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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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
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Nuclear Technology
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.”
G. Gervasini, F. Reiter
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 2373-2378
Material Property and Tritium Control | Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) | doi.org/10.13182/FST85-A24633
Articles are hosted by Taylor and Francis Online.
Several calculation codes have been developed for the determination of permeation, recycling and inventory of hydrogen isotopes in the first wall of thermonuclear fusion reactors. An analysis of these codes has been performed in the first part of this report. Then the PIDAT code has been modified by introduction of a temperature gradient in the wall. This modified code has been used to calculate the tritium behaviour in the first wall of NET. The results confirm that tritium permeation and inventory are affected by the conditions at the inner and outer surface, by trapping and by the temperature gradient in the wall.