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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.
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April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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.
Fukada Satoshi, Nishikawa Masabumi, Sagara Akio
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 1073-1077
Tritium | doi.org/10.13182/FST01-A11963386
Articles are hosted by Taylor and Francis Online.
Rates of continuous tritium recovery from a Flibe stream are calculated for a permeation window and a counter-current gas-bubble column. The area of the permeation window is estimated to be comparatively small unless very low tritium partial pressure is demanded for the system. It is probable that the tritium transfer rate is controlled not by permeation through the window material (Nb or ferrite steel) but diffusion in Flibe. Since tritium diffusion in the molten salt is also determination of the recovery rate in the gas-bubble column from Flibe to He, the evaluation of the tritium diffusion resistance in the molten salt is crucial for its design.