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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.
W. Chubb, A. C. Hott, B. M. Argall, G. R. Kilp
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 486-495
Technical Paper | Material | doi.org/10.13182/NT75-A24449
Articles are hosted by Taylor and Francis Online.
Early in 1972, confirmation was obtained that gaps observed in the columns of fuel pellets in the cores of several pressurized water reactors were the result of densification of the fuel during operation. The implications of these gaps with regard to fuel rod integrity and reactor safety stimulated a substantial effort to understand in-pile densification at low temperatures and to provide corrective action. Data obtained in the course of irradiation and by postirradiation examinations have disclosed that in-pile densification is controlled by the microstructure of the fuel, particularly its pore size distribution and porosity. These factors, in turn, were found to be controlled by fabrication parameters of which the sintering conditions were most important. The background, data, and theory of densification are reviewed. As a consequence, appropriate controls have been placed on fuel density, microstructure, and sintering conditions to reduce in-pile densification to insignificant levels.