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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
R. E. Burns, W. W. Schulz, L. A. Bray
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 566-575
Technical Paper | doi.org/10.13182/NSE63-A18449
Articles are hosted by Taylor and Francis Online.
Some solvent extraction flowsheet development studies performed recently at Hanford Laboratories in support of the Hanford radioactive waste management and neptunium recovery programs are summarized. Flowsheet for the removal of cesium from Purex current waste and stored waste supernatant liquid are discussed. Dipicrylamine-nitrobenzene is used to extract cesium; dilute nitric acid is used to strip cesium from the organic. A one-cycle flowsheet for the removal of strontium and rare earth elements from Purex process waste and separation of these into a strontium and a rare earth fraction is discussed. Extraction of the desired elements from a citrate complexed feed is by di(2-ethylhexyl) phosphoric acid-tributylphosphate-Soltrol solvent. Strontium is removed from the organic by dilute nitric acid in the second column. Rare earths are stripped from the organic by more concentrated nitric acid in a third column. Procedures for recovery of neptunium and plutonium from Purex process acidic waste are described. The solvent is di(2-ethylhexyl phosphoric) acid-Soltrol; Pu(IV) and Np(IV) are extracted from acid solution at such high distribution ratios that adequate recovery is attained in a single batch contact. Studies leading to the flowsheets as well as results of tests of the flowsheets with simulated and actual plant solutions are discussed.