• Title/Summary/Keyword: 비방사능

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Facile [11C]PIB Synthesis Using an On-cartridge Methylation and Purification Showed Higher Specific Activity than Conventional Method Using Loop and High Performance Liquid Chromatography Purification (Loop와 HPLC Purification 방법보다 더 높은 비방사능을 보여주는 카트리지 Methylation과 Purification을 이용한 손쉬운 [ 11C]PIB 합성)

  • Lee, Yong-Seok;Cho, Yong-Hyun;Lee, Hong-Jae;Lee, Yun-Sang;Jeong, Jae Min
    • The Korean Journal of Nuclear Medicine Technology
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    • v.22 no.2
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    • pp.67-73
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    • 2018
  • $[^{11}C]PIB$ synthesis has been performed by a loop-methylation and HPLC purification in our lab. However, this method is time-consuming and requires complicated systems. Thus, we developed an on-cartridge method which simplified the synthetic procedure and reduced time greatly by removing HPLC purification step. We compared 6 different cartridges and evaluated the $[^{11}C]PIB$ production yields and specific activities. $[^{11}C]MeOTf$ was synthesized by using TRACERlab FXC Pro and was transferred into the cartridge by blowing with helium gas for 3 min. To remove byproducts and impurities, cartridges were washed out by 20 mL of 30% EtOH in 0.5 M $NaH_2PO_4$ solution (pH 5.1) and 10 mL of distilled water. And then, $[^{11}C]PIB$ was eluted by 5 mL of 30% EtOH in 0.5 M $NaH_2PO_4$ into the collecting vial containing 10 mL saline. Among the 6 cartridges, only tC18 environmental cartridge could remove impurities and byproducts from $[^{11}C]PIB$ completely and showed higher specific activity than traditional HPLC purification method. This method took only 8 ~ 9 min from methylation to formulation. For the tC18 environmental cartridge and conventional HPLC loop methods, the radiochemical yields were $12.3{\pm}2.2%$ and $13.9{\pm}4.4%$, respectively, and the molar activities were $420.6{\pm}20.4GBq/{\mu}mol$ (n=3) and $78.7{\pm}39.7GBq/{\mu}mol$ (n=41), respectively. We successfully developed a facile on-cartridge methylation method for $[^{11}C]PIB$ synthesis which enabled the procedure more simple and rapid, and showed higher molar radio-activity than HPLC purification method.

Evaluation of Proper Image Acquisition Time by Change of Infusion dose in PET/CT (PET/CT 검사에서 주입선량의 변화에 따른 적정한 영상획득시간의 평가)

