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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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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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.
S. M. An, K. S. Ha, B. T. Min, H. Y. Kim, J. H. Song
Nuclear Technology | Volume 189 | Number 2 | February 2015 | Pages 133-142
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-24
Articles are hosted by Taylor and Francis Online.
The ablation kinetics of special concrete, which has been developed as one of the candidate protecting materials for the EU-APR1400 ex-vessel core catcher, was investigated experimentally. Metallic corium and stainless steel melts were generated using an induction heating technique in a cold crucible and used for the interaction tests with the special concrete. The melt delivery system was designed to prevent the melt impingement effect and chemical changes of the concrete specimen owing to preheating during the melt generation process. The metallic corium melts above the activation temperature interacted with the concrete specimens very intensively, which led to an abrupt increase of concrete ablation. However, in the interactions with the steel melts, the concrete specimens were ablated slowly even though the melt temperatures were higher than the metallic corium melts. A postanalysis of the chemical compositions and microstructures of the ingot with the ablated concrete was performed to understand the ablation phenomena. It was found that the U and Zr contained in the metallic corium melt reacted with the oxygen released by the dissociation of ferric oxides in the special concrete above the activation temperature. As a result of the exothermic reaction, both the ablation rate and the reaction layer coefficient were increased with a higher melt temperature and exhibited higher values than those in the interactions with the steel melt. Moreover, it was verified that the oxidation quotients of U and Zr are higher than those of Fe and Cr.