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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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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.