ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
Ronald D. Gasser, Mujid S. Kazimi
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 248-259
Technical Paper | Reactor | doi.org/10.13182/NT77-A31786
Articles are hosted by Taylor and Francis Online.
A two-dimensional transient freezing model is developed to study the dynamics of solidification of a fluid flowing in a cylindrical channel, the walls of which are cooled below the freezing temperature of the fluid. The model is applied to the case of molten fuel flowing downward through the coolant channels in the lower shielding structure of current liquid-metal fast breeder reactor designs subsequent to a hypothetical core meltdown accident. The results indicate that under postaccident conditions, a high potential exists for rapid relocation of significant quantities of core debris across the shield structure.