• Proceedings of the Korean Nuclear Society Conference
• /
• 2004.10a
• /
• pp.676-677
• /
• 2004

• Korean Journal of Digital Imaging in Medicine
• /
• v.16 no.1
• /
• pp.61-67
• /
• 2014

The demand of cyclotron for PET (positron emission tomography) has rapidly grown as the more use of PET or PET-CT equipment requires the increased amount of radioactive isotopes for clinical positron emission. While research on failure statistics of medical equipment used in medical centers has continued to be done, the analysis and study on failure statistics of cyclotron have rarely been conducted. However, the growing demand shows the urgency of systematical management guideline and countermeasures for device failure to minimize any supply delay of radiopharmaceuticals occurred by such failure and complains from waiting patients for PET-CT diagnosis. Therefore, this study aims to analyze the failure report from Minitrace equipped in cyclotron which is owned by the department of nuclear medicine at Yeungnam University Medical Center and draws on the data to build effective management system for cyclotron.

• Nuclear Engineering and Technology
• /
• v.21 no.3
• /
• pp.216-222
• /
• 1989

The MC-50 cyclotron at Korea Canter Center Hospital is now operational for neutron therapy and medical radioisotope production. Design features, mechanical structures and operating characteristics of the MC-50 are described in this paper. Optimum operating condition for this cyclotron has been determined by the repetitive running, and the performances of the internal beam have been investigated through the measurements of intensity and spatial distribution of the internal beam as a function of the radius of the cyclotron. Routinely, the 40 $\mu$A of 50 MeV protons have been obtained at first Faraday cup with a extraction efficiency of 61%.

• The Korean Journal of Nuclear Medicine
• /
• v.36 no.2
• /
• pp.133-139
• /
• 2002

Purpose: Scintillation Proximity Assay (SPA) does not require the physical separation of receptor bound form from free form. SPA was applied to the study of interaction of human chorionic gonadotropin (hCG) and $anti-{\alpha}$ hCG in serum. Materials and methods: $Anti-{\alpha}$ hCG was biotinylated for the binding to streptavidin. The assay was based on the simple competitive binding method between $[^{125}I]hCG$ and the hCG in sample serum, with $anti-{\alpha}$ hCG-coated beads. Aliquots of biotinylated $anti-{\alpha}$ hCG were dispensed into scintillation vials containing $100{\mu}{\ell}\;[^125}I]hCG\;and\;200{\mu}{\ell}$ of either a standard concentration of hCG for preparation of standard curve or unknown sample, and incubated for 20 min. at room temperature. Then $20{\mu}{\ell}$ streptavidin-coated beads were added to vials, and finally incubated for 10 min at room temperature. Values for unknown samples were then calculated from the standard curve. Results: Optimal background counts were certificated using varied radioactivity of radionuclides. Appropriate standard curve was obtained from SPA method successively, and the concentration of hCG from unknown serum was determined by standard curve. The result from SPA assay was similar to that of RIA. Conclusion: This observation confirms that SPA method could be useful for clinical diagnosis.

• Journal of Radiation Protection and Research
• /
• v.26 no.3
• /
• pp.161-165
• /
• 2001

We have developed a position-sensitive proton recoil telescope (PSPRT) which employs a position-sensitive photomultiplier (PS-PMT) and a scintillator for both a radiator and a proton-detector. This system is expected to achieve high energy resolution under a large solid angle, because it enables to obtain the information not only on the proton energy but also the recoil angle from the position data for both detectors. The response of the PSPRT for 14.1 MeV mono-energetic neutrons was measured, and the PSPRT proved to be operating as expected.

• Proceedings of the Korean Vacuum Society Conference
• /
• 2012.08a
• /
• pp.262-262
• /
• 2012

A multi-purpose cyclotron, MC50 has been operated to provide multi-ions of proton, deuteron and alpha at Korea Institute of Radiological and Medical Sciences (KIRAMS). Neutron is also produced through the (p,n) nuclear process with a Be target. However, a wide spectrum of current of ions is requested by beam users for carrying their various application fields. Therefore a simulation study is requested on the design of an axial injection system for high current proton and alpha beam extraction for radio-isotope productions and scientific researches. The purpose of this study is seeking a relatively simple method for the MC50 having higher alpha beam capability and also improving proton and deuteron beams currently used. We are considering two possibilities to improve the internal ion source and to install a new external axial injection system. The external injection system will be consisted of an Einzel lens, a steering magnet, a buncher, and a glazer lens placed in front of an inflector, which is located at the center of the main magnet.

• The Korean Journal of Nuclear Medicine
• /
• v.28 no.3
• /
• pp.364-370
• /
• 1994

The purpose of this study is to evaluate the clinical application of the no carrier added $[^{51}Cr]Cr(III)$-EDTA complexes, produced at Korea Cancer Center Hospital. The $[^{51}Cr]Cr(III)$-EDTA complexes, usefut for measurement of GFR were prepared at room temperature in the presence of bicarbonate catalysts. The radiochemical purity of $[^{51}Cr]Cr(III)$-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 injection of the $^{51}Cr$-EDTA, respectively. After the nonlinear regression, the area under curve was obtained. The plasma clearance of the $^{51}Cr$-EDTA was calculated with injected dose/AUC. The clearance rate calculated with the head and neck counting data was in good agreement with the 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 $time{\times}S$. The absorbed whole body radiation dose was negligibly small.

