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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.
D. J. Kowalski, V. J. Esposito
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 536-539
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32363
Articles are hosted by Taylor and Francis Online.
The classical manner of analyzing the loss-of-coolant accident hydraulic loads imposed on a Westinghouse-type steam generator was to assume a primary side outlet break and to assume that the confining structure was rigid. By considering the vertical divider plate to be flexible, it can be shown that the applied hydraulic forces on the divider plate, tubesheet, and tubes are significantly reduced. The assumption of a flexible divider plate requires the interaction of the fluid and structure simultaneously. The MULTIFLEX computer program and system model have the capability of considering this mutual interaction. Results have been obtained showing the reasons why and how the hydraulic loads on the steam generator internals are attenuated.