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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Latest News
ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
W. M. Stacey, V. L. Beavers, W. A. Casino, J. R. Cheatham, Z. W. Friis, R. D. Green, W. R. Hamilton, K. W. Haufler, J. D. Hutchinson, W. J. Lackey, R. A. Lorio, J. W. Maddox, J. Mandrekas, A. A. Manzoor, C. A. Noelke, C. de Oliveira, M. Park, D. W. Tedder, M. R. Terry, E. A. Hoffman
Nuclear Technology | Volume 150 | Number 2 | May 2005 | Pages 162-188
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT05-A3614
Articles are hosted by Taylor and Francis Online.
A design is presented for a subcritical, He-cooled fast reactor, driven by a tokamak D-T fusion neutron source, for the transmutation of spent nuclear fuel (SNF). The reactor is fueled with coated transuranic (TRU) particles and is intended for the deep-burn (>90%) transmutation of the TRUs in SNF without reprocessing of the coated fuel particles. The reactor design is based on the materials, fuel, and separations technologies under near-term development in the U.S. Department of Energy (DOE) Nuclear Energy Program and on the plasma physics and fusion technologies under near-term development in the DOE Fusion Energy Sciences Program, with the objective of intermediate-term (~2040) deployment. The physical and performance characteristics and research and development requirements of such a reactor are described.