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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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June 2025
Nuclear Technology
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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.
W. F. Calaway
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 63-74
Nuclear Safety Analysis | Energy Modeling and Forecasting / Chemical Processing | doi.org/10.13182/NT78-A17008
Articles are hosted by Taylor and Francis Online.
The electrochemical evolution of hydrogen from a molten solution of LiF-LiCl-LiBr containing small quantities of LiH and saturated with metallic lithium has been demonstrated. The evolved hydrogen is recovered from the melt by sweeping the hydrogen electrode with a circulating stream of argon and subsequently trapping the hydrogen from the argon with a hot titanium getter bed. It is found that by continually gettering the argon, 100 ± 2% of the hydride present in the molten salt, at a concentration of 1 wppm, is recoverable. Results of metallographic examinations of stainless-steel components in contact with the salt solution during the experiments indicate some evidence of surface attack (10 to 15 µm) and intergranular penetration (30 to 50 µm), but extrapolated corrosion rates are generally small (∼0.2 mm/yr). These results incorporated into a reevaluation of the molten-salt extraction process, as it applied to tritium recovery from a liquid-lithium fusion reactor blanket, indicate a more favorable processing capability than was previously expected.