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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Empowering the next generation: ANS’s newest book focuses on careers in nuclear energy
A new career guide for the nuclear energy industry is now available: The Nuclear Empowered Workforce by Earnestine Johnson. Drawing on more than 30 years of experience across 16 nuclear facilities, Johnson offers a practical, insightful look into some of the many career paths available in commercial nuclear power. To mark the release, Johnson sat down with Nuclear News for a wide-ranging conversation about her career, her motivation for writing the book, and her advice for the next generation of nuclear professionals.
When Johnson began her career at engineering services company Stone & Webster, she entered a field still reeling from the effects of the Three Mile Island incident in 1979, nearly 15 years earlier. Her hiring cohort was the first group of new engineering graduates the company had brought on since TMI, a reflection of the industry-wide pause in nuclear construction. Her first long-term assignment—at the Millstone site in Waterford, Conn., helping resolve design issues stemming from TMI—marked the beginning of a long and varied career that spanned positions across the country.
D. L. Dunaway, G. P. Miller, W. A. Johnson
Nuclear Technology | Volume 8 | Number 6 | June 1970 | Pages 482-487
Fuel Cycle | doi.org/10.13182/NT70-A28647
Articles are hosted by Taylor and Francis Online.
A study was initiated to determine the highest 235U enrichment that could be processed safely in a facility originally designed for refining natural uranium ores and concentrates. The equipment used in converting uranyl nitrate to uranium trioxide was determined to be the limiting factor. Calculations of neutron multiplication throughout the denitration cycle were made using data from the analysis of process material. It was determined that the maximum 235U enrichment could be safely increased to 2.0% from the previous limit of 1.25% 235U. Processing at the higher enrichment required slight changes in equipment to ensure against moderation of the material.