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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
W. D. Bond, H. C. Claiborne, R. E. Leuze
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 362-370
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31499
Articles are hosted by Taylor and Francis Online.
The extent to which actinides must be removed from spent reactor fuel in order to reduce the hazard index of high-level waste after a 1000-yr storage period to 5% of the hazard index of pitchblende has been determined, and a partial evaluation of the feasibility of accomplishing these removals has been made. The feasibility study was directed primarily at high-level waste from commercial reprocessing of light-water-reactor fuel. Conceptual processes were derived from published information. Several specific problems must be solved before satisfactory process flow sheets can be developed for obtaining the necessary degree of removal of uranium, neptunium, plutonium, americium, and curium.
