• Title/Summary/Keyword: 직접방사

Search Result 374, Processing Time 0.031 seconds

Synthesis of (4-$[^{18}F]$Fluorophenyl)triphenylphosphonium as a Mitochondrial Voltage Sensor for PET (PET영상용 미토콘드리아 막전위 감지기 (4-$[^{18}F]$Fluorophenyl)triphenylphosphonium의 합성)

  • Kim, Dong-Yeon;Yu, Kook-Hyun;Bom, Hee-Seung;Min, Jung-Joon
    • Nuclear Medicine and Molecular Imaging
    • /
    • v.41 no.6
    • /
    • pp.561-565
    • /
    • 2007
  • Purpose: Lipophilic cations including tetraphenylphosphonium (TPP) salts penetrate the hydrophobic barriers of the plasma and mitochondrial membranes, resulting in accumulation in mitochondria in response to the negative inner transmembrane potentials. The development of radiolabeled phosphonium cations as a noninvasive imaging agent may serve as a new molecular "voltage sensor" probe to investigate the role of mitochondria in the pathophysiology and diagnosis of cancer. Materials and Methods: We have synthesized a reference compound (4-fluorophenyl)triphenylphosphonium (TPP) and a labeled compound $[^{18}F]$TPP via two step nucleophilic substitution of no-carrier-added $[^{18}F]$fluoride with the precursor, 4-iodophenyltrimethylammonium iodide, in the presence of Kryptofix-2.2.2 and $K_2CO_3$. Result: The reference compound (4-fluorophenyl)triphenylphosphonium (TPP) was synthesized in 60% yield. The radiolabeled compound $[^{18}F]$TPP was synthesized in $10\sim15%$ yield. The radiochemical purity of the $[^{18}F]$TPP was $95.57{\pm}0.51%$ (n=11). Conclusion: $[^{18}F]$TPP was successfully synthesized that might have a potential to be utilized as a novel myocardial or cancer imaging agent for PET. However, it is required to improve the radiochemical yield to apply $[^{18}F]$TPP in preclinical or clinical researches.

화장실 양변기 배수 및 세정소음

  • 박명식;김태희
    • The Magazine of the Society of Air-Conditioning and Refrigerating Engineers of Korea
    • /
    • v.32 no.10
    • /
    • pp.17-21
    • /
    • 2003
  • 국내 화장실 양변기의 배수 및 세정소음에 관한 실험실 측정결과를 소개하고자 한다. 1989년 대한주택공사에서 조사한 설문조사에 의하면 공동주택에서 외부로부터 들리는 소음에 대한 불만을 조사한 결과, 바닥충격음, 급배수설비 소음, 그리고, 공기전달음의 순으로 나타났다. 이와 같이 급배수시 발생소음은 공동주택 입주자의 주요한 민원중의 하나이다. 급배수설비 소음은 유체의 유동에 의하여 발생하며, 직접 공기중을 전파하여 가는 “공기전달음”과 배관지지 재료 및 구조체 등을 통해 재차 공기중을 전파하여가는 “고체전달음” 으로 구분된다. 여기서 “공기전달음”이란 실내에서 발생한 소리가 구조체를 진동하고 구조체는 인접실의 구조체 주변의 공기를 진동하여 소리가 방사되거나 또는 인접실간에 열려 있는 통로를 거쳐 전달되는 소음을 말하고 “고체전달음”이란 음원이 접하고 있는 건물구조체를 통하여 진동의 형태로 전달되는 소음을 일컫는다. 공동주택에서 배수관은 아래층 천장배관에 해당되므로 배수관에서 발생하는 소음은 아래층으로 직접 전달된다. 이러한 배수설비 소음은 배관재의 종류, 배관스페이스의 구조 및 위치 등에 따라 소음레벨이 달라지게 된다.(중략)

