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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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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.
Supathorn Phongikaroon, Steven D. Herrmann, Michael F. Simpson
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 85-93
Technical Paper | Reprocessing | doi.org/10.13182/NT174-85
Articles are hosted by Taylor and Francis Online.
In this study, a diffusion-based kinetic model essential for design and operational analysis of spent nuclear fuel reduction has been developed. The model considers the cathode side of the system to be rate limiting and deals with diffusion of lithium metal through the basket loaded with uranium oxide (UO2 or U3O8). Faraday's law was implemented into the model to observe the electrochemical effect on the model. Solutions with different conditions are developed, and detailed results are presented. These solutions were compared against experimental bench scale data. At high operating current conditions (I > 0.8 A), the model fits the data well. The fitting resulted in estimated effective lithium diffusion coefficients for high and low void fraction UO2 crushed fuels of 8.5 × 10-4 cm2/s and 2.2 × 10-4 cm2/s, respectively. The effective diffusion coefficient for U3O8 is estimated to be 8.6 × 10-4 cm2/s. In some experiments, a porous magnesium oxide basket was used for containing the U3O8. It was estimated that the lithium diffusion coefficient through this magnesia basket is 3.3 × 10-5 cm2/s.