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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.
G. Bandyopadhyay
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 62-78
Technical Paper | Fuel | doi.org/10.13182/NT78-A26700
Articles are hosted by Taylor and Francis Online.
To evaluate the role of fission gas in hypothetical core disruptive accidents, experimental and analytical information describing the fission gas behavior in rapid temperature transients is urgently needed. In the present work, a direct-electrical-heating apparatus was used to obtain information on the fission gas behavior and the response of mixed-oxide fuel elements to simulated thermal transient conditions. The experimental results indicate that fission gas response and swelling behavior are strongly dependent on the transient heating rate, and that fission gas can contribute significantly to the failure of a fuel stack during a temperature transient. The microstructural results from these tests were subsequently used to perform a limited verification of the fission gas release and swelling code, FRAS, which was developed to describe the fission gas release behavior in rapid temperature transients. A comparison of the measured intragranular bubble sizes (and in some cases bubble densities) with the calculated bubble sizes (and densities) revealed that the current version of the FRAS code is inadequate in some transient conditions. A nonequilibrium analysis of bubble coalescence may be necessary to describe the fission gas behavior in such temperature transients.
