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Division Spotlight
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.
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.
L. J. Anastasia, P. G. Alfredson, M. J. Steindler
Nuclear Technology | Volume 7 | Number 5 | November 1969 | Pages 425-432
Chemical Process | doi.org/10.13182/NT69-A28445
Articles are hosted by Taylor and Francis Online.
Fluorination of simulated thermal reactor fuel containing UO2, PuO2, and oxides of elements formed in fission has been studied in a 2-in.-diam reactor containing a fluidized bed of alumina. After oxidation at 450°C pulverized the fuel pellets, the uranium was selectively fluorinated to UF6 with 10 vol% BrF5 at 200 to 400°C. Plutonium which remained in the fluidized bed as PuF4 was subsequently converted to PuF6 with 90 val% fluorine at 300 to 550°C. Volatile NpF6 was formed during fluorination with both BrF5 and fluorine and was distributed equally between the UF6 and the PuF6 products. The uranium was fluorinated at high rates with reasonably high utilization of BrF5. The temperature used to fluorinate uranium with BrF5 and plutonium with fluorine affected the extent of removal of plutonium from the fluidized bed. When fluorination is carried out at 250 to 350°C for uranium and 300 to 550°C for plutonium, ∼3% of the plutonium charged remains in the fluidized bed. Plutonium losses can be reduced by reuse of the alumina bed to process several batches of fuel.