• 대한방사성의약품학회지
• /
• 제2권2호
• /
• pp.84-95
• /
• 2016

Considerably increasing interest in using the theranostic isotopes/ isotope pairs of radiometals like $^{44/47}Sc$ and $^{64/67}Cu$ for diagnosis and/or therapeutic applications in the nuclear medicine procedures necessitates its reliable production and supply. Separation and purification of no-carrier-added (NCA) isotopes from macro quantitates of the irradiated target matrix along with other impurities is a cardinal procedure amongst several other steps involved in its production. Multitudinous methods including but not limited to liquid-liquid (solvent) extraction, extraction chromatography (EXC), ion exchange, electrodeposition and sublimation are routinely applied either solitarily or in combination for the separation and purification of radioisotopes depending on their production routes, radioisotope of interest and impurities involved. However, application of EXC though has shown promises towards the numerous separation techniques have not received much attention as far as its application prospects in the field of nuclear medicine are concerned. Advances in the recent past for application of the EXC resins in separation and purification of the several medically important radioisotopes at ultra-high purity have shown promising behavior with respect to their operation simplicity, acidic and radiolytic stability, separation efficiencies and speedy procedures with the enhanced and excellent extraction abilities. In this mini review we will be talking about the recent developments in the application and the use of EXC techniques for the separation and purification of $^{44/47}Sc$ and $^{64/67}Cu$ for medical applications. Furthermore, we will also discuss the scientific and practical aspects of EXC in the view of separation of the NCA trace amount of radionuclides.

• 대한기계학회논문집B
• /
• 제40권7호
• /
• pp.471-475
• /
• 2016

본 연구는 의료용 동위원소 생산공정에서 발생하는 방사성폐기물을 저장하는 장기저장소의 온도를 두 가지 방법으로 평가한 결과를 보여준다. 방사성폐기물에서 발생하는 열을 Volume source와 Point source로 가정하여 장기저장소의 온도를 평가한 결과, 폐기물 저장위치에 따른 최대온도분포는 유사하게 나타났으나 그 크기에 있어서 최대 $5^{\circ}C$ 정도의 차이를 보였다. 따라서, 개념설계를 위해서는 해석 시간이 오래 걸리는 Volume source를 이용한 3차원 해석보다는 Point source를 이용한 2차원 해석이 보다 효율적이지만, 상세 설계를 위한 정확한 해석 결과를 얻기 위해서는 Volume source를 이용한 3차원 해석이 수반되어야 함을 알 수 있다.

• Journal of Radiation Protection and Research
• /
• 제15권2호
• /
• pp.113-122
• /
• 1990

원자력병원에 설치된 MC-50 의학용 싸이클로트론은 4년간의 장비 도입 계획, 장비 인수 및 설치 그리고 빔 특성조사를 거쳐서 1986년 11월부터 가동을 시작하였다. MC-50 싸이클로트론은 현재 중성자치료 및 방사성 동위원소 생산에 이용되고 있다. 1989년 12월 현재, 중성자선 치료는 총 179명(1852 sessions)의 환자에서 시행되었다. 핵의학 분야에 이용되는 방사성 동위원소의 생산은 표적운반, 표적용융, 빔 진단 그리고 화학적 처리과정에 관한 문제들을 해결하기 위한 다각적인 연구를 거친 후 1989년 3월부터 시작하였다. 이 논문은 중성자 치료와 동위원소 생산에 이용된 MC-50 싸이클로트론의 운영 현황 및 장비의 특성에 대하여 기술하였으며, 또한 1989년도의 운영결과 및 제반 문제점들을 요약하였다. 1989년도 총 운전시간은 1252.5시간이었으며 이 중 중성자 치료에 400시간을 이용하였다(599 sessions). 동위원소 생산에는 832.5시간을 이용하여 총 1695mCi(Ga-67 : 1478mCi, Tl-201 : 107 mCi, I-123 : 25mCi, In-111 : 85mCi)를생산하였다. 빔 특성실험 및 기타 연구에는 20시간을 이용하였다. 1989년도의 가동율은 88.2%이었으며 전년도의 71.0%에 비하여 현저히 향상되었다.

