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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.
L. Crosatti, J. B. Weathers, D. L. Sadowski, S. I. Abdel-Khalik, M. Yoda, R. Kruessmann, P. Norajitra
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 70-74
Divertor and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-30
Articles are hosted by Taylor and Francis Online.
A modular helium-cooled divertor design based on the multi-jet impingement cooling concept, known as the helium-cooled multi-jet (HEMJ), has been developed at the Karlsruhe Research Center (FZK). Thermal-hydraulic design simulations have shown that the HEMJ divertor can accommodate an incident heat flux of at least 10 MW/m2 with local heat transfer coefficients as high as ~50 kW/(m2K). However, there were no experimental data to validate the calculated thermal performance. An experimental study of the HEMJ divertor was therefore performed at Georgia Tech in collaboration with FZK. An experimental test module duplicating the prototypical HEMJ geometry and material properties was designed, fabricated, instrumented, and tested in an air flow loop at different incident heat flux values. The air flow rate was selected to cover a wide range of Reynolds numbers spanning that for the actual HEMJ, namely 2.1 × 104. The measured temperature distributions and local heat transfer coefficients estimated from these temperature distributions are both in good agreement with numerical predictions of the air-cooled test module performance calculated using FLUENT[registered] 6.2 for all test conditions. This research supports earlier numerical predictions of the thermal performance of the HEMJ design, and provides added confidence in the ability of the FLUENT[registered]CFD package to accurately predict the thermal performance of various gas-cooled plasma-facing components with complex geometry.