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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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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
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.
E. Carella, C. Moreno, F. R. Urgorri, D. Demange, J. Castellanos, D. Rapisarda
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 357-362
Technical Paper | doi.org/10.1080/15361055.2017.1289584
Articles are hosted by Taylor and Francis Online.
Tritium behavior in a breeding blanket is a key design issue because of its impact on safety and fuel self-sufficiency best performance. Considering the difficulty in handling and its high cost, it is intended to prepare a simulation tool for tritium transport in the HCPB (Helium Cooled Pebble Bed) breeder blanket unit concept. The objective of this work is to evaluate tritium inventory inside several components of the breeder unit (pebble bed and purge gas) and its permeation into the coolant. Some simplified assumptions have been adopted and the results compared with others studies obtained by different simulation tools. Finally an example in which different experimental values of tritium residence time in ceramic breeder is presented with the purpose to observe the capability of the program to be integrated with experimental campaigns.