• 헤리티지:역사와 과학
• /
• 제36권
• /
• pp.241-266
• /
• 2003

Glass pieces excavated from Mireuksa Temple dated $7^{th}$ century A.D. were characterized by chemical composition, specific gravity and melting point. Lead isotope ratios of lead glasses were also compared with those of lead ore to attribute which lead ore was delivered for making lead glass. It was known that some lead glasses found in Japan were similar with those of Mireuksa Temple as comparing the data of chemical composition and lead isotope ratios. Characteristics of lead glass from Mireuksa Temple Thirty five glass pieces of Mireuksa Temple were analyzed for five oxides and found that all was lead glass system(PbO-$SiO_2$) with the range of 70~79% for PbO and 20~28% for $SiO_2$. The concentrations of oxides such as $Al_2O_3$, $Fe_2O_3$ and CuO were below 0.4%, 0.3% and 0.9%, respectively. Principal component analysis(PCA) as a statistical method was carried out to classify glasses with the similarities of chemical concentrations. The result of PCA has shown that three groups of glasses were created according to the excavation positions and two major oxides(PbO and $SiO_2$) greatly contributed to the dispersion of glasses on principal component 1(PC1) axis and trace element oxides($Al_2O_3$ and $Fe_2O_3$) for PC2 axis. Most of lead glasses were greenish by the efficacy of iron and copper oxides and some showed yellowish-green. The gravity of lead glasses was about 4.4~5.4 and estimated melting point was near $670^{\circ}C$. Lead isotope ratios of glasses were analyzed and found quite close to a lead ore from the Bupyeong mine in Gyeonggi-do. Comparison with lead glasses found in Japan Lead glasses of Mireuksa Temple were compared with those of Japan on the basis of chemical and physical data. Chemical compositions of Japanese lead glasses dated $7^{th}{\sim}8^{th}$ century A.D. were nearly similar with those of Mireuksa Temple but lead isotope ratios of those were separated into two groups. Three distribution maps of lead ores of Korea, Japan and China with lead isotope ratios were applied for lead glasses found in Japan. The result have shown that the locations of lead glasses from Fukuoka Prefecture coincided with the region of northen part of Korea and similar with those of Mireuksa Temple and lead glasses from Nara Prefecture dated $8^{th}$ century A.D. were located in the region of Japanese lead ore. This research has demonstrated that lead glasses of Mireuksa Temple conveyed to Miyajidake site, Fukuoka Prefecture around $7^{th}$ century A.D. and glass melting pots and glass beads excavated from Nara Prefecture confirmed the first use of Japanese lead ore for production of lead glasses from the end of $7^{th}$ century A.D.

• 한국자기공명학회논문지
• /
• 제15권2호
• /
• pp.115-127
• /
• 2011

A newly developed cost-effective approach to prepare $^{15}N/^{13}C$-labeled protein for NMR studies is presented. This method has been successfully applied to isotopically labeling of PTK6 SH2 domain and MTH 1880 protein. The production method generates cell density using a growing media containing $^{15}NH_4Cl$, $^{12}C_6$-D-glucose. Following a doubling time period for unlabeled metabolite exhaustion and then addition $^{13}C_6$-D-glucose into a M9 growing media, the cells are induced. Our results demonstrate that in order to get full incorporation of $^{13}C$, the isotopes are not totally required during the initial growth phase before induction. The addition of small amounts of $^{13}C_6$-D-glucose to the induction phase is sufficient to obtain more than 95% incorporation of isotopes into the protein. Our optimized protocol is two-thirds less costly than the classical method using $^{13}C$ isotope during the entire growth phase.

• Nuclear Engineering and Technology
• /
• 제48권3호
• /
• pp.613-623
• /
• 2016

Molybdenum-99 ($^{99}Mo$) is the most important isotope because its daughter isotope, technetium-99m ($^{99m}Tc$), has been the most widely used medical radioisotope for more than 50 years, accounting for > 80% of total nuclear diagnostics worldwide. In this review, radiochemical routes for the production of $^{99}Mo$, and the aspects for selecting a suitable process strategy are discussed from the historical viewpoint of $^{99}Mo$ technology developments. Most of the industrial-scale $^{99}Mo$ processes have been based on the fission of $^{235}U$. Recently, important issues have been raised for the conversion of fission $^{99}Mo$ targets from highly enriched uranium to low enriched uranium (LEU). The development of new LEU targets with higher density was requested to compensate for the loss of $^{99}Mo$ yield, caused by a significant reduction of $^{235}U$ enrichment, from the conversion. As the dramatic increment of intermediate level liquid waste is also expected from the conversion, an effective strategy to reduce the waste generation from the fission $^{99}Mo$ production is required. The mitigation of radioxenon emission from medical radioisotope production facilities is discussed in relation with the monitoring of nuclear explosions and comprehensive nuclear test ban. Lastly, the $^{99}Mo$ production process paired with the Korea Atomic Energy Research Institute's own LEU target is proposed as one of the most suitable processes for the LEU target.

