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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.
Doonyapong Wongsawaeng, Donald Olander
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 279-291
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3876
Articles are hosted by Taylor and Francis Online.
A liquid metal (LM) consisting of one-third weight fraction each of Pb, Sn, and Bi has been investigated as the bonding substance in place of He in the pellet-cladding gap of light water reactor fuel elements. The LM bond eliminates the large T over the preclosure gap that is characteristic of helium-bonded fuel elements. Because the LM does not wet either UO2 or Zircaloy, simply loading fuel pellets into a cladding tube containing LM at atmospheric pressure leaves unfilled regions (voids) in the bond, which lead to local fuel hot spots. Voids were eliminated during fabrication by first evacuating the rod loaded with solid alloy and a fuel stack, melting the alloy, pushing down the fuel stack to drive the LM into the gap, and finally applying at least 5 atm He overpressure. Fabrication of a 4-m-long full-scale fuel rod using this technique was successfully demonstrated. A destructive examination revealed numerous breaks in the frozen alloy bond, but all of these appeared to result from handling the fuel rod. Application to commercial fuel manufacturing should require only minor modifications to existing fabrication lines. The most suitable nondestructive examination technique utilizes a collimated X-ray beam to probe edge-on the region between the pellet surface and the cladding inside diameter.