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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Fusion Science and Technology
August 2025
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The newest era of workforce development at ANS
As most attendees of this year’s ANS Annual Conference left breakfast in the Grand Ballroom of the Chicago Downtown Marriott to sit in on presentations covering everything from career pathways in fusion to recently digitized archival nuclear films, 40 of them made their way to the hotel’s fifth floor to take part in the second offering of Nuclear 101, a newly designed certification course that seeks to give professionals who are in or adjacent to the industry an in-depth understanding of the essentials of nuclear energy and engineering from some of the field’s leading experts.
G. Listvinsky, J. J. Weede, S. L. Salem, A. Wolfson
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 514-520
The Compact Ignition Tokamak Program | Proceedings of the Seveth Topical Meeting on the Technology of Fusion Energy (Reno, Nevada, June 15–19, 1986) | doi.org/10.13182/FST86-A24798
Articles are hosted by Taylor and Francis Online.
This paper describes the ongoing analysis efforts supporting the design of the first wall (FW) and vacuum vessel (VV) components for the Compact Ignition Tokamak (CIT). Thermal and stress analyses of FW graphite tiles have established a nominal tile thickness of 1.0 cm and a maximum allowable FW surface heat flux of 11.0 MW/m2. Calculations have shown that for a cooldown time of one hour, the required tile to W thermal conductance is > 0.1 W/K. Estimates of worst-case electromagnetic loads and resulting stresses on the VV during plasma disruptions have shown the maximum stress levels to be below the allowable limits for the VV material. These results have demonstrated that the selected FW/VV concept is consistent with the design objectives.
