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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.
V. F. Baston, J. H. McFadden, W. A. Yuill
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 247-256
Technical Paper | Fuel | doi.org/10.13182/NT72-A31114
Articles are hosted by Taylor and Francis Online.
An analytical method based on the steady-state release model developed by Idaho Nuclear Corporation (now Aerojet Nuclear Company) is presented for calculating noble gas and iodine release to the fuel cladding gap of fuel pins in a nuclear reactor operating at steady-state conditions. This method, which employs fission gas capsule data and conservative assumptions (assumptions that result in prediction of maximum release), can be used in reactor safety analysis to predict the fission gases that could be available for release in the event of cladding failure and the pressure exerted by the fission gases on the inside of the cladding during reactor operation.