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http://dx.doi.org/10.7733/jkrws.2012.10.2.077

Removal of Uranium from U-bearing Lime-Precipitate using dissolution and precipitation methods  

Lee, Eil-Hee (Korea Atomic Energy Research Institute)
Lee, Keun-Young (Korea Atomic Energy Research Institute)
Chung, Dong-Yong (Korea Atomic Energy Research Institute)
Kim, Kwang-Wook (Korea Atomic Energy Research Institute)
Lee, Kune-Woo (Korea Atomic Energy Research Institute)
Moon, Jei-Kwon (Korea Atomic Energy Research Institute)
Publication Information
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) / v.10, no.2, 2012 , pp. 77-85 More about this Journal
Abstract
This study was carried out to remove (/recover) the uranium from the Uranium-bearing Lime Precipitate (ULP). An oxidative dissolution of ULP with carbonate-acidified precipitation and a dissolution of ULP with nitric acid-hydrogen peroxide precipitation were discussed, respectively. In point of view the dissolution of uranium in ULP, nitric acid dissolution which could dissolved more than 98% of uranium was more effective than carbonate dissolution. However, in this case, uranium was dissolved together with a large amount of impurities such as Al, Ca, Fe, Mg, Si, etc. and some impurities were also co-precipitated with uranium during a hydrogen peroxide precipitation. On the other hand, in the case of carbonate dissolution-acidified precipitation, U was dissolved less than 90%. Therefore, it was less effective than nitric acid dissolution for the volume reduction of radioactive solid waste. However, it was very effective to recover the pure uranium, because impurities were hardly dissolved and hardly co-precipitated with uranium.
Keywords
Uranium; Carbonate; Oxidative dissolution; Nitric acid dissolution; Acidified precipitation; Hydrogen peroxide precipitation;
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Times Cited By KSCI : 1  (Citation Analysis)
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