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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.
Y. Ikeda, A. Kumar, C. Konno, K. Kosako, Y. Oyama, F. Maekawa, H. Maekawa, M. Z. Youssef, M. A. Abdou
Fusion Science and Technology | Volume 28 | Number 1 | August 1995 | Pages 74-98
Technical Paper | Fusion Neutronics Integral Experiments — Part I / Blanket Engineering | doi.org/10.13182/FST95-A30402
Articles are hosted by Taylor and Francis Online.
To meet urgent requirements for data validation, an experimental analysis has been carried out for isotopic radioactivity induced by deuterium-tritium neutron irradiation in structural materials. The primary objective is to examine the adequacy of the activation cross sections implemented in the current activation calculation codes considered for use in fusion reactor nuclear design. Four activation cross-section libraries, namely, JENDL, LIB90, REAC*63, and REAC*175 were investigated in this current analysis. The isotopic induced radioactivity calculations using these four libraries are compared with experimental values obtained in the Japan Atomic Energy Research Institute/U.S. Department of Energy collaborative program on fusion blanket neutronics. The nine materials studied are aluminum, silicon, titanium, vanadium, chromium, MnCu alloy, iron, nickel, niobium, and Type 316 stainless steel. The adequacy of the cross sections is investigated through the calculation to experiment analysis. As a result, most of the discrepancies in the calculations from experiments can be explained by inadequate activation cross sections. In addition, uncertainties due to neutron energy groups and neutron transport calculation are considered. The JENDL library gives the best agreement with experiments, followed by REAC*175, LIB90, and REAC*63, in this order. Clear suggestions for a future direction to improve the overall calculation accuracy are developed based on the current experimental analysis.
