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Determination of carbon-14 and tritium in a Pwr spent nucleat fuel
Analytical Science and Technology / Analytical Science and Technology, (P)1225-0163; (E)2288-8985
2005, v.18 no.4, pp.298-308
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(2005). Determination of carbon-14 and tritium in a Pwr spent nucleat fuel. Analytical Science and Technology, 18(4), 298-308.
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Abstract
The methods for determining C-14 and tritium contents in the spent nuclear fuel sample were developed. The carbon-14(<TEX>$^{14}CO_2$</TEX>) released during the dissolution of the spent fuel sample and <TEX>$CaCO_3$</TEX> (<TEX>$CO_2$</TEX> carrier) with 8 M <TEX>$HNO_3$</TEX> at <TEX>$90^{\circ}C$</TEX> was collected in trap containing 1.5 M NaOH. The volatile radioactive iodine evolved when the spent fuel was dissolved, was trapped on to Ag-silicagel (Ag-impregnated silicagel) adsorbent in column which is connected to two NaOH traps. The solutions which contain tritium as HTO after fuel dissolution were decontaminated by deionization with a mixture of cation and anion exchange resins and inorganic ionexchangers. The amount of C-14 in the trap solutions and the HTO concentration in the resulting deionization water were then determined by liquid scintillation counting.
- keywords
- carbon-14, tritium, spent nuclear fuel, liquid scintillation counting
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