ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
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!
Latest Magazine Issues
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
October 2025
Nuclear Technology
September 2025
Fusion Science and Technology
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.
Masafumi Nakatsuka
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 426-433
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34863
Articles are hosted by Taylor and Francis Online.
Embrittlement of Zircaloy fuel cladding tubes by corrosion media was studied from the viewpoint of its applicability to spent-fuel reprocessing. The results from irradiated as well as unirradiated tubes are summarized as follows: 1.When iodine was employed as the solute, the use of methanol as the solvent caused significant embrittlement of the Zircaloy. 2.For the iodine-methanol solution, the embrittlement increased with the iodine content but saturated at 1 wt%. 3.A water content of up to 10 vol% in the iodine-methanol solution did not decrease the extent of embrittlement. 4.Fracture was of the grain-boundary type, and a fuel cladding tube irradiated to ∼35 GWd/t showed the same embrittlement behavior as an unirradiated one.