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