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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Zachary S. Hartwig, Massimo Zucchetti
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 725-729
Nuclear Analysis & Experiments | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12471
Articles are hosted by Taylor and Francis Online.
A critical aspect of the design of a tokamak-based neutron source is to ensure that radiation limits of the structural and magnet-insulating materials are not approached during the lifetime of the tokamak. To this end, we present an exploratory neutronics study of a materials testing facility that is based on Ignitor, a high-field tokamak. It shown that sufficient radiation damage to test materials located in the Ignitor first wall can be obtained by sustaining a reaction rate of 3.33×1019 neutrons per second for 7 operational months. Solutions to mitigate terminal damage to the toroidal field coil insulators, including its substitution for modern radiation-resistant insulators and the use of advanced radiation shield materials, are explored, and their implication for the design of the facility is discussed.