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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
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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.
Takumi Hayashi, Masayuki Yamada, Takumi Suzuki, Yuji Matsuda, Kenji Okuno
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1503-1508
Tritium Waste Management and Discharge Control | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30625
Articles are hosted by Taylor and Francis Online.
A new tritium removal system using gas separation membranes has been studied to develop more compact and cost-effective system for a fusion reactor. To obtain necessary parameters, which are directly scale able to the ITER Atmospheric Detritiation System, the basic tritium recovery performance was investigated with a scaled polyimide membrane module (hollow-filament type : 10 m3/hr ) loop. The result shows that the H2 recovery ratio from N2 or Air was more than 99 % or about 97 %, respectively, at flow rate ratio of permeated/feed =0.1, feed & permeated side pressures = 2580 & 80 torr, and module temp. = 293 K. Tritium (HT) recovery function was almost the same of H2 recovery, even though the total hydrogen concentration was a few ppm in the feed of module. H2O recovery performance was better than hydrogen recovery. These recovery functions were improved effectively decreasing the pressure ratio of permeated/feed of module.
