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표형열,박양순,박순달,박경균,송병철,박용준,지광용,Pyo, Hyung-Yeal,Park, Yang-Soon,Park, Sun-Dal,Park, Kyoung-Kyun,Song, Byung-Chul,Park, Yong-Joon,Jee, Kwang-Yong 한국방사성폐기물학회 2006 방사성폐기물학회지 Vol.4 No.1
Ion exchange resin particles should not be found in steam generator(S/G) sludge. The suspicious spherical resin particles observed in S/G sludge sample were characterized for particle size distribution under optical microscope using the micro-technique, for element analysis by the electron probe micro analysis (EPMA), and for molecular identification by the IR spectroscopy. The particle sizes are distributed from 1 to $200{\mu}m$ for the sludge, while 40 to $500{\mu}m$ for the spherical resin particles. The results of the elemental analysis showed different major impurities: Si, Al, Mn, Cr, Ni, Zn and Ti for the sludge particles, while Si, Cu, Zn for the spherical resin particles. However, both particles contain Fe as a matrix of magnetite $(Fe_3O_4)$. IR spectrum of the spherical particles was not quite similar to the IR spectrum of ion exchange resins used in S/G system. These results indicate that the spherical particles are not related to ion exchange resin particles and may be formed by the process of the sludge formation.
밀폐형 극초단파 산분해법을 이용한 중${\cdot}$저준위 방사성폐기물의 성분 원소 분석
이정진,표형열,전종선,이창헌,지광용,지평국,Lee Jeong-Jin,Pyo Hyung-Yeal,Jeon Jong-Seon,Lee Chang-Heon,Jee Kwang-Yong,Ji Pyung-Kook 한국방사성폐기물학회 2004 방사성폐기물학회지 Vol.2 No.4
The conditions are obtained for the decomposition of solid radioactive wastes, including ion exchange resin, zeolite, charcoal, and sludge from nuclear power plant. In the process of decomposing the radioactive wastes was used the microwave acid digestion method with mixed acid. The solution after acid digestion by the following method was colorless and transparent. Each solution was analyzed with ICP-AES and AAS and the recovery yield for 5 different elements added into the simulated radioactive wastes were over $94{\%}$. The elemental analysis of destructive low and medium level radioactive wastes by the proposed microwave acid digestion conditions concerning the chemical characteristics of each radioactive waste are expected to be useful basic data for development of optimal glass formulation.
추출크로마토그래피와 유도결합플라스마 원자방출분광법을 이용한 이산화우라늄분말 중 미량금속불순물 분석
최광순,이창헌,표형열,한선호,서무열,엄태윤,이계호,Choi, Kwang-Soon,Lee, Chang-Heon,Pyo, Hyung-Yeal,Han, Sun-Ho,Suh, Moo-Yul,Eom, Tae-Yoon,Lee, Gae-Ho 대한화학회 1993 대한화학회지 Vol.37 No.9
$UO_2$ 분말에 미량 함유되어 있는 금속불순물들을 신속하게 정량하고 분석과정에서 발생되는 폐액의 양을 줄이기 위하여, 우라늄용액으로부터 미량금속불순물들을 분리함과 동시에 ICP-AES로 분석할 수 있는 장치를 구성하였다. 미량금속불순물들을 분리하기 위하여, 폴리에틸렌으로 제작한 분리컬럼(내경 : 0.7cm, 길이 : 7 cm)에 TBP(tri-n-butyl phosphate)를 입힌 테프론 분말(약 $330\;{\mu}m$)을 충진하고, 분리컬럼의 출구를 ICP-AES의 시료주입구에 연결시켰다. $UO_2$ 분말에 미량 함유되어 있는 몰리브덴을 비롯한 11개 원소를 분리와 동시에 정량할 수 있었으며, 이들 원소들에 대한 회수율은 용매추출법에서와 거의 동일한 $91{\sim}110%$로서 핵연료 제조공정의 품질관리에 적용이 가능하였다. An ICP-AES system directly connected with a separation column was used in order to determine the trace elements in $UO_2$ powder promptly and reduce the volume of the waste solution. The outlet of a separation column, which was filled with Teflon powder ($330\;{\mu}m$) coated with tri-n-butyl phosphate (TBP) as extractant, was directly connected with sample injection tube of ICP-AES. Eleven elements including molybdenum in $UO_2$ powder were separated and determined simultaneously. Recoveries of these elements were $91{\sim}110%$ and these results were agreed with those of solvent extraction methods. This method was applicable to quality control in manufacturing nuclear fuel.