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A Study on the Dissolution and Separation for the Quantitative Analysis of Iodide in Spent Nuclear Fuel
Analytical Science and Technology / Analytical Science and Technology, (P)1225-0163; (E)2288-8985
2000, v.13 no.6, pp.751-758
Choi,
K. C., Lee,
C. H., Song,
B. C., Park,
Y. S., Jee,
K. Y., &
Kim,
W.
H.
(2000). A Study on the Dissolution and Separation for the Quantitative Analysis of Iodide in Spent Nuclear Fuel. Analytical Science and Technology, 13(6), 751-758.
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Abstract
A study was carried out on the dissolution of spent PWR fuels and performed on the fuels and the separation of iodide for the quantitative analysis using SIMFUEL which has chemical composition of a simulated spent PWR fuel (burn-up; 35,000 MWd/MTU and cooling time; 10 years). To dissolve the SIMFUEL effectively and to minimize the formation of volatile iodine through dissolution process, the optimum ratio of mixed acid (<TEX>$HNO_3/HCl$</TEX> 80: 20 mol%) was established and ozone gas was purged. In the separation step of iodine with <TEX>$CCl_4$</TEX>, <TEX>$NH_2OH{\cdot}HCl$</TEX> was used for reducing <TEX>${IO_3}^-$</TEX> to <TEX>$I_2$</TEX>.The optimum acidity of the dissolved solution and the added of <TEX>$NH_2OH{\cdot}HCl$</TEX> were 2.5 M and more than <TEX>$1.5{\times}10^{-3}mole$</TEX>, respectively. The recovery of iodide by ion chromatography was <TEX>$82.8{\pm}4.1%$</TEX> and the total yield was corrected by gamma spectrometery using <TEX>$^{131}I$</TEX> as a tracer.
- keywords
- simulated spent PWR fuel, iodide, ion chromatography, separation
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