http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
Determination of Boron Isotopic Ratio by Using an Alpha Track Technique
Yong Joon Park*,Hyung Yeal Pyo,Kyuseok Song,Byoung Chul Song,Kwang Yong Jee,Won-Ho Kim 대한화학회 2006 Bulletin of the Korean Chemical Society Vol.27 No.10
The determination of the boron isotopic ratio in solutions was achieved by means of a solid state track detector by using an alpha track. The neutron flux was optimized by using a Cd-foil to find the optimum conditions for counting the number of alpha tracks on the selected solid detector caused by the (n, a) nuclear reaction of boron. The home-made multi-dot detector plate was utilized in this study to increase the reproducibility of the measurement by uniformly drying the boron solution within the marked circle area on the detector plate. The experimental results of this study verified that the 11B/10B isotopic ratio can be measured by observing the number of alpha tracks for different concentrated standard solutions with various isotopic compositions. This technique was applied to the determination of 10B enrichment factor in a biological sample for a boron neutron capture therapy.
Determination of Boron Isotopic Ratio by Using an Alpha Track Technique
Park, Yong-Joon,Pyo, Hyung-Yeal,Song, Kyu-Seok,Song, Byoung-Chul,Jee, Kwang-Yong,Kim, Won-Ho Korean Chemical Society 2006 Bulletin of the Korean Chemical Society Vol.27 No.10
The determination of the boron isotopic ratio in solutions was achieved by means of a solid state track detector by using an alpha track. The neutron flux was optimized by using a Cd-foil to find the optimum conditions for counting the number of alpha tracks on the selected solid detector caused by the (n, $\alpha$) nuclear reaction of boron. The home-made multi-dot detector plate was utilized in this study to increase the reproducibility of the measurement by uniformly drying the boron solution within the marked circle area on the detector plate. The experimental results of this study verified that the $^{11}B/^{10}B $ isotopic ratio can be measured by observing the number of alpha tracks for different concentrated standard solutions with various isotopic compositions. This technique was applied to the determination of $^{10}B$ enrichment factor in a biological sample for a boron neutron capture therapy.
Jeong-JIn Lee,Hyung-Yeal Pyo,Jong-Seon Jeon,Chang Heon Lee,Kwang-Yong Jee,Pyung-Kook Ji 한국방사성폐기물학회 2004 방사성폐기물학회지 Vol.2 No.4
원자력 발전소에서 발생하는 고체 방사성 폐기물인 이온교환수지, 제올라이트, 활성탄 및 슬러지 에 포함된 성분 원소 분석을 위한 산분해 조건을 확립하였다. 방사성 폐기물의 분해 에는 흔합산을 이용한 밀폐형 극초단파 산분해법을 사용하였으며, 제안한 방법에 따른 산분해 후의 용액은 맑고 색이 없는 투명한 상태임을 확인할 수 있었다. 또한, 산분해 과정을 거친 각각의 용액 시료는 ICP-AES와 AAS를 사용하여 분석하였고, 모의 방사성 폐기물에 첨가한 5종의 금속 원소들은 이상의 높은 회수율을 보여주었다. 화학적 특성을 고려하여 제안된 산분해 조건에 의해 용액화된 중저준위 방사성 폐기물의 성분 원소 분석은 최적의 유리화 기술 개발을 위한 기초 자료로 유용하게 사용될 수 있을 것으로 판단된다. 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 . 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.
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.