenji Okuno
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 890-894
Fuel Cycle and Tritium Technology | doi.org/10.13182/FST96-A11963050
Articles are hosted by Taylor and Francis Online.
Electrolytic reactor that converts methane and water simultaneously to liberate hydrogen isotopes at very high conversion ratio was developed and tested. Addition of the second zirconia cell provides the capability of processing broad mixing ratio between water and methane by supplying or extracting oxygen. Combination of palladium permeation and electrolytic reactions was tested under reactor relevant tritium concentration in an integrated loop. Satisfactory processing of simulated plasma exhaust processing and tritium recovery was verified. Based on the result, a concept of the fuel processing system for fusion reactor is proposed and discussed.