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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
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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Nuclear Science and Engineering
July 2025
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June 2025
Fusion Science and Technology
Latest News
Countering the nuclear workforce shortage narrative
James Chamberlain, director of the Nuclear, Utilities, and Energy Sector at Rullion, has declared that the nuclear industry will not have workforce challenges going forward. “It’s time to challenge the scarcity narrative,” he wrote in a recent online article. “Nuclear isn't short of talent; it’s short of imagination in how it attracts, trains, and supports the workforce of the future.”
H.M. Attaya, G.A. Emmert, J.F. Santarius, G.L. Kulcinski
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 367-372
Power Reactor and Next-Generation Studies | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40072
Articles are hosted by Taylor and Francis Online.
A summary of a recent design effort for a high wall loading, low power, compact tokamak reactor is presented. The design employs a bean-shaped plasma to reach the second stability regime, where high beta values are attainable. A point design was chosen based on a parameteric survey that was conducted using the Tokamak Systems Code (TSC). The most important parts of that survey are presented here. Investigation of different plasma confinement scaling laws shows that the chosen point design has a reasonable ignition margin.