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고전(古錢)내 귀금속 원소의 중성자 방사화 분석에 관한 연구
전권수,이철,채명준,이종두,정구순,Kwon Soo Chun,Chul Lee,Myung-Zoon Czae,Jong Du Lee,Koo Soon Chung 대한화학회 1993 대한화학회지 Vol.37 No.11
The determination of noble metals such as Ir, Au and Ag in the ancient coins has been studied. For the measurement of the activity of $^{192}Ir,\;^{198}Au\;and\;^{110m}Ag$, radiochemical separations including solvent extraction and ion-exchange chromatography were applied to reduce the interference of high energy ${\gamma}$-ray emitted from various radionuclides with long half-life. As a results, $10^{-11}$ g/g level of Ir could be detected and it was found that the three kinds of the detection limits, i.e., critical, detection, quantitative limit, calculated by the method proposed by Currie, were enhanced. Prior to the re-irradiation with neutron, inactive carrier was added in order to determine the recovery yield of Ir in the radiochemical separation. The average recovery yields of Ir, Au and Ag in the 5 coins were 65.3%, 98.5%, 99.5%, respectively. 옛 동전(銅錢)에 존재하는 이리듐, 금과 은 등 귀금속 원소들을 정량하기 위한 연구를 수행하였다. $^{192}Ir,\;^{198}Au$ 및 $^{110m}Ag$의 방사능 세기를 계측할 때, 반감기가 긴 핵종에서 방출된 큰 감마선 에너지에 의한 간섭을 감소시키기 위하여 용매추출, 이온교환 크로마토그래피 등 방사화학 분리를 적용하였다. 그 결과 이리듐을 $10^{-11}$ g/g양까지 정량할 수 있었고, 또한 Currie의 방법으로 계산한 3종류의 검출한계, 즉 임계, 검출, 정량한계를 향상시킬 수 있었다. 이리듐의 회수율을 결정하기 위하여 담체를 첨가하여 방사화학 분리를 한 후 중성자를 제조사하였다. 5개의 동전 중의 Ir, Au 및 Ag에 대한 평균 회수율은 각각 65.3%, 98.5%, 99.5%이었다.
< 51Cr > Cr ( III )-EDTA 착물 합성 및 < 51Cr > Cr ( III )-EDTA 주사후 두경부 방사능 계측에 의한 사구체 여과율 측정
양승대,임상무,전권수,서용섭,윤용기,박현,우광선,정위섭,오옥두,이종두 ( Seung Dae Yang,Sang Moo Lim,Kwon Soo Chun,Yong Sup Suh,Yong Ki Yoon,Hyun Park,Kwang Sun Woo,Wi Sup Chung,Jong Doo Lee,Ok Doo Oh ) 대한핵의학회 1994 핵의학 분자영상 Vol.28 No.3
The purpose of this study is to evaluate the clinical application of the no carrier added[Cr] Cr(UI) EDTA complexes, produced at Korea Cancer Center Hospital. The [Cr]Cr(lll) EDTA complexes, useful for measurement of GFR were prepared at room temperature in the presence of bicarbonate catalysts. The radiochemical purity of[Cr]Cr (Iil) EDTA was over 99% by paper electrophoresis. The time activity curves were obtained by counting the blood samples from 5 volunteers and counting the head and neck regions with whole body counter after inject#ion of the Cr EBTA, respectively, After the nonlinear regression, the area under curve was obtained. The plasma clearance of the Cr-EDTA was calculated with injected dose/AUC. The clearance rate calculated with the head and neck countmg data was in good agreement with t,he result from the plasma sample radioactivity at, 1-3 hrs after injection. From this result, the counting of head and neck region and the nonlinear regression by 2-compartment model could be applied for the measurement of the clearance rate. Using MIRD system, the absorbed radiation dose was calculated by residence time x S. The absorbed whole body radiation dose was negligibly small.
이동훈,김윤종,서용섭,양승대,전권수,허민구,윤용기,홍승홍,Lee, Dong-Hoon,Kim, Yoon-Jong,Suh, Yong-Sup,Yang, Seung-Dae,Chun, Kwon-Soo,Hur, Min-Goo,Yun, Yong-Ki,Hong, Seung-Hong 대한방사선방어학회 2003 방사선방어학회지 Vol.28 No.1
악성 종양 진단에 사용되고 있는 방사성 동위원소 $^{67}Ga$의 대량생산을 위한 자동화장치를 개발하였다. $^{67}Ga$은 조사된 $^{68}Zn$ 농축타켓에서 분리 생산하며 생산방법으로는 크게 용매추출법과 이온수지 법이 이용된다. 분리과정을 자동화하기 위해서 전도도 측정 장치, 화학처리 초자, 에어 공급 및 용액공급튜브, 밸브들로 이루어진 분액장치와, 이 장치를 구동하고 제어하는 PLC 기반 콘트롤러 및 사용자 직접제어용 모니터링 장치로 구성된 시스템을 개발하였다. 개발된 시스템을 사용함으로써 생산 중에 발생되는 불필요한 방사선 피폭으로부터 생산자를 보호할 뿐만 아니라, 생산시간의 단축, 생산효율의 증대로 $^{67}Ga$ 대량 생산이 가능하게 되었다. The automatic system for $^{67}Ga$ production using for the diagnosis of malignant tumor has been developed. A solvent extraction and an ion exchange chromatography were used for the separation $^{67}Ga$ from the irradiated enriched $^{68}Zn$. This system consisted of a solvent separation unit which was composed of micro conductivity cells, air supply tubes, solvent transfer tubes, solenoid valves and glasses, a PLC based controller and a PMU user interface unit for automation. The radiation exposure to the workers and the production time can both be reduced by employing this system during the $^{67}Ga$ production phase. After all, the mass production of $^{67}Ga$ with high efficiency was possible.
