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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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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.
S. Rosanvallon, J.L. Courouau, G. Marbach, W. Gulden
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 695-699
Decontamination and Waste | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST41-695
Articles are hosted by Taylor and Francis Online.
The waste management is a challenge for any future fusion facility including ITER. Detritiation could allow easier procedures since the practices in different countries already limit tritium contents and releases for disposal in nuclear waste storage. The experience developed in steel-making processes, for liquid steel degassing by gas injection, has been applied for modeling of tritium removal. A numerical model, initially developed at IRSID (USINOR's Process Research Center) for hydrogen removal, is adapted to determine detritiation efficiency. The hydrogen isotope transfer between liquid metal and injected gas occurs in two elementary steps, liquid phase mass transfer and interfacial reaction driven by Sievert's law for H2 and T2. In the gas phase, H2 and T2 react to give HT, according to the thermodynamic equilibrium and the isotopic exchange. The model takes into account the change in bubbles swarms (sizes and velocities) as they ascent from the bottom of the vessel to the metal free surface. It is thus possible to predict the tritium content evolution during the treatment as a function of process parameters. Duration and inlet gas mixture, which have the major influence on detritiation efficiency, must be set according to the tritium initial concentration and the activity expected in the final waste.