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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Orlando, FL|Renaissance Orlando at SeaWorld
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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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Supplier Showcase focus: Radiation protection
The American Nuclear Society is hosting a Supplier Showcase webinar, “Dose-Free, Radiation Visualization, and Mitigation,” tomorrow, November 13, from 2:00 p.m. to 3:00 p.m. (EST) on the capabilities of radiation visualization using the RadVision3D product.
The webinar, sponsored by Transco Products Inc., is free for all viewers. Registration is required.
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.