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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
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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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.
Vijay K. Sethi, John K. Bates
Nuclear Technology | Volume 60 | Number 2 | February 1983 | Pages 228-230
Technical Paper | Radiation Effects and Their Relationship to Geological Repository / Radioactive Waste Management | doi.org/10.13182/NT83-A33077
Articles are hosted by Taylor and Francis Online.
Leach samples of SYNROC containing 10 wt% synthetic radwaste were irradiated with 3.5-MeV 4He+ ions and 250-keV 84Kr+ ions. The irradiations were carried out in an ultra-high vacuum chamber by clamping the samples in a holder such that the majority of the surface area of the samples could be exposed to the ion beams. The holder was designed to allow sample rotation with respect to the beam to ensure uniform damage production over the entire irradiated volume. The leach tests were conducted in deionized water at 90°C for various times. The comparison of the leach rates with those from the control samples shows that the SYNROC waste form retains its leach resistance even when exposed to large doses of displacement producing radiation.