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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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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.
Yasuhisa Oya, Takuji Oda, Satoru Tanaka, Kenji Okuno
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1423-1426
Detritiation and Isotope Separation | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12698
Articles are hosted by Taylor and Francis Online.
The tritium recovery technique at the steam generator in fast breeder reactor under the double pipe concept was studied by both of experiment and simulation. The permeation of tritium was lowered at ~1000ppm oxygen in Ar as a recovery gas. But tritium is easily converted to water form by adding 10ppm oxygen. To explain these experimental results and expand the tritium behavior at double pipe concept, DFT and Monte Carlo simulations were applied. The surface oxide layer mode was developed and stability of tritium was evaluated. It was found that most stable structure was formed in the oxide layer although tritium is unstable at the surface of oxide layer. Tritium permeation rate was almost the same even if the oxide layer was formed, but the tritium retention is enhanced by adding the oxide layer. To expand these results to tritium permeation and recovery model, numerical analysis was performed as a function of sweep rate, material thickness and thickness of surface oxide layer. It was found that control of sweep rate is one of key factors. But the design restriction, control of oxide layer thickness by flowing O2+Ar gas will be potential option for the recovery of tritium at steam generator.