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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.
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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.
K.J. Maynard, W.T. Shmayda, A.G. Heics
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1391-1398
Tritium Storage, Distribution, and Transportation | 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-A30606
Articles are hosted by Taylor and Francis Online.
The effects of tritium aging on ZrCo have been characterized to determine the suitability of ZrCo as a long term tritium storage medium. Four 1 gram ZrCo storage beds were aged for three years with varying amounts of tritium. Equilibrium tritium pressures were found to increase by approximately threefold at a given temperature and composition in the range of 100–300°C. At 25°C, the pressure increase is predicted to be twenty-fold. Tritium aged ZrCo retains the majority of decay 3He within the bulk. As this 3He concentration increases, the rate of helium release increases. Longer term tritium aging may result in a 3He release rate equal to its production rate from tritium decay. In such a case, the pressure within a sealed storage bed would steadily increase. These tritium aging effects indicate that practical ZrCo storage bed design should include conservative design pressure specifications, to safely contain the maximum possible 3He pressure.