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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.
Yuichi Ogawa, Nobuyuki Inoue, Zensho Yoshida, Kunihiko Okano
Fusion Science and Technology | Volume 24 | Number 2 | September 1993 | Pages 188-199
Technical Paper | Plasma Engineering | doi.org/10.13182/FST93-A30225
Articles are hosted by Taylor and Francis Online.
The plasma and machine parameters of a pulsed tokamak reactor with a day-long operation period have been studied, where engineering constraints such as maximum toroidal field strength are preserved at International Thermonuclear Experimental Reactor (ITER) levels so as to realize a fusion reactor with only a short-range extension of currently available technology. To provide the magnetic flux necessary to sustain a plasma current inductively for 1 day or longer, plasmas with a major radius of R > 9.5 m are necessary, and a plasma with an aspect ratio as high as A > 5 should be employed. Typical parameters are as follows: major radius R = 10 m, minor radius a = 1.85 m, plasma elongation κ = 1.8, plasma current Ip = 12.2MA, toroidal field on axis Bt >= 7.56 T, and safety factor at the plasma surface qψ = 3. A plasma volume V ∼ 1200 m3 is comparable with that of ITER, even though the major radius of a day-long operation reactor is relatively large. A very small amount of heating power (∼ 15 MW) with a heating time of only a few tens of seconds is sufficient to achieve the ignition condition. This is well within the capacity of auxiliary heating systems currently used in large tokamak devices. A confinement improvement factor (from L mode) of fL > 1.7 is required to design a reactor with a reasonable machine size and a day-long pulse duration. The operation temperature is chosen to be 〈T〉 = 20 keV with a toroidal beta βt = 2.6% (Troyon factor g = 3), which gives a fusion power Pfus = 2.5 GW even for an alpha-particle dilution nα/ne of 10%. The bootstrap current fraction is 50% or more of the total current, and current profile needed for the beta limit could be achieved with a combination ofohmic current in the plasma center region and bootstrap current in the outer region. If the maximum toroidal field is set much higher, as in proposed recent reactor designs for the Steady-State Tokamak Reactor (SSTR) and ARIES, a more attractive plasma with a larger safety factor can be designed, and the pulse length can be extended remarkably.