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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
H. O. Schad, A. A. Bishop
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 261-275
Paper | Fuel | doi.org/10.13182/NT70-A28673
Articles are hosted by Taylor and Francis Online.
Experiments were conducted to determine the behavior of stationary gas bubbles in narrow liquid-filled gaps. The work was carried out to help answer the question of how fission gas bubbles may behave in the sodium bond of oxide and carbide fueled rods. The hydraulic data obtained with uncracked pellets indicate that stagnant bubbles may exist even when the simulated fuel rod was vibrated. These stagnant bubbles are large enough to cause calculated hot spots in the bond. The location under an overhanging ledge formed by axial eccentric pellets was a common place for bubbles to stagnate. Possible differences between the actual fuel-rod behavior in the reactor and the test conditions may be caused by heating effects which influence bubble motion, cracked pellets which prevent accumulation of fission gas in the bonding, and the release of significant amounts of fission gas only when the reactor is shut down. Equations are presented for the maximum bubble size, and the length and width of bubbles stagnated at the lips (overhang) of fuel pellets.