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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
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.