• Title/Summary/Keyword: Medical radioactive isotope

검색결과 34건 처리시간 0.025초

방사선 피폭역을 달리하여 분리한 세균의 방사선감수성 비교 (Comparison of Radiosensitivity of Bacteria Isolated from Given Radiation Exposure History)

  • 김기수;민봉희;이강순
    • 미생물학회지
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    • 제12권2호
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    • pp.69-69
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    • 1974
  • This experiment was carried out to identify and to compare the radiosensitivities of bacteriz isolated from the sources of different radiation exposure histories. Among 10 strains isolated in this investigation, 4 strains of bacteria, Bacillus firmus, Bacillus brevis, Baciilus subtilis and Bacillus sphaericus were isolated from high and low radioactive sites simulaneously. Bacterial strains isolated from radioactive sources such as reactor and isotope production rooms were more resistant to irradiation than the microganisms from medical products and laboratories, however, there was no significance in radiosensitivity in the same species of bacteriz, even if they were isolated from different radiation exposure histories.

의료용 방사성폐기물 자체처분을 위한 방사능 측정 및 평가 (Measurement and Estimation for the Clearance of Radioactive Waste Contaminated with Radioisotopes for Medical Application)

  • 김창범;박민석;김기섭;정해조;장성주
    • 한국의학물리학회지:의학물리
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    • 제25권1호
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    • pp.8-14
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    • 2014
  • 의료분야에서 방사선 진료기술의 발전에 따라 방사성폐기물의 수량은 급속히 증가하고 있다. 방사성폐기물에는 주로 PET/CT에 사용하는 $^{18}F$을 비롯하여 핵의학검사에 사용하는 $^{99m}Tc$ 등과 같이 반감기가 매우 짧은 방사성동위원소가 함유되어 있다. 이를 처분하기 위하여 국제원자력기구(IAEA)는 개인선량($10{\mu}Sv/y$) 및 집단선량(1 man-Sv/y)과 핵종별 농도에 근거하여 각각 폐기물의 규제해제기준을 제시(IAEA Safety Series No 111-P-1.1, 1992 및 IAEA RS-G-1.7, 2004)하였다. 이 연구에서는 IAEA 기준에 따른 방사능농도를 측정하기 위하여, $^{18}F$, $^{99m}Tc$, $^{123}I$, $^{125}I$$^{201}TI$ 관련 방사성폐기물을 수집하고 측정용기를 준비하였다. 그리고 MCA를 이용한 감마방사능 측정, 감마계수기를 이용한 감마방사능 측정, 베타입자 방출 핵종의 방사능 측정방법 및 절차를 수립하고, 표준물질을 제작하여 교정하였다. 측정결과를 근거로 방사능 감쇠 유도식을 산출하였으며, 이를 이론식과 대비하여 고찰하였다. 이 연구 결과는 ISO 표준으로 추진할 예정이다.

코코넛 기반 활성탄 필터의 라돈 제거 효율 (Radon Removal Efficiency of Activated Carbon Filter from Coconut)

  • 안윤진;김기섭;김태환;김상록
    • 대한방사선기술학회지:방사선기술과학
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    • 제46권2호
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    • pp.141-149
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    • 2023
  • The Korea Institute of Radiological and Medical Sciences plans to produce 225Ac, a therapeutic radio-pharmaceutical for precision oncology, such as prostate cancer. Radon, a radioactive gas, is generated by radium, the target material for producing 225Ac. The radon concentration is expected to be about 2000 Bq·m-3. High-concentration radon-generating facilities must meet radioactive isotope emission standards by lowering the radon concentration. However, most existing studies concerning radon removal using activated carbon filters measured radon levels at concentrations lower than 1000 Bq·m-3. This study measured 222Rn removal of coconut-based activated carbon filter under a high radon concentration of about 2000 Bq·m-3. The 222Rn removal efficiency of activated carbon impregnated with triethylenediamine was also measured. As a result, the 222Rn removal amount of the activated carbon filter showed sufficient removal efficiency in a 222Rn concentration environment of about 2000 Bq·m-3. In addition, despite an expectation of low radon reduction efficiency of Triethylenediamine-impregnated activated carbon, it was difficult to confirm a significant difference in the results. Therefore, it is considered that activated carbon can be used as a radioisotope exhaust filter regardless of whether or not Triethylenediamine is impregnated. The results of this study are expected to be used as primary data when building an air purification system for radiation safety management in facilities with radon concentrations of about 2000 Bq·m-3.

