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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
David A. White, Fathurrachman
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 220-227
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT95-A35119
Articles are hosted by Taylor and Francis Online.
The methodology necessary to design a solvent extraction plant for isotope separation by chemical exchange is outlined. This process involves the calculation of the number of stages used in banks of mixer settlers used in such a plant. The feed is introduced at both ends of the plant, and the product is withdrawn at one end and the tailings at another. The resulting analysis, illustrated for the case of uranium enrichment, produces a fairly simple algorithm, and then more complicated configurations are examined. The method of design can be used for other systems where the isotope separation factors are more favorable.
