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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.
Roberto Bovalini, Francesco D’Auria, Antonio De Varti, Piero Maugeri, Marino Mazzini
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 113-130
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34630
Articles are hosted by Taylor and Francis Online.
The main results obtained at the University of Pisa on small-break loss-of-coolant accident counterpart experiments carried out in boiling water reactor (BWR) experimental simulators are summarized. In particular, the results of similar experiments performed in the PIPER-ONE, Full Integral Simulation Test (FIST), and ROSA-III facilities are analyzed. The tests simulate a transient originated by a small break in the recirculation line of a BWR-6 with the high-pressure injection systems unavailable. RELAP5/MOD2 nodalizations have been set up for these facilities and for the reference BWR plant. The calculated results are compared among each other and with the experimental data. Finally, the merits and the limitations of such a program are discussed in view of the evaluation of code scaling capabilities and uncertainty.
