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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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Fusion Science and Technology
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.
H. H. Toudeshki, C. J. Martin, F. Najmabadi, J. P. Blanchard
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 535-540
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST15-112
Articles are hosted by Taylor and Francis Online.
ARIES ACT-1 is a conceptual design for a commercial tokamak with aggressive physics and engineering. In the spirit of advanced engineering, the vacuum vessel design employed several novel concepts. It eliminates the use of water cooling in order to allow higher temperature operation and reduce the tritium inventory. It employs a low activation bainitic steel that eliminates the need for post-weld heat treatment. It includes sufficient volume to accommodate a full loss of coolant accident. Finally, it employs a novel mechanical design in order to withstand the operating stresses during normal operation, anticipated transients, and disruptions. In this paper, we present the most recent design for this component, update the stress analysis confirming the suitability of the design, and present results for disruption forces due to a plasma quench.