• Journal of Radiation Protection and Research
• /
• v.15 no.2
• /
• pp.113-122
• /
• 1990

After four years of planning, equipment acquisition, facility construction and beam testing, the KCCH cyclotron facility was put into operation in November1986. Now the KCCH cyclotron(MC-50) has been used for four years in neutron therapy and radioisotope production. Up to December 1989, 179(1852 sessions) patient have undergone neutron therapy. Radioisotope production for nuclear medicine use was started from March 1989 after extensive work to overcome target transport, target melting, beam diagnostic and chemical processing problems. This status report introduces the cyclotron facility, and the experiences of neutron therapy and isotope production with the MC-50 cyclotron. Besides, the operation results and the general troubles of the MC-50 during 1989 are summarized. Total operation time was 1252.5 hours. Four hundred hours were used for neutron therapy of 599 treatment sessions and 832.5 hours for radioisotope production. Total amount of produced raioisotope was 1695 mCi(Ga-67 : 1478mCi, Tl-201 : 107 mCi, I-123 : 25mCi, In-111 : 85mCi). Twenty hours were used for scheduled beam testing. In 1989, 882% of the planned operation were performed on schedule and this rats is improved remarkably compared to 71.0% in 1988.

• Journal of Radiopharmaceuticals and Molecular Probes
• /
• v.1 no.2
• /
• pp.88-94
• /
• 2015

The KOTRON-13 cyclotron was manufactured by Samyoung Unitech as the second generation of the KIRAMS-13 cyclotron after its technology was transferred from the Korea Institute of Radiological and Medical Sciences in South Korea. Its prototype was installed at Seoul National University Bundang Hospital as part of a distributed network of regional cyclotrons with the support of a grant from the National Research Foundation of Korea. However, its initial condition has limited capacity to extract a relatively low beam current and to produce carbon-11. In this review, we provide an introduction and overview of the current state of the KOTRON-13 cyclotron, which was successfully upgraded by carrying out various modifications and optimizing the carbon-11 target system.

• The Korean Journal of Nuclear Medicine Technology
• /
• v.13 no.3
• /
• pp.147-151
• /
• 2009

Purpose: 2-[$^{18}F$]Fluoro-2-deoxy-D-glucose ([$^{18}F$]FDG) particularly plays as a important role in Positron Emission Tomography (PET) imaging in nuclear medicine. Domestic [$^{18}F$]FDG auto synthesizers are installed in Seoul National University Bundang Hospital (SNUBH) at June 2008, these modules were known that it's synthetic yields were guaranteed in average $45{\pm}5%$ so far. To improve yields and convenience of domestic [$^{18}F$]FDG auto synthesizer, numerous trials in reaction time, base concentration, pressure and temperature were performed to increase [$^{18}F$]FDG yields. Materials and Methods: Several synthetic factors (temperature, time and pressure) and shortcoming were corrected based on many evaporation test. Syringe dispensing of tetra-butylammonium bicarbonate (TBAB) was replaced with micro pipette to prepare tetrabutyl ammonium fluoride salt ([$^{18}F$]TBAF). Troublesome refill of liquid nitrogen every 2 hours which was used to protect vacuum system was changed to charcoal cartridge, base guard filter. To monitor the volume of delivered $[^{18}O]OH_2$ from cyclotron by surveillance camera, we set up the volumetric vial on the cover of the module. In addition to, the recovery vial was added in [$^{18}F$]FDG production system to recover [$^{18}F$]FDG loss due to the leak of valve ($V_{13,14}$) in [$^{18}F$]FDG purification process. Results: When we used micro pipette for adding TBAB ($30\;{\mu}L$ in 12% $H_2O$ in acetonitrile), this quantitative dispensation has enabled to improve $5.5{\pm}1.7%$ residual fluorine-18 activity in fluorine separation cartridge compared to syringe adding. Besides, the synthetic yields of [$^{18}F$]FDG has increased $58{\pm}2.6%$ (n=19), $58{\pm}2.9%$ (n=14), $60%{\pm}2.5%$ (n=17) for 3 months. The life cycle of charcoal cartridge and base vacuum was 3 months prior to filling liquid nitrogen every 2 hours and additional side separator can prevent pump corrosion by organic solvent. After setting of volumetric indicator vial, the operator can easily monitor the total volume of irradiated $[^{18}O]OH_2$ from cyclotron. The recovery vial can be used for the stabilizer when an irregular [$^{18}F$]FDG loss was generated by the leak of valves ($V_{13,14}$). Conclusions: We has optimized appropriate synthetic conditions (temperature, time, pressure) in domestic [$^{18}F$]FDG auto synthesizer. In addition to, the remodeling with several accessories improve yields of domestic [$^{18}F$]FDG auto synthesizer with reliable reproducibility.