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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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May 2025
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.
Hsu-Chieh Yeh, Cleon E. Dodge, Lawrence E. Hochreiter
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 473-481
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32355
Articles are hosted by Taylor and Francis Online.
An empirical reflood heat transfer correlation has been developed from the FLECHT reflood data for different axial power shapes and variable flooding rate conditions. This correlation consists of a separate quench correlation and a heat transfer coefficient correlation. The reflood correlation predicts both the quench front location and the heat transfer coefficient above the quench front. The reflood heat transfer correlation prediction is in good agreement with both the cosine and the skewed axial power shape FLECHT reflooding data as well as other rod bundle reflood data.