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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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.
Yang Hong Jung, Seung Je Baik, Young Gwan Jin
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 94-102
Technical Paper | doi.org/10.1080/00295450.2020.1738795
Articles are hosted by Taylor and Francis Online.
A radioactive corrosion product, Chalk River unidentified deposit (crud) was sampled and analyzed using an electron probe micro-analyzer with zinc-injected spent nuclear fuel rods (HU Unit 1, actual burnup 49 655 MWd/tonne U). Hot-cell facilities, a space for handling highly radioactive materials, were used as a way to collect crud deposited in the fuel rod cladding tube at a specific location of the spent fuel rod. A soft collection method for collecting crud using rubbings or adhesive tape was used to collect a sample, and a sample was collected with hard collection using a steel knife from the cladding tube of the fuel rod. The spent fuel rods were used for two cycles burned after zinc was injected into the primary coolant, which is known to inhibit the generation of crud. To compare the analysis results of the soft and hard collection methods for sampling crud, the results of the crud collected using an ultrasonic wave system were analyzed. The crud used in this study used burned fuel rods for two cycles after zinc ions were injected into the primary coolant. Based on the results, the Ni/Fe ratio can be estimated to be about 1.18. The Ni/Fe ratio value of 1.18 derived from this study is not much different from the Ni/Fe ratio values derived from nuclear power plants operating around the world.