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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.
Linfeng Yan, Dawei Wang, Hsingtzu Wu
Nuclear Technology | Volume 208 | Number 12 | December 2022 | Pages 1822-1831
Technical Paper | doi.org/10.1080/00295450.2022.2083750
Articles are hosted by Taylor and Francis Online.
A passive residual heat removal system plays an important role in cooling the reactor core under accident conditions. The computational fluid dynamics (CFD) software package ANSYS Fluent is used to analyze the influence of malfunction of any 2 of 12 tubes of a passive residual heat removal heat exchanger (PRHR HX) on its performance. Then the computation was validated using the published experimental data. Five different scenarios and a normal condition are computed to analyze the influence of locations of the malfunctioning tubes on the heat transfer performance of the PRHR HX. The results show that the tube defect reduces the amount of heat transferred by the PRHR HX. However, it is correlated with the size of the surface area of the deficient tubes instead of their locations. In other words, analysis suggests that defect tubes with the same surface area should result in similar damage regardless of the location.
