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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.1-7
DOI :

방사성폐기물 시료 중 241Am과 244Cm의 정량

Determination of 241Am and 244Cm in Radwaste Samples

Kihsoo Joe, Tae-Hyun Kim, Young-Shin Jeon, Kwang Youg Jee, Won-Ho Kim

Abstract

Anion exchange chromatography and HDEHP extraction chromatography using DTPA-lactic acid as an eluent were applied in series for the separation of Am and Cm in radwaste samples. The separated elements were determined by electrodeposition at the sodium hydrogen sulfate-sodium sulfate buffer solution followed by alpha-spectrometry. The recovery yields of Am and Cm were 85.2, respectively, from the synthetic solution of spent nuclear fuel sample. The amounts of 241Am and 2440m determined in radwaste sample solutions of condensate bottoms were at the range of 1.5-1.9 Bq/g and -1.7 Bq/g, respectively.
241Am, 244Cm, trans uranium, HDEHP extraction chromatography, electrodepositionradwaste samples, alpha spectrometry, 아메리슘, 큐륨, 초우란원소, HDEHP 추출크로마토그래피, 전착, 방사성폐기물 시료, 알파분광분석

 

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