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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.
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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.
Masabumi Nishikawa, Nobuyuki Nakashio, Toshiharu Takeishi, Satoshi Matsunaga, Kiyoteru Kuroki
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1233-1238
Tritium Properties and Interaction with Material | 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/FST28-1233
Articles are hosted by Taylor and Francis Online.
Sorption behavior of tritium to isotropic graphite is discussed including solubility, diffusivity in the bulk of isotropic graphite and sorption capacity of hydrogen isotopes on the surface of isotropic graphite. The solubility and the diffusion coefficient of hydrogen isotopes in the graphite are obtained using the breakthrough method in the temperature range of 673–1273K and the activation energy of diffusivity is about 100kJ/mol. The sorption capacity of tritium on the graphite surface is also obtained by the breakthrough method using tritiated water in nitrogen gas flow. Tritium is captured on the graphite surface by isotope exchange reaction between tritium in gas flow and hydrogen in hydroxyl group on the graphite surface.These hydrogen atoms in hydroxyl group can easily exchange with other hydrogen isotopes in gas flow though they cannot be easily released from the graphite by drying or evacuating.