• Ocean and Polar Research
• /
• 제30권4호
• /
• pp.407-418
• /
• 2008

Seawater samples were collected at discrete depths from five stations across the polar front in the Drake Passage (Antarctic Ocean) by the $20^{th}$ Korea Antarctic Research Program in December, 2006. Nitrate concentrations of seawater increase with depth within the photic zone above the depth of Upper Circumpolar Deep Water (UCDW). In contrast, ${\delta}^{15}N$ values of seawater nitrate decrease with depth, showing a mirror image to the nitrate variation. Such a distinct vertical variation is mainly attributed to the degree of nitrate assimilation by phytoplankton as well as organic matter degradation of sinking particles within the surface layer. The preferential $^{14}{NO_3}^-$ assimilation by the phytoplankton causes $^{15}{NO_3}^-$ concentration to become high in a closedsystem surface-water environment during the primary production, whereas more $^{14}{NO_3}^-$ is added to the seawater during the degradation of sinking organic particles. The water-mass mixing seems to play an important role in the alteration of ${\delta}^{15}N$ values in the deep layer below the UCDW. Across the polar front, nitrate concentrations of surface seawater decrease and corresponding ${\delta}^{15}N$ values increase northward, which is likely due to the degree of nitrate utilization during the primary production. Based on the Rayleigh model, the calculated ${\varepsilon}$ (isotope effect of nitrate uptake) values between 4.0%o and 5.8%o were validated by the previously reported data, although the preformed ${\delta}^{15}{{NO_3}^-}_{initial}$ value of UCDW is important in the calculation of ${\varepsilon}$ values.

• 보존과학회지
• /
• 제30권4호
• /
• pp.345-351
• /
• 2014

인용사지에서 출토된 청동기 5점으로부터 채취한 시료를 대상으로 원료의 기원과 이동을 확인하기 위해 성분분석 및 납동위원소비 분석을 실시하였다. 인용사지에서 출토된 청동기는 구리 및 주석의 이원계 합금으로 제작되어 납이 인위적으로 첨가되지 않음을 확인할 수 있었다. 또한 출토 청동기의 납동위원소비 분석 결과, Mabuchi(1985)의 분포도에 의해 한반도 남부 및 중국 남부 지역에 포함됨을 확인하였으며, 한반도 납동위원소 분포도에 도시하여 태백산분지인 Zone 2 및 옥천변성대에 해당하는 Zone 3에 위치함을 알 수 있었다. 대상 유물은 모두 납의 함량이 상당히 적은 주석청동으로, 이때의 납동위원소비는 구리 광석의 산지에서 기인하는 것으로 추정할 수 있다. 납동위원소비 분석은 납을 미량으로 포함한 모든 유물에 적용 가능하므로, 다양하게 해석할 수 있으며, 추가적인 데이터의 확보와 연구를 통해 산지 추정 연구의 신뢰성을 높일 수 있을 것이라 판단된다.

• 자원환경지질
• /
• 제57권3호
• /
• pp.343-352
• /
• 2024

경복궁 전각 청기와에 사용된 납유의 발색 원리와 용융제로 사용된 납의 산지를 확인하기 위해 성분 분석과 납동위원소비 분석을 실시했다. 청기와 31점을 녹색, 청색, 황색으로 구분하여 표면에 시유된 납유의 성분을 분석한 결과 Pb, Si, Cu가 주성분으로, Fe, Ca, Mg, Al 등이 미량으로 검출되었다. 청색 납유에서는 Cu의 함량이 높았으며 황색 또는 갈색의 납유에서는 Cu는 검출되지 않았고 Fe의 함량이 높게 나타났다. 따라서 납유의 제작에 용융제로 납을, 발색제로 산화동을 사용했음을 알 수 있었다. 또한 경복궁 청기와에 사용된 납유의 납동위원소비는 한반도 납동위원소비 분포도에서 충청도와 전라도를 포함하는 zone 3 영역에 도시되었으며, 납유의 용융제는 이들 지역에서 산출되는 방연석 등을 사용했을 것으로 추정된다. 삼국과 통일신라시대 녹유의 납동위원소비는 대부분 한반도를 벗어나 위치하여 납의 산지가 변화되었음을 알 수 있었다. 특히 녹유 전돌의 납동위원소비를 통해 주변국과의 교류를 추정할 수 있었으며 동일 사찰에서 출토된 녹유 전돌의 납동위원소비가 서로 달라 다른 시기 또는 다른 공방에서 제작된 것으로 판단할 수 있었다.

• Membrane and Water Treatment
• /
• 제4권4호
• /
• pp.265-275
• /
• 2013

China is one of the countries with the highest reserves of coal bed methane (CBM) in the world. Likewise, the CBM industry is significantly growing in China. However, activities related to CBM development have led to more environmental problems, which include serious environmental damage and pollution caused by CBM-produced water. In this paper, the detailed characteristics of CBM-produced water in the southern Qinshui Basin were investigated and analyzed and compared with local surface water and coal mine drainage. Most of CBM-produced water samples are contaminated by higher concentration of total dissolved solids (TDS), K (Potassium), Na (Sodium) and $NH_4$. The alkalinity of the water from coalmines and CBM production was higher than that of the local surface water. The concentrations of some trace elements such as P (Phosphorus), Ti (Titanium), V (Vanadium), Cr (Chromium), Ni (Nickel), Zn (Zinc), Ge (Germanium), As (Arsenic), Rb (Rubidium), and Pd (Palladium) in water from the coalmines and CBM production are higher than the acceptable standard limits. The ${\delta}D$ and ${\delta}^{18}O$ values of the CBM-produced water are lower than those of the surface water. Similarly, the ${\delta}D$ values of the CBM-produced water decreased with increasing drainage time.