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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
Yoshi Hirooka, Haishan Zhou
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 63-69
Technical Paper | doi.org/10.13182/FST13-777
Articles are hosted by Taylor and Francis Online.
The first wall of a magnetic fusion DEMO reactor serves to separate the edge plasma from breeding blanket, the latter of which is required to operate at elevated temperatures. To minimize the thermo-mechanical stress, the wall thickness is often limited to be less than 1 cm. As a result, the first wall is subjected to hydrogen isotopes permeation in the two opposite directions via plasma-driven permeation (PDP) by D+ (or D0) and T+ (or T0) in the edge plasma region and via gas-driven permeation (GDP) by T2 bred in the blanket. In the present work, the bi-directional hydrogen permeation behavior through a candidate first wall material, F82H, has been studied, using a laboratory-scale plasma device. Experimental data indicate that GDP tends to dominate the overall hydrogen isotopes transport. The effects of surface roughness and contamination on PDP have been investigated. Also, a one-dimensional diffusion code has been used to simulate bi-directional PDP and GDP under reactor-relevant conditions where multiple hydrogen isotopes flow through the first wall.