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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.
Seong-Wan Hong, Sang Ho Kim, Rae-Joon Park
Nuclear Technology | Volume 206 | Number 3 | March 2020 | Pages 401-413
Technical Paper | doi.org/10.1080/00295450.2019.1654816
Articles are hosted by Taylor and Francis Online.
In the postulated severe accidents of nuclear power plants, the interaction mode of the molten corium with water happens differently depending on the height of the water level in the reactor cavity. The interaction of the molten corium with the partially filled water in the reactor cavity has been extensively studied. The molten corium in this case was released into the water after free falling to some distance. Meanwhile, some advanced reactors have adapted the in-vessel corium retention concept by cooling the reactor vessel’s outside wall. If a reactor vessel failure happens in this case, the molten corium in the reactor vessel is injected directly into the water without any free fall. Triggered steam explosion experiments were carried out to compare the explosion behavior conditions of the partially flooded cavity and ex-vessel cooling. It was found that the jet breakup process before the explosion appeared differently between the two experiments. These behaviors contributed to the differences in the maximum dynamic pressure and load that express the explosion’s strength. The explosion’s strength under the partially flooded cavity condition was about two times stronger than that under ex-vessel cooling. Accordingly, it is believed that the steam explosions under conditions of ex-vessel cooling are of less concern than the partially flooded cavity condition.