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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.
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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.
Bal Raj Sehgal, Ching-Lu Lin, Edward L. Fuller
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 149-162
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A26277
Articles are hosted by Taylor and Francis Online.
A liquid-metal fast breeder reactor core design employing seed-blanket-type modular assemblies is presented. The seed region contains PUO2-UO2 fuel and the blanket region contains depleted UO2 fuel. These assemblies constitute the inner core while conventional mixed-oxide assemblies are employed in the outer core region. The results of design studies and analysis show that a large reduction in the sodium void reactivity can be obtained. The core fissile loading is larger than that for a homogeneous core. The analysis of an unprotected loss-of-flow (LOF) accident shows drastically reduced potential for a LOF-driven transient overpower accident. These results and conclusions are similar to those obtained for other heterogeneous core designs.