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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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A webinar, and a new opportunity to take ANS’s CNP Exam
Applications are now open for the fall 2025 testing period for the American Nuclear Society’s Certified Nuclear Professional (CNP) exam. Applications are being accepted through October 14, and only three testing sessions are offered per year, so it is important to apply soon. The test will be administered from November 12 through December 16. To check eligibility and schedule your exam, click here.
In addition, taking place tomorrow (September 19) from 12:00 noon to 1:00 p.m. (CDT), ANS will host a new webinar, “How to Become a Certified Nuclear Professional.” More information is available below in this article.
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.