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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.
S. Chatzidakis, A. Ikonomopoulos, S. E. Day
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 119-131
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13332
Articles are hosted by Taylor and Francis Online.
This study presents numerical modeling of the SPERT-IV D-12/25 tests, a series of reactivity insertion, self-limiting, transients for a variety of coolant flow conditions. The PARET-ANL code is used to simulate the system response under these reactivity-initiated accident conditions and estimate the measured damage-indicating parameters - including the cladding temperature - using three departure from nucleate boiling (DNB) correlations, namely, those of Tong, Mirshak, and Bernath. The main objective of this sensitivity analysis is to identify, through performance measures, the DNB correlation influence on the prediction of the transient behavior. It appears that for reactivity insertions >1.20 $, the predicted transient behavior varies significantly depending on the applied DNB correlation. In addition, this study discusses the degree of conservatism introduced by each DNB correlation in the peak clad temperature estimates.
