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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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November 2024
Latest News
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
R. A. Anderl, D. A. Petti, K. A. McCarthy, G. R. Longhurst
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 568-572
Device, Facility, and Operation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST41-568
Articles are hosted by Taylor and Francis Online.
The Safety and Tritium Applied Research (STAR) Facility has been established at the Idaho National Engineering and Environmental Laboratory (INEEL) and is designated as a National User Facility. STAR is designed for use by the fusion community to study tritium science and technology issues associated with the development of fusion technology. The facility tritium inventory limit is 16,000 Ci, allowing several simultaneous experiments requiring hundreds to a few thousand Ci per experiment. Experiments are conducted in gloveboxes. Current plans include research on tritium interactions with plasma facing materials; tritium behavior, corrosion and safety studies for molten fluoride salts; chemical reactivity of fusion materials; mobilization of activation products and characterization of dust/debris from fusion devices.
