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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
N. Levitz, D. E. Grosvenor, S. Vogler, F. G. Teats, N. Quattropani
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 60-63
Technical Note | Chemical Processing | doi.org/10.13182/NT73-A31334
Articles are hosted by Taylor and Francis Online.
A continuous fluidized-bed process for the conversion of uranium/plutonium nitrates to oxides is under development to facilitate the recycle of plutonium in the nuclear fuel cycle. The basic process consists of two steps, each performed in a separate fluid-bed reactor: (a) codenitration at 375°C of uranyl nitrate-plutonium nitrate solutions to a UO3-PuO2 powder form, and (b) reduction of the UO3-PuO2 with hydrogen at 600°C to form UO2-PuO2. Pilot-plant denitration studies with uranyl nitrate-plutonium nitrate solutions containing uranium/plutonium ratios of 50 and 4, and plutonium nitrate solution alone are described, as well as reduction of UO3-PuO2 powder. Examination of the UO3-PuO2 denitration product by autoradiographic and electron microprobe techniques showed that the PuO2 was distributed in the UO3 matrix with a high degree of homogeneity. The conversion process appears to be applicable over the entire range of uranium-plutonium concentrations and for plutonium nitrate alone. The suitability of this product for the fabrication of fuel pellets is being studied in cooperation with nuclear fuel manufacturers.
