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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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Fusion Science and Technology
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.
D. Henderson, L. El-Guebaly, P. Wilson, A. Abdou, ARIES Team
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 444-448
Advanced Designs | doi.org/10.13182/FST01-A11963276
Articles are hosted by Taylor and Francis Online.
Detailed activation, decay heat and waste disposal calculations of the ARIES-AT design are performed to evaluate the safety aspects of the device. The high initial activity of the SiC highly irradiated components translates directly into a higher initial decay heat for these structures than for the well-protected steel-based components. However, after a one-hour cool-down period, the SiC decay heat drops by two decades to levels comparable to the steel-based components. The decay heat of the LiPb coolant was found to exceed that of the SiC components for several days after shutdown. This implies that a loss of flow accident (LOFA) event is more critical than a loss of coolant accident (LOCA) event for LiPb/SiC systems. Regarding waste disposal, all structures can easily meet the Class C Low-Level Waste (LLW) requirements established for the ARIES power plants. Many components could qualify as Class A LLW after a 100-year storage period after selection of low activation materials and control of the Nb and Mo impurities in ferritic steel. A purification system will be required to remove the 210Po and 203Hg generated by Pb during operation.