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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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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.
H. P. Planchon, G. H. Golden, J. I. Sackett, D. Mohr, L. K. Chang, E. E. Feldman, P. R. Betten
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 549-557
Technical Paper | doi.org/10.13182/NSE100-549
Articles are hosted by Taylor and Francis Online.
Two milestone tests were conducted in the Experimental Breeder Reactor II (EBR-II), demonstrating some of the inherent safety features of a liquid-metal reactor. The first test was a loss of flow without scram and the second was a loss of heat sink without scram. Both tests were initiated from 100% power, and in both tests the reactor was shut down passively-by natural processes, principally thermal expansion—without automatic scram, operator intervention, or the help of special incore devices. The temperature transients during the tests were mild, as predicted, and there was no damage to the core or reactor plant structures. The tests plus analysis demonstrated the feasibility of inherent passive shutdown for undercooling accidents and identified the more important features necessary for inherent shutdown and passive cooling. The results provide a technical basis for future experiments in EBR-II to investigate inherent safety for transient overpower accidents and to provide additional data for validation of computer codes used for design and safety analysis of inherently safe reactor plants.