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Launching into tomorrow: NRIC guides new era of research and deployment
In June 2025, the Department of Energy announced the Reactor Pilot Program, an authorization pathway that allowed reactor developers to partner with the DOE to get first-of-a-kind (FOAK) reactors built and tested. Soon after, the DOE rolled out a complementary Fuel Line Pilot Program, which aimed to fast-track fuel projects. In all, 20 projects were accepted into the new programs.
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.