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November 9–12, 2025
Washington, DC|Washington Hilton
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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
W. M. Stacey, K. A. Boakye, S. K. Brashear, A. C. Bryson, K. A. Burns, E. J. Bruch, S. A. Chandler, O. M. Chen, S. S. Chiu, J.-P. Floyd, C. J. Fong, S. P. Hamilton, P. B. Johnson, S. M. Jones, M. Kato, B. A. MacLaren, R. P. Manger, B. L. Meriwether, C. Mitra, K. R. Riggs, B. H. Shrader, J. C. Schulz, C. M. Sommer, T. S. Sumner, J. S. Wagner, J. B. Weathers, C. P. Wells, F. H. Willis, Z. W. Friis, J. I. Marquez-Danian, R. W. Johnson, C. de Oliveira, H. K. Park, D. W. Tedder
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 72-105
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT07-A3857
Articles are hosted by Taylor and Francis Online.
The design concept for a subcritical, He-cooled, fast reactor, fueled with transuranics (TRUs) from spent nuclear fuel in coated TRISO particles and driven by a tokamak D-T fusion neutron source, is being developed at Georgia Institute of Technology. The basic concept has been developed in two previous papers. This paper reports (a) advances in the design concept intended to enable achievement of "deep-burn" of the TRUs and passive safety, (b) investigations of the possibility of reprocessing the TRISO TRU fuel and of extending the strength of the fusion neutron source, (c) more extensive analyses to confirm and improve the design with respect to the adequacy of the fuel and nuclear performance, heat removal, tritium self-sufficiency and shielding, (d) more extensive analyses to confirm that the International Tokamak Experimental Reactor divertor, magnet and heating/current drive systems can be adapted, and (e) fuel cycle analyses to further investigate the contribution that such a reactor could make to closing the nuclear fuel cycle.