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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
J. R. Easoz, R. Bajaj, R. E. Gold, J. W. H. Chi
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 780-784
Blanket and First Wall Engineering | doi.org/10.13182/FST83-A22955
Articles are hosted by Taylor and Francis Online.
This paper reports work performed under Program Element I (PE-I) of the First Wall, Blanket, and Shield Program, the principal objectives of which are the testing of first wall design concepts to support the design of fusion reactor first walls and the verification of analytical techniques and design tools. The test facility, ESURF, consists of a 36 kW continuous duty electron beam, evacuated target chamber, and a 6.9 MPa water loop for active cooling of test pieces. Long pulse “steady state” surface heat loads are simulated by rastering the beam in two dimensions, while disruption heat loads are simulated by imposing a focused, stationary beam for a fixed length of time on the target area. Initial test pieces consisted of stainless steel (Type 316) tubes. Tests to date have included thermal-hydraulic characterization of the specimens, thermal cycling up to 500 cycles, disruption heat load simulations, and combined disruption heat loads with thermal cycling. The test results reported here address the verification of predicted thermomechanical response of the specimens, the effects of disruption heat loads on surface melting and crack formation, and the affect of thermal cycling on crack formation/propagation.