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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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Latest News
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.
D. C. Baxter, A. E. Dabiri, J. E. Glancy, W. K. Hagan
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 599-602
Fusion System Studies | doi.org/10.13182/FST83-A22927
Articles are hosted by Taylor and Francis Online.
A tokamak reactor systems code has been developed by combining a previously developed plasma engineering code with an existing reactor systems code and adding calculations for thermal hydraulics, stress analysis, physical sputtering, and neutron activation dose rate. Calculations from the thermal hydraulics and neutron activation dose rate modules are compared with results from more complex codes. The effects on reactor performance of unpredictable properties such as plasma profiles and confinement times are demonstrated.