  • PDF

새로운 재생셀룰로오스 섬유$(enVix{\circledR})$의 직접 염료에 대한 염색성

  • 심우섭;고준석;김성수;김재필;김익수
    • Proceedings of the Korean Society of Dyers and Finishers Conference
    • /
    • 2003.04a
    • /
    • pp.78-82
    • /
    • 2003
  • 셀룰로오스계 재생섬유 중 가장 먼저 개발된 Viscose rayon은 셀룰로오스 펄프를 17-18%의 가성소다 수용액에 팽윤시켜 알칼리 셀룰로스를 만든 뒤 이황화탄소(CS$_2$)에 반응시킨 후 방사하여 제조하며 흡습성, 제전성, 드레이프성 및 광택이 우수한 쾌적성 섬유이다. 그러나 탄성 회복율이 좋지 않으며 강력이 적고 특히 습윤시의 강력 저하의 단점이 있을 뿐만 아니라 제조과정에서 사용하는 이황화탄소의 환경 유해성이 큰 문제점으로 지적되고 있어 선진국들이 점차 설비를 폐쇄하거나 개도국으로 이전하고 있는 실정이다. (중략)

  • PDF

Uncertainty Analysis of Food-chain Pollution for a Radioactive Material from Atmosphere (대기로부터 방사능물질의 토양침적시 농작물오염에 대한 불확실성분석)

  • 유동한;이한수
    • Proceedings of the Korea Air Pollution Research Association Conference
    • /
    • 2003.11a
    • /
    • pp.191-192
    • /
    • 2003
  • 원자력시설의 사고시 대기중으로 누출된 방사성물질에 의해 오염된 토양으로부터 재배된 농작물로 인한 인체노출은 각종 환경오염물질에 의한 인체영향 연구결과에 보듯이 직접적인 방사능에 의한 인체노출 못지 않게 상당히 중요하다. 이러한 섭식경로를 통한 노출은 각 나라마다 서로 다른 토양조건 및 작물체종류의 다양성등 다른 양상을 보이고 있어, 연구가 수행된 미국이나 유럽등지의 평가방법을 그대로 사용하면 국내의 토양에서 재배되는 농작물이나 이를 이용한 축산물에 따른 한국인의 독특한 섭취양상을 충분히 고려하여 평가하기 어려울 수 있다. (중략)

  • PDF

Relationship between Compressive Strength and Dynamic Modulus of Elasticity in the Cement Based Solid Product for Consolidating Disposal of Medium-Low Level Radioactive Waste (중·저준위 방사성 폐기물 처리용 시멘트 고화체의 압축강도와 동탄성계수의 관계)

  • Kim, Jin-Man;Jeong, Ji-Yong;Choi, Ji-Ho;Shin, Sang-Chul
    • Journal of the Korea Concrete Institute
    • /
    • v.25 no.3
    • /
    • pp.321-329
    • /
    • 2013
  • Recently, the medium-low level radioactive waste from nuclear power plant must be transported from temporary storage to the final repository. Medium-low level radioactive waste, which is composed mainly of the liquid ion exchange resin, has been consolidated with cementitious material in the plastic or iron container. Since cementitious material is brittle, it would generate cracks by impact load during transportation, signifying leakage of radioactive ray. In order to design the safety transporting equipment, there is a need to check the compressive strength of the current waste. However, because it is impossible to measure strength by direct method due to leakage of radioactive ray, we will estimate the strength indirectly by the dynamic modulus of elasticity. Therefore, it must be identified the relationship between of strength and dynamic modulus of elasticity. According to the waste acceptance criteria, the compressive strength of cement based solid is defined as more than 3.44 MPa (500 psi). Compressive strength of the present solid is likely to be significantly higher than this baseline because of continuous hydration of cement during long period. On this background, we have tried to produce the specimens of the 28 day's compressive strength of 3 to 30 MPa having the same material composition as the solid product for the medium-low level radioactive waste, and analyze the relationship between the strength and the dynamic modulus of elasticity. By controling the addition rates of AE agent, we made the mixture containing the ion exchange resin and showing the target compressive strength (3~30 MPa). The dynamic modulus of elasticity of this mixtures is 4.1~10.2 GPa, about 20 GPa lower in the equivalent compressive strength level than that of ordinary concrete, and increasing the discrepancy according to increase strength. The compressive strength and the dynamic modulus of elasticity show the liner relationship.

