A Study on the Separation of Neodymium from the Simulated Solution of $U_3Si/Al$ Spent Nuclear Fuel
Analytical Science and Technology / Analytical Science and Technology, (P)1225-0163; (E)2288-8985
2000, v.13 no.5, pp.584-591
Choi, Kwang Soon
Kim, Jung Suk
Han, Sun Ho
Park, Soon Dal
Park, Yeong Jae
Joe, Kih Soo
Kim, Won Ho
Choi,
K. S., Kim,
J. S., Han,
S. H., Park,
S. D., Park,
Y. J., Joe,
K. S., &
Kim,
W.
H.
(2000). A Study on the Separation of Neodymium from the Simulated Solution of <TEX>$U_3Si/Al$</TEX> Spent Nuclear Fuel. , 13(5), 584-591.
Abstract
The separation of Nd from the simulated $U_3Si/Al$ spent fuel solution with sequential two-step anion exchange separation has been studied. To prepare the simulated $U_3Si/Al$ spent nuclear fuel, unirradiated $U_3Si/Al$ whose composition consists of small $U_3Si$ particle dispersed in an Al matrix with Al cladding was dissolved with a mixture of 4 M HCl and 10 M $HNO_3$ and 8 or 15 fission product elements were added to the dissolved solution. The trace amount of silica in the solutions was removed by evaporating to dryness with HF and the U was adsorbed on the first anion exchange resin. Neodymium can be purely isolated from the fission product elements with a methanol-nitric acid eluent using the second anion exchange resin. A large excess of Al didn't influence on the elution velocity of Nd, but reduced the eluted contents of Nd, Al, Eu, Gd, Sm and Sr, A large amount of Al was removed first from the column with 3 mL of loading solution (0.8 M $HNO_3$/99.8% MeOH) before Nd elution by the eluent [0.04 M $HNO_3$-99.8% MeOH(1:9)]. The recovery of Nd was more than 94%, regardless of Al contents. Taking the 9 to 13 mL fraction of eluate was effective to purely isolate Nd.
- keywords
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neodymium separation,
<TEX>$U_3Si/Al$</TEX> fuel,
anion exchange chromatography