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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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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.
C. J. Martin, L. A. El-Guebaly
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 985-989
Technical Paper | Tritium, Safety, and Environment | doi.org/10.13182/FST07-A1622
Articles are hosted by Taylor and Francis Online.
Loss of Coolant Accident (LOCA) and Loss of Flow Accident (LOFA) thermal simulations have been performed for the ARIES compact stellarator fusion power plant. The ARIES-CS design uses three separate coolant loops: lithium-lead (LiPb) in the blanket, helium in the blanket and the shield, and water in the vacuum vessel. The thermal response to LOCA/LOFA conditions was simulated using transient axisymmetric finite element models. In these analyses, the plasma was quenched three seconds after coolant loss, and the temperature of the chamber components subsequently increased due to the generated decay heat. Thermal simulations determined the maximum temperatures reached in the various components were below the 740°C temperature limit for the reusability of the ferritic steel structure.
