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Journal of the Korean Chemical Society (JKCS)

ISSN 1017-2548(Print)
ISSN 2234-8530(Online)
Volume 44, Number 6
JKCSEZ 44(6)
December 20, 2000 

 
Title
Cation Exchange Separation and Determination of Ruthenium in a Simulated Spent Nuclear Fuel

모의 사용후핵연료에 함유된 루테늄의 양이온교환 분리 및 정량
Author
Moo-Yul Suh , Se-Chul Sohn, Chang-Heon Lee, Kwang-Soon Choi, Do-Yang Kim, Yeong-Jae Park, Kyoung-Kyun Park, Kwang-Yong Jee, Won-Ho Kim

서무열, 손세철, 이창헌, 최광순, 김도양, 박영재, 박경균, 지광용, 김원호
Keywords
Abstract
사용후핵연료에 미량 함유되어 있늘 루테늄 분석법을 개발하기 위하여 양이온교환법을 이용한 분리 조건을 조사하였다. 산분해 장치를 사용하여 9:1 몰비의 혼합산(HCl-HNO₃)으로 루테늄 시료를 용해시켰다. 염산 용액에서 루테늄의 흡수스펙트럼과 이온교환 거동 조사를 통해 분리에 관련된 루테늄의 화학종을 제시하엿다. 미량의 루테늄이 함유되어 있는 우라늄 용액을 양이온교환수지(AG 50W×8, 100~200mesh) 분리관(0.7×0.8 cm)에 넣고 0.5M 염산으로 루테늄을 용리시켰다. 모의 사용후핵연료에 확립된 루테늄 분리방법을 적용하고 유도결합 플라스마 원자방출분광분석법으로 분석한 결과 루테늄 회수율은 98.5%이었다.

Cation exchange separation and inductively coupled plasma atomic emission spectrometric(ICP-AES) determination of ruthenium in HCl solutions were studied to quantitatively determine ruthenium in spent nuclear fuels. Ruthenium-bearing samples were dissolved with the mixed acid solution(9 : 1 mole ratio, HCl-HNO₃) using an acid digestion bomb. Based on the absorption spectra and ion exchange behaviour of ruthenium in hydrochloric acid media, its possible chemical species were discussed. On a cation exchange column (0.7 × 8.0 cm) packed with AG 50W × 8(100~200 mesh) and equilibrated with 0.5 M HCl, ruthenium was eluated with 0.5 M HCl while uranium was retained on the column. The established separation method was applied to a simulated spent nuclear fuel and resulted in the recovery of 98.5% with a relative standard deviation of 0.7%.

Page
526 - 532
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