  • Kim, Chang Hyeon;Lee, Hyun Kuk;Song, Chi Ok;Lee, Gi Heun
    • The Korean Journal of Nuclear Medicine Technology
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    • v.18 no.2
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    • pp.22-27
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    • 2014
  • Purpose There is the recent PET/CT scan in tendency that use low dose to reduce patient's exposure along with development of equipments. We diminished $^{18}F$-FDG dose of patient to reduce patient's exposure after setting up GE Discovery 690 PET/CT scanner (GE Healthcare, Milwaukee, USA) establishment at this hospital in 2011. Accordingly, We evaluate acquisition time per proper bed by change of infusion dose to maintain quality of image of PET/CT scanner. Materials and Methods We inserted Air, Teflon, hot cylinder in NEMA NU2-1994 phantom and maintained radioactivity concentration based on the ratio 4:1 of hot cylinder and back ground activity and increased hot cylinder's concentration to 3, 4.3, 5.5, 6.7 MBq/kg, after acquisition image as increase acquisition time per bed to 30 seconds, 1 minute, 1 minute 30 seconds, 2 minute, 2 minutes 30 seconds, 3 minutes, 3 minutes 30 seconds, 4 minutes, 4 minutes 30 seconds, 5 minutes, 5 minutes 30 seconds, 10 minutes, 20 minutes, and 30 minutes, ROI was set up on hot cylinder and back radioactivity region. We computated standard deviation of Signal to Noise Ratio (SNR) and BKG (Background), compared with hot cylinder's concentration and change by acquisition time per bed, after measured Standard Uptake Value maximum ($SUV_{max}$). Also, we compared each standard deviation of $SUV_{max}$, SNR, BKG following in change of inspection waiting time (15minutes and 1 hour) by using 4.3 MBq phantom. Results The radioactive concentration per unit mass was increased to 3, 4.3, 5.5, 6.7 MBqs. And when we increased time/bed of each concentration from 1 minute 30 seconds to 30 minutes, we found that the $SUV_{max}$ of hot cylinder acquisition time per bed changed seriously according to each radioactive concentration in up to 18.3 to at least 7.3 from 30 seconds to 2 minutes. On the other side, that displayed changelessly at least 5.6 in up to 8 from 2 minutes 30 seconds to 30 minutes. SNR by radioactive change per unit mass was fixed to up to 0.49 in at least 0.41 in 3 MBqs and accroding as acquisition time per bed increased, rose to up to 0.59, 0.54 in each at least 0.23, 0.39 in 4.3 MBqs and in 5.5 MBqs. It was high to up to 0.59 from 30 seconds in radioactivity concentration 6.7 MBqs, but kept fixed from 0.43 to 0.53. Standard deviation of BKG (Background) was low from 0.38 to 0.06 in 3 MBqs and from 2 minutes 30 seconds after, low from 0.38 to 0 in 4.3 MBqs and 5.5 MBqs from 1 minute 30 seconds after, low from 0.33 to 0.05 in 6.7 MBqs at all section from 30 seconds to 30 minutes. In result that was changed the inspection waiting time to 15 minutes and 1 hour by 4.3 MBq phantoms, $SUV_{max}$ represented each other fixed values from 2 minutes 30 seconds of acquisition time per bed and SNR shown similar values from 1 minute 30 seconds. Conclusion As shown in the above, when we increased radioactive concentration per unit mass by 3, 4.3, 5.5, 6.7 MBqs, the values of $SUV_{max}$ and SNR was kept changelessly each other more than 2 minutes 30 seconds of acquisition time per bed. In the same way, in the change of inspection waiting time (15 minutes and 1 hour), we could find that the values of $SUV_{max}$ and SNR was kept changelessly each other more than 2 minutes 30 seconds of acquisition time per bed. In the result of this NEMA NU2-1994 phantom experiment, we found that the minimum acquisition time per bed was 2 minutes 30 seconds for evaluating values of fixed $SUV_{max}$ and SNR even in change of inserting radioactive concentration. However, this acquisition time can be different according to features and qualities of equipment.

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A Theoretical Analysis of the Acceptability of Design Stress Value for the Fuel Rod with Nonlinear Thermal Stresses (비선형 분포의 열응력이 작용하는 Fuel Rod에서 설계 응력값의 적합성여부에 대한 이론적 해석)

  • 호광일
    • Journal of Energy Engineering
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    • v.12 no.3
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    • pp.177-183
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    • 2003
  • The purpose of this paper is to verify that the design stress value of fuel rod for the irradiation test satisfies the structural design requirement. In this structural safety analysis thermal effect is the most severe element for the safety. The thermal effects are very complicated problem to be analyzed for the structural safety in short hand. By the application of theoretical analysis, the design margin of stress which was used in this fuel rod design was verified in the conservative point of view. In the future design of fuel rod, this analysis can be used as the theoretical method for the verification of safe design.

