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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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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.
Franco Vittorio Frazzoli, Romolo Remetti, Sergio Guardini, Valeri Maiorov
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 205-214
Technical Paper | Reprocessing | doi.org/10.13182/NT99-A2968
Articles are hosted by Taylor and Francis Online.
The presence of Pu X-ray peaks in the gamma spectrum of Pu-bearing materials [for example, PuO2 and mixed-oxide (MOX) samples] is commonly attributed to alpha and gamma excitation. The aim of this work is the development of a mathematical model, based on the "thick target yield" approach, for both alpha- and gamma-induced fluorescence processes, thus enabling the quantification of the relative importance of these effects and the interpretation of the experimental data.Experimental data obtained at the Performance Laboratory (European Commission, Joint Research Center, Ispra, Italy) from well-characterized PuO2 and MOX samples under well-defined experimental conditions are compared with the expected values based on the model developed, taking into account special self-attenuation of X rays from induced effects.Finally, a feasible application of the model is considered concerning the field of nuclear material accountancy and control; the possibility of inferring U and Pu concentrations in MOX from the normalized Pu K-shell X-ray counting rate is considered, and the expected performances are given.