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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
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Stephen T. Lam, John Stempien, Ronald Ballinger, Charles Forsberg
Fusion Science and Technology | Volume 71 | Number 4 | May 2017 | Pages 644-648
Technical Note | doi.org/10.1080/15361055.2017.1290945
Articles are hosted by Taylor and Francis Online.
Research characterizing hydrogen behavior on carbon has been primarily focused on collecting data at near-ambient temperatures and pressures for storage or for high volume applications such as fusion. Transport models of a pre-conceptual 236 MWt pebble-bed fluoride-salt-cooled, high-temperature reactor (PB-FHR) estimate that the production of tritium is relatively low resulting in partial pressures ranging between 0 and 20 Pa. Operating temperatures in an FHR range from 600 to 700°C. Under these operating conditions, the interaction between hydrogen and carbon is currently undefined. Since an FHR contains large quantities of carbon (reflectors, fuel, structures), the tritium behavior in carbon must be investigated in order to develop methods to control tritium release rates to the environment and material corrosion. Preliminary modeling and experiments demonstrate high performance is achieved in a carbon adsorption tower, which can reduce system release rates by greater than 99%. This research aims to (1) accurately measure hydrogen uptake and kinetics on different types of carbon at prototypic conditions and (2) use tritium transport modeling to demonstrate the potential of carbon materials for tritium capture and control.