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Separation and Purification for the Determination of Samarium and its Isotopes in PWR Spent Nuclear Fuels
Analytical Science and Technology / Analytical Science and Technology, (P)1225-0163; (E)2288-8985
2001, v.14 no.4, pp.291-299
Kim,
J. S., Jeon,
Y. S., Choi,
K. S., Park,
S. D., Lee,
C. H., &
Kim,
W.
H.
(2001). Separation and Purification for the Determination of Samarium and its Isotopes in PWR Spent Nuclear Fuels. Analytical Science and Technology, 14(4), 291-299.
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Abstract
A method of separation and purification of Sm for quantitation of Sm isotopes from various fission products in PWR spent nuclear fuels has been studied. Simulated solution containing inactive metal ions(Cs, Ba, Gd, Eu, Sm and Nd) in place of radioactive fission products was prepared. Sm was separated with 0.5 M <TEX>$HNO_3$</TEX>/80% MeOH after washing with 1 M <TEX>$HNO_3$</TEX>/90% MeOH on AG <TEX>$1{\times}8$</TEX>, anion exchange resin. Sm was purified on cation exchange resin, AG <TEX>$50W{\times}8$</TEX>, pretreated with 0.2 M alpha-hydroxisobutyric acid(pH 4.5-4.6) to remove Ba causing isobaric effect Sm from PWR spent fuel. As a result of mass spectrometric measurement, eluted Sm portion did not include isobars form other elements such as Gd, Eu, Pm, Nd and BaO. The contents of Sm and its isotopes(<TEX>$^{147}Sm$</TEX>, <TEX>$^{148}Sm$</TEX>, <TEX>$^{149}Sm$</TEX>, <TEX>$^{150}Sm$</TEX>, <TEX>$^{151}Sm$</TEX>, <TEX>$^{152}Sm$</TEX> and <TEX>$^{154}Sm$</TEX>) in spent fuel were determined by isotope dilution mass spectrometric method spiking <TEX>$^{154}Sm$</TEX>.
- keywords
- samarium separation, anion and cation exchange chromatography, IDMS
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