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- E-ISSN 2288-8985
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Determination of La in <TEX>$U_3Si/Al$</TEX> Spent Nuclear Fuel by Ion Chromatography-Inductively Coupled Plasma-Mass Spectrometry
Analytical Science and Technology / Analytical Science and Technology, (P)1225-0163; (E)2288-8985
2000, v.13 no.5, pp.601-607
Han,
S. H., Choi,
K. S., Kim,
J. S., Jeon,
Y. S., Park,
Y. S., Jee,
K. Y., &
Kim,
W.
H.
(2000). Determination of La in <TEX>$U_3Si/Al$</TEX> Spent Nuclear Fuel by Ion Chromatography-Inductively Coupled Plasma-Mass Spectrometry. Analytical Science and Technology, 13(5), 601-607.
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Abstract
Lanthanum has been used as one of the burnup monitor in spent nuclear fuel. <TEX>$U_3Si/Al$</TEX> spent nuclear fuel contains small amount of La in high concentration of U and Al. Therefore, chemical separation of La is required to remove matrix elements. At first, ion chromatography (IC) and inductively coupled plasma systems were installed in radiation shielded glove box to handle the radioactive samples. Retention behavior of uranium, aluminum, lanthanum and some interesting fission products (Sr, Zr, Y, Mo, Ru, Pd, Rh, Cs, Ba, Ce, Pr, Nd, Sm, Eu and Cd) was investigated using the CG10 column and <TEX>${\alpha}$</TEX>-HiBA eluent. As all elements were eluted earlier than lanthanum in 0.2 M <TEX>${\alpha}$</TEX>-HiBA eluent, a portion of U and Al was directly passed to waste using a three way valve between the column and the nebulizer. Thus it was possible to determine the lanthanum in a high concentration of U and Al matrix. Retention time of La was about 12 minutes in this separation condition. Optimum range for the determination of La in <TEX>$U_3Si/Al$</TEX> spent nuclear fuel was <TEX>$1-10{\mu}g/L$</TEX> (ppb) with this system and detection limit was <TEX>$0.25{\mu}g/L$</TEX> in case of <TEX>$200{\mu}L$</TEX> of sample volume.
- keywords
- IC-ICP-MS, <TEX>$U_3Si/Al$</TEX>, spent nuclear fuel, matrix elimination, determination of lanthanum
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