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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
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Rudolf Avenhaus, Gert Spannagel
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1003-1008
Analysis and Accountancy | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30537
Articles are hosted by Taylor and Francis Online.
Principles of material accountancy are presented for a typical tritium fuel cycle under special consideration of the in-vessel inventory which for the time being can only be estimated roughly. For this purpose we pursue the selection and testing of suitable algorithms: For the process simulation we apply the stochastic version of the Karlsruhe Tritium Model. It is demonstrated that with the help of statistical methods which have been developed three years ago for the purpose of nuclear material safeguards, the measured data can be analyzed such that questions put forward by the operator as well as the licensing authority can be answered.