Review of the Gross Alpha for Characterization of Radioactive Waste (방사성폐기물 특성평가를 위한 전알파 분석법 고찰)

  • Kim, Hyuncheol;Lim, Jong-Myoung;Jang, Mee;Park, Ji-Young
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.18 no.2_spc
    • /
    • pp.227-235
    • /
    • 2020
  • In this study, we discussed the limitations of gross alpha measurements for the characterization of radioactive wastes produced in nuclear facilities through experimental tests and Monte Carlo N-particle transport simulations. The determination of gross alpha is essential for the disposal of radioactive waste produced in nuclear facilities in Korea. The measurements of gross alpha are easy to perform and yield rapid analytical results, but it cannot be used for quantitative analysis. The error of counting efficiency for gross alpha with various masses of the deposit on planchets using KCl and 241Am was determined. The relative deviation of the counting efficiency in samples having the same mass was 20%. Uranium was extracted from the soil through acid leaching and extraction chromatography, and the concentration of U determined by inductively coupled plasma-mass spectrometry (ICP-MS) was compared with the results for gross alpha. The gross alpha was underestimated by 50% compared to the U concentration by ICP-MS. The counting efficiency depended on the energy from the alpha emitters, which differed by up to three times in determination of the counting efficiency depending on the kinds of alpha radionuclides of interest. Therefore, the gross alpha is not compatible with the sum of radioactivity for each alpha emitter and is suitable as a screening method.

A Study on the Treatment of Radioactive Liquid Wastes using Synthetic textile by Air Intake System (공기유입시스템에서의 섬유매체에 의한 방사성액체폐기물 처리에 관한 연구)

  • 김태국;이영희;안섬진;손종식;홍권표
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2003.11a
    • /
    • pp.101-104
    • /
    • 2003
  • In this study based on the mass transfer theory, experiments for the evaporation rates depending on various conditions were carried out through the operation of the existing Natural Evaporation Facility in KAERI. Evaporation media were made of the cotton and polyester. Air circulation in the facility was forced by exhausting fans. The evaporation rate and the decontamination factor were calculated by the result of experiment. The evaporation rate increased as the flow rate of air supply, the feed rate of liquid waste, and the temperature of supplied air increased. As for the humidity of supplied air, the evaporation rate was getting higher as the humidity was getting lower. As the result of this study, operation conditions of the Natural Evaporation Facility are optimized as follows : The air temperature above $8^{\circ}C$, the air humidity below 70%, the air flow rate 1.14-1.47 m/sec, and the liquid waste feed rate $4.6{\ell}/hr\cdotm^2$. The decontamination factor and the radioactivity are $5.1{\times}10^3$and $4.7{\times}10^{-13}{\mu}Ci/\textrm{m}{\ell}$ respectively, at the above mentioned optimum operation conditions. The air factor in the Dalton's equation for evaporation was determined from results of experiment on the temperature, the humidity, and the flow rate of supplied air as following : $[\textit{Eh}=(0.018 + 0.0141\textitv) {\delta}textitH]$

  • PDF

A Comparative Study on the Economics of Reprocessing and Direct Disposal of Nuclear Spent Fuel (사용후 핵연료의 제처리와 직접 처분의 경제성 비교 연구)

  • Kang, Seong-Ku;Song, Jong-Soon
    • Journal of Radiation Protection and Research
    • /
    • v.25 no.2
    • /
    • pp.89-96
    • /
    • 2000
  • Nuclear fuel cycle choices and costs are important in considering energy policies, fuel diversity, security of supply and associated social and environmental impacts. Particularly, the nuclear spent fuel is very important in view of high activity and the need of long term management. This study focuses on the comparison of reprocessing and direct disposal of nuclear spent fuel in terms of cost, safety and public acceptability. The results of the study show that the direct disposal is about 7% more economical than the reprocessing. In terms of safety, the results show that the risk of vitrified HLW (high-level radioactive waste) is less than directly disposed spent fuel. For the public acceptability, both of the methods are not well understood and therefore they are not accepted. In conclusion, it is necessary to guarantee the safety of the both spent fuel processing methods through continuous development of associated technology and to have a fuel cycle policy which should consider not only the economics but also social and environmental impacts.

