@article{32bac9f06a5546858d75a11ca25bee89,
title = "A novel method for molybdenum-99/technetium-99m recovery via anodic carbonate dissolution of irradiated low-enriched uranium metal foil",
abstract = "A new method is presented here for digesting irradiated low-enriched uranium foil targets in alkaline carbonate media to recover 99Mo. This method consists of the electrolytic dissolution of uranium foil in a sodium bicarbonate solution, followed by the precipitation of carbonate, base-insoluble fission products, activation products, and actinides with calcium oxide; most of the molybdenum, technetium, and iodine remain in solution. An electrochemical dissolver and mixing vessel were designed, fabricated, and tested for the processing of a full-sized irradiated foil under ambient pressure and elevated temperature. Over 92% of the fission-induced 99Mo was recovered in a product solution that was compatible with an anion-exchange column for retaining molybdenum and iodine.",
author = "Brown, {M. Alex} and Gelis, {Artem V.} and Fortner, {Jeffrey A.} and Jerden, {James L.} and Stan Wiedmeyer and Vandegrift, {George F.}",
note = "Publisher Copyright: {\textcopyright} 2014 American Chemical Society.",
year = "2015",
month = jan,
day = "21",
doi = "10.1021/ie503858j",
language = "English",
volume = "54",
pages = "712--719",
journal = "Industrial and Engineering Chemistry Research",
issn = "0888-5885",
publisher = "American Chemical Society",
number = "2",
}