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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
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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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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.
Om Prakash Joneja, Michel Schaer, Cherif Sahraoui, J.-P. Schneeberger, Vijay R. Nargundkar, K. Subba Rao
Fusion Science and Technology | Volume 23 | Number 4 | July 1993 | Pages 408-418
Technical Paper | Blanket Engineering | doi.org/10.13182/FST93-A30133
Articles are hosted by Taylor and Francis Online.
It is important to know the neutron yield, the spatial distribution, and the spectra emitted from a generator when performing any quantitative measurements. An extremely intense (d, t)-driven neutron generator is used in the LOTUS fusion blanket program. The planned measurements include integral tritium and 233U breeding as well as heat deposition rate studies in blankets representative of fusion reactor blankets. Quantitative estimates of these integral parameters demand precise determination of the characteristics of the neutron generator. Extensive foil activation measurements have been carried out to determine the reaction rate distribution and the neutron yield by a proposed method. A comparison between the calculated and measured reaction rates and the distribution confirm the adequacy of the cross-section sets and the geometry description of the complete experimental arrangement.
