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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.
G. L. Ritter
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 194-202
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16311
Articles are hosted by Taylor and Francis Online.
The Purex solvent extraction process will be used in the nuclear fuel recovery and recycling center to reprocess up to 2100MT/yr of spent light water reactor fuels. Modifications to the process will be made to improve fission product decontamination and to treat gaseous and liquid radioactive waste streams. These modifications will allow overall decontamination factors for most fission products from recovered uranium and plutonium of >1010. No liquid process wastes will be released, and releases of radioactive materials in gaseous effluents will be as low as reasonably achievable.
