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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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.
N. M. Levitz, G. J. Vogel, E. L. Carls, E. Grosvenor, B. Kullen, D. Raue, W. Murphy
Nuclear Technology | Volume 6 | Number 2 | February 1969 | Pages 147-155
Technical Paper and Note | doi.org/10.13182/NT69-A28246
Articles are hosted by Taylor and Francis Online.
A total of 2.3 kg of PuF4 was fluorinated to PuF6 with elemental fluorine in a fluidized bed of alumina in three campaigns, each consisting of three separate fluorination runs followed by a fluorination-cleanup step in which any plutonium deposited in the lines and equipment was recovered. Each run involved 260 g of −325 mesh PuF4 powder; a single ∼6.5-kg bed of nominal 48–100 mesh alumina was used in each campaign. A 93% F2-7% N2 gas mixture, which was recycled, served as the fluidizing gas and reactant. The temperature of the fluidized alumina bed was increased incrementally to 550°C, and the total fluorination time for each run was 3 to 5 h. The PuF6 was collected in traps at ∼−65°C and subsequently was sorbed on NaF. Plutonium material balances were 97, 101, and 99%. Average production rates of PuF6 were 2.4 to 4.1 lb PuF6/(h ft2) but rates >6 lb PuF6/(h ft2) were attained in initial 30-min fluorination periods. Fluorine utilization efficiency (the ratio of fluorine reacted to that which could theoretically react based on equilibrium considerations) averaged 22, 17, and 28% although efficiencies near 100% were calculated for the earlier portions of a run, when large quantities of plutonium were present. Over 96% of the plutonium charged was recovered as PuF6 while ½% was discarded as waste in the alumina bed of the fluorinator. Less than 2% of the PuF6 was decomposed to PuF4 by radiation, and this was refluorinated and recovered without difficulty.