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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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 Science and Engineering
June 2025
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.
G. Pierini, R. Baratti, A.M. Polcaro, P.F. Ricci, A. Viola
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 2121-2126
Blanket and Process Engineering | Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) | doi.org/10.13182/FST85-A24597
Articles are hosted by Taylor and Francis Online.
The extraction of tritium from the liquid alloy 17Li83Pb has been examined taking into consideration the equations related to the design of “droplet spray” and “bubble” extractors in order to verify which are the higher tritium recovery efficiencies which can be realized so as to minimize the permeation of tritium into the water of the cooling system. As far as the droplet spray unit is concerned, the tritium extraction efficiency has been correlated to tritium pressure in the extractor, to the droplet radius and to the residence time of the droplets in the extractor. For the tritium desorption from the alloy, flowing countercurrent to a helium stream in a bubble extractor, the axial dispersion in the liquid and gaseous phases and the effects of gas phase expansion caused by reduced hydrostatic head in the extractor are taken into account. From the results of this study, both the bubble and spray droplet extractors seem to be very appropriate units for tritium recovery from the alloy. Moreover, in order to reach high extraction efficiencies for reducing the tritium permeation to the water cooling system, the spray droplet extractor appears more suitable.
