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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.
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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.
R. Berger, G. Koehly, C. Musikas, R. Pottier, R. Sontag
Nuclear Technology | Volume 8 | Number 4 | April 1970 | Pages 371-379
Chemical Processing | doi.org/10.13182/NT70-A28663
Articles are hosted by Taylor and Francis Online.
Four slugs containing a sum total of 20.950 g of plutonium as Al-Pu 10% alloy have been irradiated in the EL-3 reactor to an integrated flux of 5 × 1021 n/cm2. After 2.5 years of cooling, the processing has been carried out in the hot cell “Petrus.” It consisted of (a) an alkaline and/or nitric dissolution of the “napkin-rings,” (b) a plutonium separation by two extraction cycles with trilaurylamine (5 vol%), each consisting of a plutonium extraction from a nitric medium and stripping by a solution containing sulfuric and nitric acids, (c) a transplutonium element separation by two HDEHP (8 vol %) extraction cycles, each consisting of an actinide-lanthanide extraction from an aluminum and lithium nitrate solution and a selective stripping of the transplutonium elements by a lithium nitrate solution containing diethylenetriaminopentaacetic ions (DTPA), and (d) an americium/curium separation by anion exchange resin using a nitric solution containing a complexing agent as eluent. From these runs 2.6 g of plutonium, 150 mg of americium, and 15 mg of curium have been recovered. The overall yields of plutonium and transplutonium elements were >97 and 98%, respectively, and the β - γ decontamination factors >105. In general, these results show clearly the effectiveness of solvent extraction in actinide reprocessing.