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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
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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Latest News
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.
D. Ramaswami, N. M. Levitz, A. A. Jonke
Nuclear Technology | Volume 1 | Number 4 | August 1965 | Pages 293-300
Technical Paper | doi.org/10.13182/NT65-A20525
Articles are hosted by Taylor and Francis Online.
A fluid-bed volatility process, developed for the recovery of uranium from highly enriched uranium-zirconium and uranium-aluminum alloy fuels, involves separating the alloying material as a volatile chloride by reaction with hydrogen chloride and recovering the uranium as its volatile hexafluoride by reaction with fluorine. These highly exothermic reactions are conducted in a fluidized bed of alumina, which serves as a heat transfer medium. Process development work conducted in a 3.8-cm (1½-in.) diam nickel fluid-bed reactor with aluminum and zirconium alloys of normal uranium showed that recovery of >99% of the uranium in the fuel can be achieved. High decontamination from fission products is expected on the basis of technology developed in previous studies. Considerable economic advantage of this process over current aqueous reprocessing schemes results from (a) small waste volumes produced, mostly in solid form, (b) considerable flexibility in process operating conditions, (c) fewer operations needed, and (d) the product form, uranium hexafluoride, which is readily amenable to isotope separation or conversion for reuse as fuel.