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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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ANS Student Conference 2025
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Albuquerque, NM|The University of New Mexico
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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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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
W. M. Stacey
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 719-726
Technical Paper | The Technology of Fusion Energy - Nonelectric Applications | doi.org/10.13182/FST07-A1575
Articles are hosted by Taylor and Francis Online.
A series of design scoping and fuel cycle studies for sub-critical fast transmutation reactors driven by tokamak fusion neutron sources has been carried out to determine if the requirements on the tokamak neutron sources are compatible with the fusion physics and technology design database that will exist after the operation of ITER and to determine if there is a significant advantage in fuel cycle flexibility due to sub-critical operation that would justify the additional cost and complexity of a fusion neutron source. The fast reactor technologies are based on reactor concepts being developed in the DoE Generation-IV and Advanced Fuel Cycle initiatives.