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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Latest News
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.
James M. Wu, Chun-Fa Chuang
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 40-49
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33301
Articles are hosted by Taylor and Francis Online.
Three-dimensional natural convection of the compacted spent fuel rod in a pool was studied. A numerical technique was developed based on the conservation of mass, momentum, and energy of a typical flow element in the channel. The coolant flow is laminar and single phase. The decay heat generation from the spent fuel rod was assumed to be a chopped sine curve. Different configurations of the fuel rods were considered. Calculation was done by varying the inlet coolant temperature, decay heat generation, radius of the spent fuel rod, and distance between spent fuel rods. A simple correlation for the Nusselt number, hydraulic diameter, Prandtl number, and Grashof number was obtained.
