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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Latest News
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.
R. N. Anderson, N. A. D. Parlee, J. M. Gallagher
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 29-35
Technical Paper | Fuel | doi.org/10.13182/NT72-A31064
Articles are hosted by Taylor and Francis Online.
The thermodynamics and kinetics of nitrogen-nitride reactions in liquid uranium-tin alloys have been investigated experimentally. In the presence of dissolved metal impurities in the alloys, the nitrogen has been found to react with the uranium to form UN which can, under proper conditions, be precipitated as a pure phase from the melt, leaving impurities behind. Thus, the concept of nitride precipitation offers a possible metallurgical separation method applicable to the reprocessing of spent fast reactor fuels. Based on laboratory studies for uranium and the extrapolated behavior for plutonium, it appears possible to attain 99% uranium recovery and 98% plutonium recovery, with decontamination factors of 106.