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ISSN : 1738-1894(Print)
ISSN : 2288-5471(Online)
Journal of Nuclear Fuel Cycle and Waste Technology Vol.3 No.1 pp.49-56
DOI :

방사성폐기물 중 129I 측정을 위한 시료의 전처리

Sample pre-treatment for measurement of 129I in radwastes

Ke-Chon Choi, Sun-Ho Han, Kwang-Yong Jee, Ki-Seop Choi

Abstract

Many different kinds of radwastes are discharged from the nuclear power plants, and I is included in these radwastes. Recovery test of I was evaluated for different radwastes(dry active waste, sludge, spent resin and simulated evaporator bottom). Recovery of I for dry active waste by acid leaching with NaClO was and l291 for spent rein by alkali fusion method with KOH as a flux agent was ), respectively. iodide in simulated evaporator bottom containing a high concentration of borate was adsorbed with anion exchange resin at pH 7 phosphate buffer solution. Recovery of I for anion exchange resin was and not affected up to 1,200 g/mL (as a Boron). Recovery of I for the spent resin from nuclear power plant was .
sample pre-treatment, 129I, radwastes, recovery, 시료전처리, 방사성폐기물, 회수율

 

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