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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Latest News
DOE fast tracks test reactor projects: What to know
The Department of Energy today unveiled 10 companies racing to bring test reactors online by next year to meet Trump's deadline of next Independance Day, leveraging a new DOE pathway that allows reactor authorization outside national labs. As first outlined in one of the four executive orders on nuclear energy released by President Trump on May 23 and in the request for applications for the Reactor Pilot Program released June 18, the companies must use their own money and sites—and DOE authorization—to get reactors operating. What they won’t need is a Nuclear Regulatory Commission license.
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.