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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
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.
