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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.
Peter K. Mast, James H. Scott
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 600-605
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32371
Articles are hosted by Taylor and Francis Online.
A new fuel pin failure model, the Los Alamos Failure Model (LAFM), based on a linear life fraction rule failure criterion, has been developed to provide a reliable and inexpensive prediction of the time and axial location of liquid-metal fast breeder reactor fuel pin failure in a hypothetical transient overpower (TOP) accident. Code testing analyses for a number of TOP Transient Reactor Test Facility tests have resulted in excellent agreement between calculated and observed pin failure time and location. Because of the nature of the failure criterion used, the code has also been used to investigate the extent of cladding damage incurred in terminated as well as unterminated TOP transients in the fast test reactor. The results of these analyses show that 3 dollar/s and 50 and 5 cent/s transients terminated by the secondary trip point (25% overpower) result in negligible calculated cladding damage.