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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
Francesco Ghezzi, Walter T. Shmayda, Giovanni Bonizzoni
Fusion Science and Technology | Volume 31 | Number 1 | January 1997 | Pages 75-105
Technical Paper | Tritium System | doi.org/10.13182/FST97-A30781
Articles are hosted by Taylor and Francis Online.
Tritium gas handling involves the production of tritiated water, which is 10000 times more hazardous than tritium gas. If tritium emission to the environment must be minimized, the need to process tritiated water and recover the chemically bound tritium appears clear. Facilities for processing tritiated water produced in fission reactors are already available, while facilities for a deuterium-tritium fusion machine are under development. However, these facilities are intended for large-scale applications and are neither practical nor economical for small-scale applications. HTO vapor reduction to HT over a hot metal getter other than uranium offers a simple, safe, and economical solution. A high alloy capacity and conversion rate combined with a low tritium residual inventory in the exhausted alloy make this method attractive. An experimental investigation of the efficiency of reducing HTO by a Zr-Fe-Mn alloy is presented. The results, obtained by three independent diagnostics (stripper set, ionization chambers, and mass spectrometry), show that for gas residence times >1 s and alloy temperatures >400°C, a conversion efficiency exceeding 90% is achievable. Specific conversion rates >0.1 μmol/s·g−1 are observed during the alloy usage, while a capacity of the alloy, measured as an oxygen-to-alloy mole ratio, >2.6 has been measured.