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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.
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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
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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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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.
S. Welte, E. Fanghänel, S. Fischer, F. Kramer, T. L. Le, M. Sturm, N. Tuchscherer
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 316-320
Technical Paper | doi.org/10.1080/15361055.2017.1291233
Articles are hosted by Taylor and Francis Online.
One of the main tasks of the Tritium Laboratory Karlsruhe (TLK) is the operation of the Windowless Gaseous Tritium Source (WGTS) of the Karlsruhe Tritium Neutrino (KATRIN) experiment, which will perform an absolute measurement of the neutrino mass with a sensitivity of 200 meV/c2 (90% confidence level). While the Inner Loop system of KATRIN provides a stabilized tritium throughput of 40 g day−1 in the WGTS, the outer loop is required for tritium clean-up, purification, and accountancy.
The ability of the outer loop to supply tritium has been investigated using feed gas samples of different compositions. This paper will describe the gas processing tests which were done with batches of approximately 1 mol of tritium each and 20 mol in total, processed on a day-to-day basis in the TLK tritium loop. It is shown, that an isotopic tritium purity of > 98% can reliably supplied to the KATRIN experiment. This is sufficient to maintain the required isotopic tritium purity of > 95% in the KATRIN inner loop.