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Centrus, X-energy sign enrichment contract as TRISO-X expands TX-1 campus
Centrus Energy Corp. will be providing X-energy with enrichment services for low-enriched uranium and high-assay, low-enriched uranium to support X-energy’s planned deployments of Xe-100 small modular reactors and TRISO-X fuel, according to the terms of a new contract signed by the companies. The fuel will be produced at Centrus’s American Centrifuge Plant in Piketon, Ohio. In turn, X-energy will provide Centrus with prepayments to help support expanding the capacity of Centrus’s domestic commercial enrichment program.
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.