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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.
Lainsu Kao, Mujid S. Kazimi
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 170-184
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A33995
Articles are hosted by Taylor and Francis Online.
Analyses of the concrete attack and ex-vessel aerosol release using various assumptions for the molten corium/concrete interaction have been performed. The study involved variations in several parameters, such as initial debris temperature, amount of unoxidized zirconium, amount of melt, concrete ablation temperature, and concrete type. At high initial corium temperatures the periodic contact (nucleate-boiling-like) model leads to more rapid concrete attack, higher decomposition gas release, and higher fission product release than the gas film model. At low initial corium temperatures, when a corium crust is initially formed, the various heat transfer models do not lead to significant differences in the fission product releases. Besides the initial debris temperature, the most significant parameter in prediction of the fission product release is the amount of unoxidized zirconium. Among the various fission products, the nonvolatiles, such as lanthanum, are more sensitive to changes in the parameters.