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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.
Yeon Soo Kim, D. R. Olander, S. K. Yagnik
Nuclear Technology | Volume 128 | Number 3 | December 1999 | Pages 300-312
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT99-A3033
Articles are hosted by Taylor and Francis Online.
As a means of improving the gap-thermal conductance, a liquid metal (LM) is proposed as the gap-filling material replacing helium gas in the conventional light water reactor fuel rod. The potential application of the concept includes power reactor fuel rods, special-purpose test-reactor experimental rods, and mixed-oxide fuel rods. Novel fabrication methods to ensure a uniform LM-filled gap between the fuel and the cladding of minirods have been developed. The main concern was overcoming the large surface tension of an LM to eliminate LM-free spots in the gap. Compatibility tests of the LM with a Zircaloy tube have been conducted. Liquid gallium showed excessive reaction with Zircaloy at 350°C for a month. Liquid Bi-Sn-Pb alloy, on the other hand, showed a nearly negligible reaction with Zircaloy under the same conditions. Thermal superiority of the LM-bonded gap over a conventional helium-gas gap in a miniature fuel rod was confirmed through theoretical calculations and experimental measurements. The experiments involved water-quenching the element from 600°C and measuring the decrease of the fuel centerline temperature. The LM-bonded element reached 100°C in 10 s, while the gas-bonded element required nearly 100 s to attain this temperature.