$^{67}Ga$ 생산용 화학처리 자동화 장치 개발

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.

< 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.

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.

종양 이식 백서에서 3-<131I>iodo-O-methyl-L-alpha-methyltyrosine 의 체내 동태 연구 - L-3-<131I>iodo-alpha-methyltyrosine 와 비교

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)

L - 3 [ 123I ] iodo - α - methyltyrosine 합성과 9L Glioma 이식 백서 분포조사

임상무(Sang Moo Lim),이종두(Jong Doo Lee),서용섭(Yong Sup Suh),전권수(Kwon Soo Chun),우광선(Kwang Sun Woo),정위섭(Wee Sup Chung),양승대(Seung Dae Yang),임종석(Jong Seok Lim),박현(Hyon Park),윤용기(Yong Ki Yun) 대한핵의학회 1995 핵의학 분자영상 Vol.29 No.1

N/A L-3[123I]iodo-methyltyrosine([123I] IMT) was synthesized by electrophilic radio-iodination using chloramine-T and Iodobead in phosphate buffered solution. And the biodistribution was examined in 9L glioma bearing rats. The radiosynthesis of [123I] IMT with iodobead was simpler and higher in radiochemical yield(88%) than the method using chloramine-T(83%) as radioiodinating reagent. The highest yield was obtained from the reaction using 1 piece of Iodobead, 200μg α- methyltyrosine in 100μl phosphate-buffered solution (pH 5.5) and the reaction was completed in 7min. 24hours after the injection, the biodistribution in 9L glioma transplanted rats revealed the in vivo deiodination, the excretion via kidney, and 3 times higher uptake in the tumor than normal brain. These results suggest the promising clinical use of [123I]IMT in the various ious malignancies.

지방육종형성 동물모델에서 123I-15-(p-iodophenyl)-3-R , S-methylpentadecanoic acid ( BMIPP ) 의 생체분포와 생체영상

최창운(Chang Woon Choi),임상무(Sang Moo Lim),이태섭(Tae Sup Lee),서용섭(Yong Sup Suh),우광선,정위섭(Wee Sup Chung),임수정(Soo Jung Lim),오옥두(Ok Doo Awh) 대한핵의학회 2001 핵의학 분자영상 Vol.35 No.5

N/A Purpose: 123I-labeled fatty acids have been used in the evaluation of regional myocardial energy metabolism. This study aimed to evaluate the usefulness of 123I-BMIPP as a liposarcorna-imaging agent. Materials and Methods: We compared in vitro uptakes between liposarcoma(SW872) and glioma(9L) cell lines, and examined biodistribution and in vivo images of 123I-BMIPP in liposarcoma-bearing nude mice. Cold-BMIPP was labeled with 123I using Cu2+ as catalyst. After purification by Sep-pak, radiochemical purity was determined by TLC. We compared cellular uptake between glioma and liposarcoma after incubation of 5, 10, 15, 30, 60, 120, and 180 mins with culture medium containing I-BMIPP. The difference in biodistribution was determined between non-feeding (water only) group for 18 hr and feeding group in normal mice (n=6/group) at 0.5, 2, and 24 hr. In liposarcoma-bearing nude mice model, liposarcoma, SW872, cell lines were injected subcutaneously into the left thigh of nude mice. The biodistribution of 123I-BMIPP was evaluated at 0.5, 2, and 24 hr (n=5 / group) and in vivo image of 123I-BMIPP was obtained with gamma camera at 2 and 24 hr in liposarcorna-bearing nude mice. Results: Radiolabeling yield and radiochemical purity were 95% and above 99%, respectively. SW872 cell line showed more increased uptake than 9L with 1.5 times at 180 mins. The clearance of 'I-BMIPP in various tissues was more delayed in the non-feeding group than in the feeding group, especially at delayed time (24 hr) in normal mice, and the major excreting organ was the gastrointestinal tract. In liposarcoma-bearing nude mice, tumor/blood ratio of 123I-BMIPP was 0.94, 0.75, and 1.38 and tumor/muscle ratio was 0.66, 1.53, and 1.11 at 0.5, 2, and 24hr, respectively. 123I-BMIPP was selectively localized in liposarcoma at 24 hr image. Conclusions: These results suggest that 123I-BMIPP can be used as a liposarcoma-imaging agent. (Korean J Nucl Med 200135:324-333)

