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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.
Charles J. Mueller, James E. Cahalan, David J. Hill, John M. Kramer, John F. Marchaterre, Dean R. Pedersen, Roger W. Tilbrook, T. Y. C. Wei, Arthur E. Wright
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 226-234
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Saftey | doi.org/10.13182/NT90-A34430
Articles are hosted by Taylor and Francis Online.
The areas of Integral Fast Reactor (IFR) safety research are characterized in terms of their importance to the risk of core disruption sequences for innovative designs. Such sequences constitute the primary risk to public health and safety. All core disruption sequences are divided into four fault categories: classic unprotected (unscrammed) events, loss of decay heat, local fault propagation, and failure of critical reactor structures. Event trees are used to describe these sequences, and the areas in the IFR safety and related base technology research programs are discussed with respect to their relevance in addressing the key issues in preventing or limiting core disruptive sequences. Thus, a measure of potential for risk reduction is obtained for guidance in establishing research priorities.
