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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.
B. Mukherjee, M. H. El Haddad, M. L. Vanderglas, D. V. Leemans
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 505-512
Technical Paper | Materials | doi.org/10.13182/NT55-505
Articles are hosted by Taylor and Francis Online.
A large number of Monel 400 steam generator tubes may be subjected to low cycle fatigue because of the particular location of the thermal plate. A low cycle fatigue analysis method, simulating the deformation response of structural component elements due to irregular load history, was applied to predict stress-strain behavior and then fatigue life of the Monel 400 steam generator tubing. The experiments revealed that under worst loading conditions (maximum displacement, with a tube locked in the thermal plate), the specimens failed due to mechanical fatigue in a period corresponding to three to five times the expected service life of a steam generator. Standard internal coil eddy current inspection techniques were not successful in detecting the cracks that had initiated in the Monel tubes in the region of the modeled tubesheet. This made the experimental and analytical fatigue life prediction work even more valuable.
