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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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
Siting of Canadian repository gets support of tribal nation
Canada’s Nuclear Waste Management Organization (NWMO) announced that Wabigoon Lake Ojibway Nation has indicated its willingness to support moving forward to the next phase of the site selection process to host a deep geological repository for Canada’s spent nuclear fuel.
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.