최창운,양승대,우광선,정위섭,임수정,서용섭,전권수,안순혁,이종두,홍성운,임상무 ( Chang Woon Choi,Seung Dae Yang,Kwang Sun Woo,Wee Sup Chung,Soo Jung Lim,Yong Sup Suh,Kwon Soo Chun,Soon Hyuk Ahn,Jong Doo Lee,Sung Soon Hong,Sang Moo Lim 대한핵의학회 1998 핵의학 분자영상 Vol.32 No.3
Purpose : The aim of this sutdy was to evaluate the feasibility of 3-[131I]Iodo-O-methyl-L-a-methyltyrosine ([131I]OMINT) as an agent for tumor image. Materlals and Methods: After synthesis of 4-O-methyl-L-a-methyltyrosine (OMAMT), OMAMT was labeled with 131I using Iodogen method. In viro cellular uptake study was performed using 9 L gliosarcoma cells at various time points upto 4 hr. The biodistribution (five rats implanted with the 9 L gliosarcoma cells per group) was evaluated at 30 min, 2 hr, 24 hr after iv injection of 3.7 MBq [131I]OMIMT or L-3-[131I]iodo-a-methyltyrosine ([131I]IMT). Gamma camera images were obtained at 30min, 2 hr, and 24 hr. Results : [131I]OMINT uptake was 3.3 times and 2.5 times higher than [131I]IMT uptake at 30 min and 60 min, respectively and same after 2 hr in in vitro sutdy using 9L gliosarcoma cells. Maximum accumulation in tumor occurred at 30 min for both [131IOMINT and [131I]IMT in tumor bearing rats. The tumor uptake of [131I]OMINT was significantly higher than that of [131I]IMT in tumor bearing rats. The tumor uptake of [131I]OMIMT was significantly higher than that of [131I]IMT at early time point studied (3.74 +- 0.48 vs 0.38 +- 0.17% ID/g at 30 min and 2.40 +- 0.17 vs 0.24 +- 0.03% ID/g at 2 hr, respectively, p<0.01). However, the tumor uptake of both radiolabels were not significantly different at 24 hr (0.04 +- 0.01 vs 0.05 +- 0.01% ID/g). Tumor was visualized as early as at 30 min in gamma camera images. Conclusion : These data suggested that [131I]OMIMT might be a useful tumor imaging agent and has more advantage for the tumor imaging compared to [131I]IMT. (korean J NuclMed 1998;32;290-7)
MC - 50 싸이클로트론을 이용한 123I 제법 연구
이종두(Jong Doo Lee),서용섭(Yong Sup Suh),양승대(Seung Tae Yang),전권수(Kwon Soo Chun),한현수(Hyon Soo Han) 대한핵의학회 1991 핵의학 분자영상 Vol.25 No.2
N/A 123I, which is applied for the thyroid and other in vivo kinetic study, has a special role in life sciences. The 159 KeV r-ray from 123I is almost ideally appropriate for the current imaging instrurnentation. Its decay mode (electron capture) and short half-life (13.3 hr) reduced the burden of radiation dose to the patients, and its chemical property makes it easy to synthesize the labelling compounds. In this experiment, the production of 123I via the nuclear reaction 124Te(p,2n)123I with 28 MeV protons was sutdied. TeO, is used as a target material, because it has goad physical properties. The target was prepared with TeO, powder and was rnolten into a ellipsoidal cavity (a=14mm, b=10 mm, 270.8 mg/cm thick) of pure platinum. The irradiation was carried out in the external proton beam with incident energies range from 28 MeV to 22 MeV, and current was 30pA. The loss of TeO, target was significantly reduced by using 4-cooling system in irradiation. The dry distillation method was adopted for the separation of 123I from irradiated target, and when it was kept 5 minutes at 780C, its result was quantitative. The loss of the target material (TeO,) was below 0.2% for each production run and 'I from the dry distillation apparatus was captured with 0. 01 N NaOH in NaI form, then the pH of the solution was adjusted to 7.5-9.0 with HC1/NaOH. The Na123I solution was passed through 0.2pm membrane filter, and sterilized under high pressure and temperature for 30 minutes. The prodvction of 'I is acceptable for clinical application based on the quality of USP XXI.