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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
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Denver, CO|The Westin Denver Downtown
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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.
I. N. Sviatoslavsky, E. A. Mogahed, Y-K. M. Peng, B. E. Nelson, P. J. Fogarty, E. T. Cheng, R. J. Cerbone
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1649-1653
Nonelectric Applications of Fusion | doi.org/10.13182/FST96-A11963187
Articles are hosted by Taylor and Francis Online.
Engineering design issues of a volumetric neutron source (VNS) based on a steady state low aspect ratio DT tokamak are presented. At the present the major radius is 0.8 m, the minor radius 0.6 m for an aspect ratio of 1.33, the plasma current is 10.1 MA, the toroidal field at the major radius is 1.8 T, the fusion power is 39 MW giving an average neutron wall loading of 1.0 MW/m2 on the outboard side with an available testing area of 10 m2. Two neutral beams delivering more than 20 MW are used to drive the steady state fusion plasma. A single turn unshielded water cooled dispersion strengthened (DS) Cu centerpost is used in conjunction with a conducting Cu bell jar which acts as a vacuum boundary and the return legs for the toroidal field (TF) coils. The centerpost is 9 m long, carries 7.2 MA and is specially shaped to minimize ohmic heating, which is calculated using temperature dependent DS Cu properties and increases in resistivity due to nuclear transmutations are accounted for. A naturally diverted plasma scrapeoff layer dominated by pressure-driven instabilities is assumed giving a peak heat flux of 5.2 MW/m2 on the diverter plates. Fabrication approaches for the centerpost and its replacement time lines have been estimated to be feasible and reasonable.