Microwave Radiometry for functional Diagnosis of Biological tissue (생체 기능적 진단을 위한 Microwave Radiometry의 응용)

  • Lee, J.W.;Kim, K.S.;Lee, S.M.;Yoon, G.
    • Proceedings of the KIEE Conference
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    • 2000.11d
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    • pp.845-847
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    • 2000
  • 깊은 생체 조직에서 전자기 에너지의 일부가 피부로 전달되는데, 이때 생체 내부에서 피부로 전달되는 전자기 에너지의 세기는, 주파수 대역과 전자기파를 흡수, 반사, 투과시키는 인체의 매질에 따라 다르다. Microwave Radiometry는 인체 내부 조직에서 방출되는 1-6 GHz 대역의 전자기 에너지 일부를 피부 표면에서 측정하여 일정한 체적내의 인체 내부 온도 평균온도를 추정하는 방법이다. 이러한 Radiometry로 암이나 종양 등의 이상 조직을 진단하는 의학적 가설은, 암이 진행시 악성 종양의 세포의 신진대사가 정상 세포보다 활발하게 되고 또한 종양 세포 주위로 혈액의 유입이 증가하게되어, 주위의 정상 세포 보다 열을 보다 더 방출하는 데 있다. 이때 발생된 열은 일정한 주파수 대역의 마이크로파 에너지를 방출하게 되고, 이에 Radiometry로 인체에 무해하고(passive), 비침습적(non-invasive), 방사능의 영향이 없는 (non-ionizing) 방법으로 인체 내부에서 전달되는 전자기 에너지 강도를 측정하여 종양 부위와 주위 정상부위의 온도 차이를 추정 의학진단에 응용할 수 있다. 본 논문에서는 이러한 Microwave Radiometry의 의학적 응용과 생리학적 특성을 고려한 인체모델용 팬텀에 대하여 살펴본다.

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The Eye/Brain Radioactivity Ratio for Assessment of Graves' Ophthalmopathy (Graves병 안구증에서 $^{99m}Tc-DTPA$ 뇌신티그라피를 이용한 안구/뇌 방사능비에 관한 연구)

  • Lee, B.W.;Sung, S.K.;Park, W.;Suh, K.S.;Choi, D.J.;Kim, J.S.
    • The Korean Journal of Nuclear Medicine
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    • v.22 no.1
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    • pp.27-31
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    • 1988
  • In Graves' disease, changes in orbital tissue and structure are casued by inflammatory infiltation, which induces increase of capillary permeability and breakdown of blood-tissue barriers. Using the uptake of $^{99m}Tc-DTPA$ in inflammatory lesion, Eye/Brain radioactivity ratios in brain scintigraphy were evaluated in 15 normal controls and 40 Graves' patients. The results were as follows; 1) Eye/Brain radioactivity ratio was significantly higher in Graves' ophthalmopthy group than in control group (p < 0.005). 2) In Graves' ophthalmopathy, Eye/Brain radioactivity ratio was significantly higher in active (progressive) group than in inactive (non-progressive) group (p < 0.05). 3) There was no correlation between class of ATA classification of Graves' ophthalmopathy and Eye/Brain radioactivity ratio. 4) There was no correlation between Eye/Brain radioactivity ratio and serum activity of TBII. In conclusion, Eye/Brain radioactivity ratio using $^{99m}Tc-DTPA$ brain scintigraphy may be useful to determine the activity of Graves' ophthalmopathy and whether treatment of Graves' ophthalmopathy is necessary or not.

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하드웨어 메모리 스크러버 설계

  • Kim, Dae-Young;Cho, Chang-Burm;Kang, Seok-Ju;Chae, Tae-Byung
    • Aerospace Engineering and Technology
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    • v.2 no.1
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    • pp.73-79
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    • 2003
  • Usual satellite design adopts hardware Error Detection and Correction (EDAC) circuitary for memory elements to endure proper operation in space radiation environment and periodic read-back(scrubbing) scheme to remove errors occurred and to prevent further accumulation of errors, in parallel, But lack of detail radiation test data upset rates of KOMPSAT-2 mass storage was estimated very worse compared to that of KOMPSAT-1, which was evaluated from very precise radiation test. Although upset rates were evaluated enough low to accommodate by KOMPSAT-2 Flight Software, hardware scrubbing scheme is studied to shorten scrubbing time as well. This paper describes hardware scrubbing architecture having minimum 1.88 minutes scrubbing interval over 1 Gbits memory.

