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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
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.