Electrodeposition of 237Np for Alpha Spectrometry and Application to Spent Nuclear Fuel Samples

• Published in: Journal of nuclear fuel cycle and waste technology (Online) Vol. 4; no. 2; pp. 95 - 102
• Main Authors: 조기수, 김정석, 한선호, 박영재, 김원호, Kihsoo Joe, Jung-Suck Kim, Sun-Ho Han, Yeong-Jai Park, Won Ho Kim
• Format: Journal Article
• Language: Korean
• Published: 한국방사성폐기물학회 30.06.2006
• Subjects: 237Np; 음이온교환 크로마토그래피; anion exchange chromatography; 악티나이드 분리; 알파분광분석; actinides separation; alpha spectrometry; electrodeposition; 전착
• ISSN: 1738-1894; 2288-5471

알파분광법에 의한 의 정량방법을 검토하였다. 황산염 매질에서 전류세기, 전착시간 및 유기물 첨가제 둥의 변화에 따른 의 전착조건을 찾은 결과 A에서 유기첨가제 없이 시간 동안 전착하는 것이 효율적이었다. 을 4.16 Bq에서 0.0264 Bq(1ng) 까지 전착한 결과 농도가 낮을수록 전착율 및 재현성이 낮아졌으며 1 ng 까지 측정이 가능하였다. 사용후 핵연료 합성용액에서 을 분리한 후 알파분광법으로 측정하여 정량한 결과 (n=4)의 회수율을 나타내었다. 사용후 핵연료 시료용액 중 을 정량하였으며 계산 값과 비교한 결과 10% 이내에서 서로 일치하였다. Alpha spectrometry was studied for the determination of in spent nuclear fuel samples. The optimum condition for the electrodeposition of was obtained as follows : for hour of deposition time, at the current intensity of A and at sodium sulfate electrolyte without organic additive. The deposition yield and its reproducibility on was decreased as the amount of decreased from 4.16 Bq down to 0.0264 Bq(1ng). The recovery yield of determined by alpha spectrometry after separation in synthetic solution was (n=4). The contents of in spent nuclear fuel samples were determined and the result showed an agreement within 10% of a difference between the measurement and the calculation.