Separation of isotopes U and Cs in irradiated nuclear fuel with cation exchange column method using lampung zeolite

In this study, the cation exchange column method using Lampung zeolite was used to separate uranium from cesium. The separation of uranium from cesium aims to obtain a pure uranium solution sample free from the cesium isotope because it affects uranium measurements with an alpha spectrometer and als...

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Hauptverfasser: Boybul, Boybul, Yanlinastuti, Yanlinastuti, Ginting, Aslina Br, Haryati, Iis, Indaryati, Sutri
Format: Tagungsbericht
Sprache:eng
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Zusammenfassung:In this study, the cation exchange column method using Lampung zeolite was used to separate uranium from cesium. The separation of uranium from cesium aims to obtain a pure uranium solution sample free from the cesium isotope because it affects uranium measurements with an alpha spectrometer and also contains high radiation exposure. The separation of uranium and cesium was carried out in an atmosphere of nitric acid, hydrochloric acid and sulfuric acid to see the efficiency of the absorption of uranium and cesium by the zeolite through the cation exchange process. Determination of the efficiency of uranium separation used a standard sample of uranium with a certain concentration. and efficiency of cesium absorption using a sample solution after nuclear fuel irradiation. The purpose of this study was to obtain the optimal parameters for the separation process of uranium and cesium isotopes in order to obtain a pure uranium sample solution for measurement with an alpha spectrometer. The process parameters used are type of eluent and concentration of eluent. The results of optimization of the uranium and cesium separation process were obtained that uranium leaving the column unbound with zeolite was in the eluent solution, the optimum condition was using nitric acid eluent solution with 0.15 M concentration with a recovery of 99.92%. While the cesium isotope is in the stationary phase bound as zeolite-Cs with a recovery of 99.98%. The results of the optimization of the uranium and cesium separation process were used to determine the content of uranium isotopes in the irradiated nuclear fuel solution. Measurement results of uranium isotope content in nuclear fuel solution after irradiation were obtained respectively at 55.6 mg/g Top position, 40.3 mg/g Middle position, and 50.4 mg/g Bottom position. The results of the measurement of the cesium content in the irradiated nuclear fuel solution were obtained respectively at 0.42 mg/g in the Top position, 0.99 mg/g in the Middle position, and 0.45 mg/g in the Bottom position.
ISSN:0094-243X
1551-7616
DOI:10.1063/5.0193160