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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Nuclear Science and Engineering
November 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Liftoff report lifts the lid on cost and risk in push to nth-of-a-kind reactors
The Pathways to Commercial Liftoff: Advanced Nuclear report that was released in March 2023 by the Department of Energy called for five to 10 signed reactor contracts for at least one reactor design by 2025. Now, 18 months have passed, and despite the word “resurgence” in media reports on the U.S. nuclear power industry, 2025 is fast approaching with no contracts signed.
Zhiwei Zheng, Fabiola Guido Garcia, Jianan Liu, Shinya Nagasaki, Tammy (Tianxiao) Yang
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1475-1486
Research Article | doi.org/10.1080/00295450.2023.2300900
Articles are hosted by Taylor and Francis Online.
Uranium has been identified as an element of interest for the safety assessment of a deep geological repository for used nuclear fuel. This paper examines the sorption behavior of U(VI) onto MX-80 bentonite and granite in Ca-Na-Cl solutions of varying ionic strengths [0.05 to 3 mol/kgw (m)] and across a pH range of 4 to 10. U(VI) sorption on MX-80 showed that U(VI) sorption gradually increased with pHm until pHm = 6, where it reached its maximum, and decreased slightly with pHm until pHm = 8, and then became constant. U(VI) sorption on granite increased along with pHm, reached the maximum around pHm = 7 to 8, and then slightly decreased with pHm. Both MX-80 and granite showed essentially no ionic strength dependence for sorption of U(VI). A nonelectrostatic surface complexation model successfully predicted sorption of U(VI) onto MX-80 and granite using the formation of an inner-sphere surface complex. Optimized values of surface complexation reaction constants (log K0) for the formation reactions of these surface species are proposed.