  • PDF

Dose Rate of Restroom in Facilities using Radioisotope (방사성동위원소 사용시설(내/외) 화장실의 외부선량률)

  • Cho, Yong-Gwi;An, Seong-Min
    • Journal of radiological science and technology
    • /
    • v.39 no.2
    • /
    • pp.237-246
    • /
    • 2016
  • This study is therefore aimed at measuring the surface dose rate and the spatial dose rate in and outside the radionuclide facility in order to ensure safety of the patients, radiation workers and family care-givers in their use of such equipment and to provide a basic framework for further research on radiation protection. The study was conducted at 4 restrooms in and outside the radionuclide facility of a general hospital in Incheon between May 1 and July 31, 2014. During the study period, the spatial contamination dose rate and the surface contamination dose rate before and after radiation use were measured at the 4 places-thyroid therapy room, PET center, gamma camera room, and outpatient department. According to the restroom use survey by hospitals, restrooms in the radionuclide facility were used not only by patients but also by family care-givers and some of radiation workers. The highest cumulative spatial radiation dose rate was 8.86 mSv/hr at camera room restroom, followed by 7.31 mSv/hr at radioactive iodine therapy room restroom, 2.29 mSv/hr at PET center restroom, and 0.26 mSv/hr at outpatient department restroom, respectively. The surface radiation dose rate measured before and after radiation use was the highest at toilets, which are in direct contact with patient's excretion, followed by the center and the entrance of restrooms. Unsealed radioactive sources used in nuclear medicine are relatively safe due to short half lives and low energy. A patient who received those radioactive sources, however, may become a mobile radioactive source and contaminate areas the patient contacts-camera room, sedation room, and restroom-through secretion and excretion. Therefore, patients administered radionuclides should be advised to drink sufficient amounts of water to efficiently minimize radiation exposure to others by reducing the biological half-life, and members of the public-family care-givers, pregnant women, and children-be as far away from the patients until the dose remains below the permitted dose limit.

A Study on Image Reconstruction for Seed Localization for Permanent Prostate Brachytherapy (전립선암 근접치료 시 방사성선원 위치확인을 위한 영상 재구성에 관한 연구)

  • Hong, Ju-Young;Rah, Jeong-Eun;Suh, Tae-Suk
    • Radiation Oncology Journal
    • /
    • v.25 no.2
    • /
    • pp.125-133
    • /
    • 2007
  • [ $\underline{Purpose}$ ]: This study was to design and fabricate a phantom for prostate cancer brachytherapy to validate a developed program applying a 3-film technique, and to compare it with the conventional 2-film technique for determining the location of an implanted seed. $\underline{Materials\;and\;Methods}$: The images were obtained from overlapped seeds by randomly placing a maximum of 63 seeds in the anterior-posterior (AP) position and at $-30^{\circ} to $30^{\circ} at $15^{\circ} intervals. Images obtained by use of the phantom were applied to the image processing procedure, and were then processed into the development program for seed localization. In this study, cases were set where one seed overlapped, where two seeds overlapped and where none of the three views resolved all seeds. The distance between the centers of each seed to the reference seed was calculated in a prescribed region. This distance determined the location of each seed in a given band. The location of the overlapped seeds was compared with that of the 2-film technique. $\underline{Results}$: With this program, the detection rate was 92.2% (at ${\pm}15^{\circ}), 94.1% (at ${\pm}30^{\circ}) and 70.6% (compared to the use of the 2-film technique). The overlaps were caused by one or more than two seeds that overlapped; the developed program can identify the location of each seed perfectly. However, for the third case the program was not able to resolve the overlap of the seeds. $\underline{Conclusion}$: This program can be used to improve treatment outcome for the brachytherapy of prostate cancer by reducing the number of errors in the process of reconstructing the locations of perfectly overlapped seeds.