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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. Chinaglia and D. Monti, C. Fedrighini and A. M. Moncassoli
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 308-317
Technical Paper | doi.org/10.13182/NSE67-A18270
Articles are hosted by Taylor and Francis Online.
Fast-, epithermal-, and thermal-neutron penetration has been measured in the ETNA facility (plane fission neutron source) for some simple shield configurations (all water or a composite of water, iron, and water slabs with iron thickness of 6.2, 10, and 19.6 cm)., Experimental results are presented as thermal fluxes or activation-detector reaction rates for the water-only configuration and as the ratios of the reaction rates observed in the other configurations to those obtained with water only. These results are compared to calculations performed with a multigroup-removal diffusion code (MAC-RAD) and a semi-empirical diffusion code (FOG-S) to test their ability to predict the influence of an iron slab on the neutron spectrum and the neutron attenuation.
