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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.
Valter Cocilovo, Giuseppe Ramogida
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 478-482
Technical Note | doi.org/10.1080/15361055.2017.1330608
Articles are hosted by Taylor and Francis Online.
In this work the analysis of the effects of the poloidal currents flowing on the cooling piping of the divertor armour tiles is carried out. To deal with the complexity of the problem a parametric solving scheme, starting from the nominal plasma current value, was adopted to contemplate the great variability of the possible cases deriving from the experimental data base and to compensate the lack of knowledge due to the not well assessed theory on the plasma wall interaction. Further to overcame the difficulties in modeling the real design of the piping with the necessary spatial resolution to individuate the local current concentration areas the methodology illustrated here is based on shell interfaces for solving either the electric and the mechanical problem. This approach proved to be capable to highlight the critical design areas and was useful to suggest the relative remedial corrections.