ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Ph. Cetier, J. Charuau, Y. Belot, S. Fauvel, C.H. Wu
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1148-1152
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/FST95-A30562
Articles are hosted by Taylor and Francis Online.
This presentation describes experiments to investigate the sorption of tritium on carbon dust of different particle sizes and specific surface areas. The conditions of exposure were determined at the first wall of the tokamak. These conditions include low tritium pressures and depending on the operation phase, temperatures varying between 25°C and 1000°C. The simulation of these conditions inside an exposure chamber were necessary in order to design and construct a specific exposure device that could be adapted to these unusual conditions. Initial sorption data were obtained for carbon dust derived from a JET first-wall tile. The amount of tritium sorbed into or onto the carbon dust is between 0.1 and 10 mg T per kg C for a 24 hour-exposure duration. It increases with dust temperature. Other determinations, dealing particularly on the influence of exposure duration, are required to interpret this initial data.