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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.
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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.
Aurélien Ledieu, François Devreux, Philippe Barboux, Yves Minet
Nuclear Science and Engineering | Volume 153 | Number 3 | July 2006 | Pages 285-300
Technical Paper | doi.org/10.13182/NSE06-A2614
Articles are hosted by Taylor and Francis Online.
This paper proposes a contribution to understanding the alteration of high-level waste glasses. Numerical simulations, based on a Monte Carlo model, have been performed in parallel to static dissolution tests on simplified glasses. The leaching of borosilicate glasses has been investigated for various compositions containing three or four oxides, which have been derived from the French nuclear glass composition. The comparison between experimental data and simulations allows a precise understanding of the role of each element. The degree of alteration is shown to result from a competition between the irreversible extraction of the soluble species (boron and alkalis) and the reversible dissolution-condensation dynamics of silica, which make possible the restructuring of the surface layer into a passivating layer. The model explains how the surface layer is responsible for the blocking or, at least, for a considerable slowing down of the alteration. It is also able to explain a quite unexpected result, namely, the fact that the replacement of silica by more insoluble oxides (zirconium or aluminum oxides) actually induces an increase of the degree of alteration. This is due to the slowing down of the surface layer reconstruction that delays the alteration blocking.