Advanced
Cation Exchange Separation and Determination of Ruthenium in a Simulated Spent Nuclear Fuel
Cation Exchange Separation and Determination of Ruthenium in a Simulated Spent Nuclear Fuel
Journal of the Korean Chemical Society. 2000. Dec, 44(6): 526-532
  • Published : December 00, 2000
Download
PDF
Export by style
Article
Author
Metrics
Cited by
About the Authors
Suh, Moo-Yul
Sohn, Se-Chul
Lee, Se-Chul
Choi, Kwang-Soon
Kim, Do-Yang
Park, Yeong-Jae
Park, Kyoung-Kyun
Jee, Kwang-Yong
Kim, Won-Ho

Abstract
Cation exchange separation and inductively coupled plasma atomic emission spectrometric(ICP-AES) determination of ruthenium in HCl solutions were studied to quantitatively determine ruthenium in spent nuclear fuels. Ruthenium-bearing samples were dissolved with the mixed acid solution(9 : 1 mole ratio, HCl-HNO$_3$) using an acid digestion bomb. Based on the absorption spectra and ion exchange behaviour of ruthenium in hydrochloric acid media, its possible chemical species were discussed. On a cation exchange column (0.7 ${\times}$ 8.0 cm) packed with AG 50W ${\times}$ 8(100~200 mesh) and equilibrated with 0.5 M HCl, ruthenium was eluated with 0.5 M HCl while uranium was retained on the column. The established separation method was applied to a simulated spent nuclear fuel and resulted in the recovery of 98.5% with a relative standard deviation of 0.7%.