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The Determination of $^{14}C$ in Stack Effluent Gases by Carbonate Suspension Counting Method (탄산염 부유측정법을 이용한 연도 가스중의 방사성 탄소 측정)

  • Chun, Sang-Ki;Woo, Hyung-Joo;Cho, Soo-Young;Kim, Nak-Bae;Lee, Jong-Dae
    • Analytical Science and Technology
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    • v.12 no.4
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    • pp.279-283
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    • 1999
  • The purpose of this study was to optimize carbonate suspension counting method for the measurements of high level activity of $^{14}C$ in a reactor stack effluent gases. Although it is less sensitive method, the carbonate suspension counting method has been found to be a suitable technique for the $^{14}C$ monitoring of samples with small amount but with high specific activity and to be relatively simple and fast.

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Characteristic of PVA-PMAA on the Fixation of Radioactively Contaminated Sand as a Result of a Nuclear Accident (PVA-PMAA에 의한 헥사고 오염모래의 고정화 특성)

  • Won, He-Jun;Ahn, Byung-Kil;Oh, Won-Jun
    • Nuclear Engineering and Technology
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    • v.27 no.1
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    • pp.18-24
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    • 1995
  • Characteristics of poly(vinyl alcohol)-poly(methacrylic acid) system (PVA.-PMAA system) for fixation of radioactive contaminant on sand were studied. Dissociation of carboxyl group in PMAA was found to be suppressed by PVA Permeability of sand layer treated with PVA-PMAA solution is directly proportional to the PMAA concentration when the [PMAA] is below 0.082 M and the empirical proportional constant (k) is -8.95$\times$10 ̄$^4$cm$^{5}$ /mole. The change of permeability can be explained by the formation of an intermacromolecular complex between PVA and PMAA The polymer bridge formed on a sand surface combines sand yams more firmly. The PVA-PMAA system is more effective than the PVA system for the fixation of deposited condensational radionuclides.

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Optical Bleaching Behaviour of Neutron Irradiated KCI Single Crystal

  • Suh, In-Suck
    • Nuclear Engineering and Technology
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    • v.5 no.4
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    • pp.286-290
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    • 1973
  • Hydroxide free KCI single crystals are prepared and doped with samall amounts of KSH or $K_2$S. The samples are subjected to neutron irradiations while keeping them under the condition of liquid nitrogen temperature in the dark. The irradiated ones are then bleached by using a U.V. lamp and analysed as four different kinds of chemical forms in $^{35}$ S whose valence states are -2, 0, +4 and +6. It semms that the sulphide fraction of $^{35}$ S in doped crystals is higher than that in pure crystals. In addition, two distinct patterns in bleaching process up to 30 minutes results in a fast increase in the sulphide fraction and then the sulphide levels off to a slowly increasing region upon prolonged bleaching. A detailed description on the distribution of $^{35}$ S valence states will be made in connection with point defects in the crystals.

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How to Remove Radioactive Ions in Radioactive Waste (방사성 폐수 내 방사성 이온 제거방법)

  • Shin, Do Hyoung;Rhim, Ji Won;Park, Sung Kyun;Seo, Chang Hee;Park, Hun Hwee
    • Membrane Journal
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    • v.25 no.6
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    • pp.478-487
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    • 2015
  • This review article indicated accident examples in the past and discussed dangerousness according to these examples. In addition, the ways to remove radioactive ions in radioactive waste, they were divided broadly and enumerated experimental case. These were many results of the experiment and patents used various ways complexly, but domestic technology prowess lower than foreign technology prowess. Even in case of accidents that could happen afterwards, it is essential for growth and competitiveness of domestic technology. Through this article, it considered today's technology for removing radioactive ions and was trying to find out about the possibility of development.