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방사성폐기물 시료 중 $\^{241}$Am과 $\^{244}$Cm의 정량
조기수,김태현,전영신,지광용,김원호,Joe Kih Soo,Kim Tae Hyun,Jeon Young Shin,Jee Kwsng Yong,Kim Won Ho 한국방사성폐기물학회 2005 방사성폐기물학회지 Vol.3 No.1
Anion exchange chromatography and HDEHP extraction chromatography using DTPA-lactic acid as an eluent were applied in series for the separation of $^{241}$Am and $^{244}$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 $^{241}$Am and $^{244}$Cm were 85.2$\pm$$15.3\%$, 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.