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Division Spotlight
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.
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
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
Anderson M. S. Alves, Adino Heimlich, Fernando Lamego, Celso M. F. Lapa
Nuclear Technology | Volume 207 | Number 2 | February 2021 | Pages 316-322
Technical Note | doi.org/10.1080/00295450.2020.1747840
Articles are hosted by Taylor and Francis Online.
The Argonaut reactor is a water-moderated research reactor that was designed by the Argonne National Laboratory. There are currently few reactors of this type under operating conditions in the world, one of which, located at the Nuclear Engineering Institute in Brazil, has been in operation since 1965. This study analyzes a nonpostulated accident caused by the collision of the reactor coverer into the core during crane manipulation. This event causes the release of particulate and volatile fission products into the reactor hall. Thus it was necessary to evaluate the isotopic inventory and the fuel burnup for more than 50 years of operation. These data are used to calculate the source term and the instantaneous dose at 1 m from the reactor core.