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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.
Bernd A. Thiele, Hermann Diehl, Wilhelm Ohly, Heinz Weber
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 597-606
G. Irradiation Behavior | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33481
Articles are hosted by Taylor and Francis Online.
Control rods in a pebble-bed-type high-temperature reactor operate at temperatures below 650°C, but in upset conditions short-term excursions up to 850°C can occur. Here, austenitic steels or nickel-base alloys show ductility losses caused by “helium high-temperature embrittlement.” The first of a series of irradiation experiments, followed by postirradiation tensile testing, quantified the losses in ductility of eight alloys (austenitic steels and high-temperature iron- and nickel-base alloys). Relative to the initial values of the rupture elongation, the ductility losses between 600 and 850°C were the same for all alloys with the exception of the strongly precipitation-hardened alloys, which showed more severe embrittlement at 600 to 700°C. The objective of the second experiment was to optimize the microstructure of austenitic steels (1.4981 and 1.4970) by specific thermomechanical treatments to increase the ductility after irradiation. Here again, it was found that all varieties showed nearly the same relative embrittlement behavior. Thus, it can be concluded that maximum ductility after irradiation requires a material with high ductility before irradiation.