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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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. J. Petkus, T. R. Johnson, R. K. Steunenberg
Nuclear Technology | Volume 4 | Number 6 | June 1968 | Pages 388-393
Technical Paper and Note | doi.org/10.13182/NT68-A26363
Articles are hosted by Taylor and Francis Online.
Uranium monocarbide was synthesized on a 500- to 1000-g scale by the reaction of uranium dissolved in a liquid zinc-magnesium alloy with finely divided carbon suspended in the liquid-metal solution. The carbide precipitated as an insoluble solid phase that was heavier than the solvent metal. After a settling period, the bulk of the Zn-Mg supernatant liquid was transferred by pressure-siphoning. The Zn-Mg remaining with the UC precipitate was removed by vacuum distillation at temperatures of 850 to 900°C. The better UC products had a carbon-to-uranium atom ratio (C/U) of 1.05 to 1.10 and contained 0.2 to 0.3 wt% O and 0.2 to 0.4 wt% Mg and Zn. Uranium monocarbide was the only compound formed by this method but it was not possible to produce UC with a C/U ratio of 1.00 or less because an excess of carbon was necessary to completely react the dissolved uranium.