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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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
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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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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.
A. H. Fleitman, A. J. Romano and C. J. Klamut
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 24-32
Technical Paper | doi.org/10.13182/NSE65-A19759
Articles are hosted by Taylor and Francis Online.
Mercury corrosion of Si-deoxidized, low-carbon steel was studied in 5000-h tests using four natural circulation loops with once-through boilers operating at 593°C and with 111°C of superheat. The relative effects of very small quantities of Ti or Zr additions to the Hg and the effectiveness of steel pretreatment (for 500 h at 590–620°C with a liquid Hg-Zr solution), prior to contact with boiling Hg, were determined. A fourth loop, which had no additives nor loop pretreatment, was run simultaneously. With the exception of the Hg-Zr pretreated loop, maximum depth of corrosion did not exceed 50 µm and occurred near the superheater exit where the temperature was the highest. Boiler and condenser corrosion were less than 30 µm in these latter loops. Corrosion 300–1000 µm deep was found on the downstream side of the superheater of the Hg-Zr pretreated loop, and the severity of the attack was attributed to boiling instabilities, which caused liquid Hg to come into contact with the superheater walls. Adherent iron deposits were found in the boilers and cooler liquid regions of three of the loops, but no discernible iron deposits were found in the loop with Zr added. The total quantity of mass-transferred iron (deposits and particulate) was estimated to be approximately 0.2 gm in the Zr-added loop, 0.5 gm in the Ti-added loop, 1 gm in the loop with no additions and 2 gm in the loop pretreated with Hg-Zr solution.