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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, Hiroki Takata, Toshiharu Takeishi, Kozo Kamimae
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 386-389
Technical Paper | Tritium Science and Technology - Tritium Measurement, Monitoring, and Accountancy | doi.org/10.13182/FST05-A949
Articles are hosted by Taylor and Francis Online.
Feasibility of the monitoring way of HTO in air to follow the tritium level in water contained in a small shallow beaker with open surface placed still in a room was discussed in this study. It is considered that the isotope exchange reaction between tritiated water in air and water in a beaker, the evaporation or condensation reaction of water at surface and the diffusion of tritium in water played the important roles in the tritium transfer phenomena through the air-water interface. Using the mass transfer coefficients obtained in the previous paper, change of tritium level in water contained in a shallow open beaker was numerically estimated and comparison with the experimental data showed good agreement. The estimated amount of tritium released from the facility with storage pools of spent fuels from a PWR power station using the method of this study showed good agreement with the observed value evaluated from the monitor of the power station