- P-ISSN 1225-0163
- E-ISSN 2288-8985
- P-ISSN1225-0163
- E-ISSN2288-8985
- SCOPUS, ESCI, KCI
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Determination of Fission Products in Simulated Nuclear Spent Fuels by Cation.Anion Exchange Chromatography and Inductively Coupled Plasma Atomic Emission Spectrometry
Analytical Science and Technology / Analytical Science and Technology, (P)1225-0163; (E)2288-8985
2000, v.13 no.4, pp.446-452
Choi,
K. S., Sohn,
S. C., Pyo,
H. Y., Suh,
M. Y., Kim,
D. Y., Park,
Y. S., &
Jee,
K.
Y.
(2000). Determination of Fission Products in Simulated Nuclear Spent Fuels by Cation.Anion Exchange Chromatography and Inductively Coupled Plasma Atomic Emission Spectrometry. Analytical Science and Technology, 13(4), 446-452.
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Abstract
The simulated nuclear spent fuel (SIMFUEL) containing the platinum group elements which will not be dissolved in a nitric acid was completely dissolved with a acid digestion bomb. The metallic elements separated in the SIMFUEL were measured by inductively coupled plasma atomic emission spectrometry (ICP-AES). Because the peaks of metallic elements were spectrally interfered by uranium spectrum, uranium and metallic elements were separated by cation exchange resin for Mo, Pd, Rh and Ru and by anion exchange resin for Ba, Ce, La, Nd, Rh, Sr, Y and Zr, respectively. The recovery of Mo, Pd, Rh and Ru after separation by cation exchange chromatography found to be 99-103% and anion exchange separation showed 96.5-107% of recovery except Y with the simulated solution whose concentration was similar to the spent nuclear fuel. The relative standard deviation of this method showed 1.3-6.7% in the SIMFUEL whose concentrations of metallic elements were between several <TEX>$10^2-10^3$</TEX>ppm.
- keywords
- SIMFUEL, anion.cation exchange chromatography, ICP-AES
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