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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
E. T. Laats, T. R. Schmidt, J. A. Reuscher
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 68-76
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31539
Articles are hosted by Taylor and Francis Online.
Experiments have been performed recently at Sandia Laboratories to investigate and characterize potential fuel materials for fast burst reactors. A novel technique has been developed to determine the thermomechanical properties of fuel materials under actual use conditions. The Sandia Pulsed Reactor II is used to rapidly fission heat a thin rod of the sample material, supported at its center, thereby inducing longitudinal stress waves in the sample. The dilation history at the ends of the rod and the temperature of the rod are recorded. A measure of the internal friction is determined from the decay of the longitudinal oscillations induced in the sample. The materials examined include uranium, U—0.78 wt% Ti, U— 6 wt% Mo, and U—10 wt% Mo. The first two are alpha-phase materials in a wrought condition, while the second two are gamma-phase-stabilized materials in an “as cast” condition. The alpha-phase wrought materials had higher internal friction than the gamma-phase “as cast” materials, with uranium being the highest by approximately two orders of magnitude as compared to U— 10 wt% Mo, the lowest.