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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
S. J. Hakim
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 129-139
Technical Paper | doi.org/10.13182/NSE79-A19458
Articles are hosted by Taylor and Francis Online.
Simultaneous crust growth in a fluid and the melting of an adjacent colder structure surface in contact with it are examined with emphasis on fast breeder reactor safety applications. The calculations were made subject to the following assumptions: 1. As long as a crust exists, melted structure adjacent to it stays in place until it melts. 2. When a crust melts, melted structure is ablated. The ablation process does not influence the temperature profile in the remaining intact structure. The dependence of the Fourier number at which complete structure melting occurs on fluid-to-crust heat flux is obtained for uranium oxide and thorium oxide crusts forming on steel surfaces. The crust behavior is also investigated as the heat flux is varied. The dependence of the results on internal heat generation and the Biot number on the other side of the structure is determined.