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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.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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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Fusion Science and Technology
November 2024
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.
C. Fagan, M. Sharpe, W. T. Shmayda, W. U. Schröder
Fusion Science and Technology | Volume 76 | Number 4 | May 2020 | Pages 424-429
Technical Paper | doi.org/10.1080/15361055.2020.1714409
Articles are hosted by Taylor and Francis Online.
The effect of a thin alumina coating on stainless steel 316 (SS316) samples on tritium adsorption and transport are reported. Compact films of alumina were produced on the surfaces of pristine SS316 samples using an atomic layer deposition (ALD) technique. Subsequently, these samples were exposed for 24 h to a deuterium-tritium gas mixture (PT = 0.5 atm, 25°C). A combination of methods including selective etching and programmed thermal desorption were employed to assess both the depth profile of the tritium concentration in the sample and the total quantity of tritium absorbed, respectively. Tritium was quantitatively determined through the measurement of beta radioactivity using liquid-scintillation counting techniques. Data suggest that SS316 with a thin film of alumina reduces the total tritium uptake by ~25% relative to uncoated samples. Importantly, such films appear to reduce, by a factor of 200, tritium diffusion into SS316 and therefore constitute an effective barrier against tritium transport. This observation is of practical importance for tritium and, generally, reactive gas handling.