ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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!
Latest Magazine Issues
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
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.
V. S. Iyer, S. K. Mukerjee, R. V. Kamat, K. T. Pillai, N. Kumar, V. N. Vaidya, D. D. Sood
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 388-393
Technical Paper | Material | doi.org/10.13182/NT90-A34459
Articles are hosted by Taylor and Francis Online.
Oxidation studies have been carried out on 11.5 to 12.0 g/cm3 density uranium monocarbide microspheres and on mixed 11.96 to 12.04 g/cm3 density uranium-plutonium carbide pellets under various oxygen partial pressures in the 550 to 745 K temperature range. Oxidation of UC and (U,Pu)C produced a U3O8 [oxygen-to-metal ratio (O/M) = 2.66] and (U,Pu)O2 (O/M = 2.15), respectively, with a carbon content of <600 ppm. The surface area of the resultant oxides as determined by the Brunauer-Emmett-Teller method are 1 to 2 and 4 to 5 m2/g, respectively. The oxidized products were suitable for wet and dry recycle.