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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.
Afiqa Mohamad, Yutaka Udagawa
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 245-260
Research Article | doi.org/10.1080/00295450.2023.2185061
Articles are hosted by Taylor and Francis Online.
In the Power to Melt and Maneuverability (P2M) project, a simulation exercise on two past power ramp experiments, xM3 on a medium-burnup rod and HBC4 on a high-burnup rod, was performed with the fuel performance code FEMAXI-8 to investigate fuel behavior under high-power and high-temperature conditions toward centerline fuel melting. In order to treat fuel melting, empirical melting temperature models have been incorporated into the FEMAXI-8 code. The present analysis gives reasonable predictions not only on cladding deformation but also on the fuel melting behavior of the HBC4 rod in which the UO2 liquidus temperature was reached during the transient. On the other hand, model improvement appears to be needed for a more accurate treatment of the fuel melting behavior of the xM3 rod in which the fuel center temperature reached the solidus line, whereas it may have not reached the liquidus line. A reasonable agreement of estimated fission gas release (FGR) with the measurement suggested that the high-temperature FGR at the given conditions is essentially a temperature-dependent phenomenon rate limited primarily by thermally activated elementary processes, such as fission gas diffusion.