http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
^27Al(p,α pn)핵반응에 의한 무담체 ^22Na 제법 연구
유국현,서용섭,양승대 東國大學校 1998 東國論叢 Vol.37 No.-
A method for the production of no-carrier added(NCA) ^22Na was developed via ^27Al(p, ㄷαpn) nuclear reaction with 50.5MeV protons. the half life of ^22Na is 2.6 years and main γ-energy is 1274.5keV and it is used standard source and sodium catabolism study. The cross-section and thick target yield for the reaction was measured in detail in the energy range of 50.5→20.2MeV in order to determine the optimum conditions for the production of ^22Na. the maximum cross-section for the production of ^22Na was 40.8 mbarn at 43.85MeV. the calculated production yield of ^22Na by 50.5MeV protons on aluminium was 60.9μCi/μAh. The seperation of ^22Na was carried out by ion exchange, precipitation and diffusion. It was found that ion exchange column operation using AG50W-X4 resin was the most efficient method among them.
유국현,서용섭 東國大學校 2000 東國論叢 Vol.39 No.-
The half-life of ^54Mn is 312.2 days and main γ-energy is 835keV, therefore it is used as a standard source for a multi-channel analyzer and a dose calibrator and managanese catabolism study in human body. In this paper, a method for the production of no carrier added ^54Mn was studied via ^54Cr(p,n) and ^59Co(p, αpn), with MC-50 cyclotron and described chemical isolation method of ^54Mn from a irradiated target by ion exchange resin. Chromium and cobalt were used as target materials. The production yields of ^54Mn by 50.5 MeV protons was 4.5 μCi.μ/Ah on chromium target and 11.85 μCi/μAh on cobalt target. The cross-section and thick target yield of ^59Co(p, αpn)^54Mn reaction were measured in the energy range of 50.5→22.2MeV in order to determine the optimum conditions for the production of ^54Mn. the maximum cross-section was 47.48 mbarn at 41.2MeV.
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.
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.
< 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.