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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.
H. F. Henry, J. C. Bailey, R. C. Rohr
Nuclear Science and Engineering | Volume 5 | Number 5 | May 1959 | Pages 285-290
Technical Paper | doi.org/10.13182/NSE59-A25600
Articles are hosted by Taylor and Francis Online.
The radioactive In116 produced by the In115(n,γ ) In116 reaction has been utilized in a simple personnel monitoring device at the ORGDP for several years as a method for estimating the total radiation dosage received in the event of a possible accidental nuclear reaction. A 1-gm indium foil is placed in a standard plastic security badge; after a suspected exposure to an accidental burst, this foil is monitored by a β-γ survey meter, and the reading obtained used to determine the estimated dosage. A time-after-exposure correction factor is also used. For calibration of indium foil, an exposure to a light-water moderated critical reactor of highly enriched uranyl fluoride was evaluated and the results are indicated briefly. An instantaneous exposure of about 60 mrad is detectable immediately after an exposure even with the unsplit badges and one of about 120 mrad is detectable an hour after the occurrence.
