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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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
W. Berkhahn, W. Ehrfeld, G. Krieg
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 329-340
Technical Paper | Isotope Separation | doi.org/10.13182/NT78-A26731
Articles are hosted by Taylor and Francis Online.
In the separation nozzle process, uranium isotope separation is based on the mass dependence of the centrifugal forces in a fast curved flow consisting of uranium hexafluoride and a light auxiliary gas that is admixed in a high molar excess. The objectives of this investigation are to determine the dependence of the separating characteristics of a centrifugal flow field on its spatial structure. Calculations were carried out for small UF6 mole fractions in the light auxiliary gas, so that the complicated ternary diffusion equations are reduced to two simple binary diffusion equations. The calculations show that isotope separation increases with the radial displacement of the UF6 streamlines relative to the auxiliary gas. Favorable initial distributions for a large radial shifting of UF6 exist when the flux, at the beginning of deflection, is high for small deflection radii, whereas at the end of deflection, the UF6 should be concentrated at large radii near the outer deflection wall. Consequently, a radial decrease of flow velocity, a high ratio of nozzle width to deflection radius, and high centrifugal fields at the end of deflection yield high separation effects. Taking into account the interdependence between the gas flow rate, the viscous losses, and the diffusion coefficient, the model developed can predict the influence of geometric parameters on the separating characteristics of the nozzle.