Determination of carbon-14 and tritium in a Pwr spent nucleat fuel

김정석; 박순달; 이창헌; 송병철; 지과용

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P-ISSN1225-0163
E-ISSN2288-8985
SCOPUS, ESCI, KCI

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P-ISSN 1225-0163
E-ISSN 2288-8985

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Vol.18, No.4

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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

& (2005). Determination of carbon-14 and tritium in a Pwr spent nucleat fuel. , 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($^{14}CO_2$) released during the dissolution of the spent fuel sample and $CaCO_3$ ($CO_2$ carrier) with 8 M $HNO_3$ at $90^{\circ}C$ 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.