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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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.
J. Yaung, N. Ghoniem
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 87-91
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32755
Articles are hosted by Taylor and Francis Online.
The Fuel Rod Analysis Program (FRAP-S3) is a fairly comprehensive computer code that is developed for the analysis of light water reactor fuel elements during steady-state operation. However, the code pre dicts an increase in the fuel radial temperature dis tribution with an increase in the fuel density, which is contrary to experiments. A simple modification of the code was used where the thermal conductivity is treated as porosity independent in the inner iteration loops of the program. The resulting temperature pro file is corrected for the effects of porosity after it has converged. The modified code shows good agree ment with the IFA-11 series of experiments using the Halden Boiling Water Reactor in Sweden.
