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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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IAEA again raises global nuclear power projections
Noting recent momentum behind nuclear power, the International Atomic Energy Agency has revised up its projections for the expansion of nuclear power, estimating that global nuclear operational capacity will more than double by 2050—reaching 2.6 times the 2024 level—with small modular reactors expected to play a pivotal role in this high-case scenario.
IAEA director general Rafael Mariano Grossi announced the new projections, contained in the annual report Energy, Electricity, and Nuclear Power Estimates for the Period up to 2050 at the 69th IAEA General Conference in Vienna.
In the report’s high-case scenario, nuclear electrical generating capacity is projected to increase to from 377 GW at the end of 2024 to 992 GW by 2050. In a low-case scenario, capacity rises 50 percent, compared with 2024, to 561 GW. SMRs are projected to account for 24 percent of the new capacity added in the high case and for 5 percent in the low case.
Tsuguyuki Kobayashi
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 231-244
Technical Paper | Reprocessing | doi.org/10.13182/NT12-A13368
Articles are hosted by Taylor and Francis Online.
A simple procedure to simulate the important kinetic features of counter-current processes in pulsed columns has been developed. The overall mass transfer coefficient was simplified to be constant along the column, and the stripping of Pu4+ by hydroxylamine is assumed to be instantaneous to avoid complex reaction rate calculations. The number of calculation cells can be determined by making calculations with an increasing number of cells until its influence becomes small enough. The validity of these simplifications was confirmed by comparing the calculation results with a wide range of measured data from extraction and stripping as well as Pu partition tests with laboratory, engineering, and pilot scale columns. This procedure is intended for use in a conceptual design study of a future fast breeder reactor (FBR) reprocessing plant. An example of its application in a flow sheet calculation was demonstrated, where a coextraction process of U and Pu was simulated to find the conditions to obtain a solution with Pu/(U + Pu) ratio being 30% from a typical feed of FBR spent fuel solution.