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Uranium prices steady as EIA releases annual market report
The end-of-July spot price for uranium was $86.36 per pound, as reported by Cameco—roughly the same as it has been since February. Analytics firm Trading Economics reported a uranium futures price of $86.60 per pound, a figure that also has been holding steady since early April.
These updates come as the U.S. Energy Information Administration has released its 2025 Uranium Marketing Annual Report, which examines in detail multiple aspects of the U.S. uranium market. Data are derived from answers given in the Uranium Marketing Annual Survey, which collects information on contracts, deliveries (during the past year and projected for the next 10 years), purchased enrichment services, inventories, fuel assembly usage, and market requirements.
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.