I-123 표지 지방산의 체내 분포 및 대사 ( I ) - < I-123 > 15-( p-iodophenyl ) pentadecanoic acid ( IPPA )

고창순(Chang Soon Koh),이명철(Myung Chul Lee),정준기(June Key Chung),이동수(Dong Soo Lee),정재민(Jae Min Jeong),장영수(Young Soo Chang),서용섭(Yong Sup Suh) 대한핵의학회 1998 핵의학 분자영상 Vol.32 No.1

N/A I-123 labelled fatty acids are suitable for investigation of regional myocardial metabolism, so they are on the clinical trial. However, the precise properties of these materials are not characterized yet. We have synthesized phenylpentadecanoic acid and labeled this compound with I-123. The purpose of this study was to examine the stability, biodistribution, metabolism and SPECT imaging of [I-123]15-(p-iodophenyl)pentadecanoic acid(I-123-IPPA) that we made. The stability test of I-123-IPPA in serum of rat, mouse and human showed no free I-123 after 1 hour. In biodistribution study in mice for various time intervals after injection(5, 10, 15, 30, 60 minutes), uptake in myocardium was 14.5%ID/g(5 min), and 1.9%ID/heart(5 min), while uptake in muscles was 2.6%ID/g(5 min). Myocardium to blood ratio and myocardium to lung ratio increased for 5 min after injection and then decreased rapidly. Chromatographic data of rat blood and urine showed that little PPA was found in blood and urine 15-20 min after injection. The myocardial I-123-IPPA SPECT images of a dog with myocardial infarction showed defects similar to those of Tc-99m-MIBI and F-18-FDG. These data suggest that I-123-IPPA is quite stable in vitro and shows favorable biodistribution in mice. SPECT imaging with I-123-IPPA demonstrated infarct zone as photon defect in dog model of myocardial infarction. I-123-IPPA may be used for the evaluation of fatty acid metabolism in clinical trials in Korea.

신경내분비종양 진단에 있어서 I - 123 MIBG 조기 평면 영상과 SPECT 영상의 임상적 유용성

양승오(Seoung Oh Yang),최윤영(Yun Young Choi),이희경(Hee Kyung Lee),원경숙(Kyoung Sook Won),류진숙(Jin Sook Ryu),서용섭(Yong Sup Suh),신중우(Jung Woo Shin),김희중(Hee Jung Kim) 대한핵의학회 1996 핵의학 분자영상 Vol.30 No.4

N/A The purpose of this study was to evaluate the clinical usefulness of I-123 MIBG scintigraphy with early planar and SPECT image in the diagnosis of neuroendocrine tumors. We reviewed I-123 MIBG scintigraphies of 21 patients who had been suspected to have neuroendocrine tumors by CT or MRI findings. Early 4 hour planar and SPECT images were obtained in all patients and delayed (13-24 hour) planar images were performed in 17 patients. Final diagnoses were made by surgery, biopsy, or clinical follow up. Twelve patients were confirmed to have neuroendocrine tumors. With 4 hour planar and SPECT images, there were 9 true positives(6 pheochromocytomas, 1 paraganglioma, 1 neuroblastoma, and 1 medullary cancer of the thyroid), 8 true negatives(l adrenal cortical adenoma, 1 malignant fibrous histiocytoma, 1 adenoma in colon and 5 benign nonfunctioning adrenal tumors), l false positive(hepatocellular carcinoma) and 3 false negatives(l recurred medullary cancer of the thyroid, 1 liver metastasis of carcinoid tumor and 1 ganglioneuroma). The sensitivity and specificity of I-123 MIBG scintigraphy were 75% and 89%, respectively. SPECT images provided good anatomical correlation with CT or MRI. Delayed images showed increased tumor to background ratio in 5 out of 8 true positive patients, but did not change the diagnosis. In conclusion, early 4 hour images with I-123 MIBG is clinically convenient and useful method in the detection of neuroendocrine tumors, and SPECT images can provide good anatomical correlation with CT or MRI.

^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.

MC-50 싸이클로트론을 이용한 Mn-54 제법 연구

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.