몬테카를로 시뮬레이션을 통한 중하전입자의 콘크리트 방사화 비교평가 (Comparative Evaluation of Radioactive Isotope in Concrete by Heavy Ion Particle using Monte Carlo Simulation)

  • 배상일;조용인;김정훈
    • 대한방사선기술학회지:방사선기술과학
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    • 제44권4호
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    • pp.359-365
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    • 2021
  • A heavy particle accelerator is a device that accelerates particles using high energy and is used in various fields such as medical and industrial fields as well as research. However, secondary neutrons and particle fragments are generated by the high-energy particle beam, and among them, the neutrons do not have an electric charge and directly interact with the nucleus to cause radiation of the material. Quantitative evaluation of the radioactive material produced in this way is necessary, but there are many difficulties in actual measurement during or after operation. Therefore, this study compared and evaluated the generated radioactive material in the concrete shield for protons and carbon ions of specific energy by using the simulation code FLUKA. For the evaluation of each energy of proton beam and carbon ion, the reliability of the source term was secured within 2% of the relative error with the data of the NASA Space Radiation Laboratory(NSRL), which is an internationally standardized data. In the evaluation, carbon ions exhibited higher neutron flux than protons. Afterwards, in the evaluation of radioactive materials under actual operating conditions for disposal, a large amount of short-lived beta-decay nuclides occurred immediately after the operation was terminated, and in the case of protons with a high beam speed, more radioactive products were generated than carbon ions. At this time, radionuclides of 44Sc, 3H and 22Na were observed at a high rate. In addition, as the cooling time elapsed, the ratio of long-lived nuclides increased. For nonparticulate radionuclides, 3H, 22Na, and for particulate radionuclides, 44Ti, 55Fe, 60Co, 152Eu, and 154Eu nuclides showed a high ratio. In this study, it is judged that it is possible to use the particle accelerator as basic data for facility maintenance, repair and dismantling through the prediction of radioactive materials in concrete according to the cooling time after operation and termination of operation.

봉와직염(蜂窩織炎)의 한방(韓方) 임상치험(臨床治驗) 1례(例) (A Case Report on Cellulitis Treated with Therapeutic Intervention of Oriental Medicine)

  • 조성은;우영민;김용호;이진헌
    • 대한한방내과학회지
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    • 제22권3호
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    • pp.483-488
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    • 2001
  • A patient diagnosed as cellulitis by bone scan was taken the therapeutic intervention of Oriental medicine for 35 days. Cellulitis is characterized by acute purulence inflammation deeply diffused throughout epidermal connective tissue to subcutaneous adipose tissue. This patient presented a finding of soft tissue radioactive isotope uptake increase on bone scan of both foot and ankle. Cellulitis belongs to the category of ong(癰) in Oriental medicine. During therapeutic intervention, 3 herbal prescriptions were applied. Yeonkyopedok-san was applied for high fever and severe chilling on acute stage. After the application of Yeonkyopedok-san and Sunbangwhalmyong-eum, clinical symptoms improved with changes of CRP($112{\rightarro}12),\;WBC(13{\rightarro}8.8),\;ESR(65{\rightarro}46$). After the application of Chungpesagan-tang, clinical symptoms improved with changes of $CRP(12{\rightarro}3),\;WBC(8.8{\rightarro}5),\;ESR(46{\rightarro}13$).

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정중선 이소성 갑상선에서 주사상의 변화 추적 - 증례보고 - (A Changing Pattern of Isotope Scan of the Midline Ectopic Thyroid - A Case Report -)

  • 김갑태;김완섭;정을삼
    • Advances in pediatric surgery
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    • 제2권2호
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    • pp.133-137
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    • 1996
  • A 17 month-old girl presented in the pediatric clinic on November 27th, 1990 with a neck mass. The mass was 2 cm in diameter, firm in consistency and movable on the upper pole of the thyroid cartilage in the midline. The technetium thyroid scan showed a hot reactivity at the compatible site of the mass, but no other radioactivity in either site of the normal thyroid positions. At her second visit on January 23th, 1996, the mass had enlarged up to 3.5cm in diameter in the same location of the neck. The follow up thyroid scan revealed a walnut sized, snowman-like radioactivity. One of the snowman-like double images seemed to be a lingual ectopic thyroid and the other a midline ectopic thyroid remnant in the infrahyoid level. This interpretation was supported by the computed tomography of the neck, which showed a ligual mass in the foramen cecum area and an another mass in the anterior comis-sure of the larynx in the mildline. Thyroid function test was normal except a slightly increased TSH. As a result of this changing pattern of thyroid radioactive images, a case of a lingual thyroid as well as another midline ectopic thyroid tissue at the infrahyoid level is reported.

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Analysis of Air Discharge and Disused Air Filters in Radioisotope Production Facility

  • Kim, Sung Ho;Lee, Bu Hyung;Kwon, Soo Il;Kim, Jae Seok;Kim, Gi-sub;Park, Min Seok;Jung, Haijo
    • 한국의학물리학회지:의학물리
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    • 제27권3호
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    • pp.156-161
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    • 2016
  • When air discharged from a radioisotope production facility is contaminated with radiation, the public may be exposed to radiation. The objective of this study is to manage such radiation exposure. We measured the airborne radioactivity concentration at a 30 MeV cyclotron radioisotope production facility to assess whether the exhaust gas was contaminated. Additionally, we investigted the radioactive contamination of the air filter for efficient air purification and radiation safety control. To measure the airborne radiation concentration, specimens were collected weekly for 4 h after the beginning of the radioisotope production. Regarding the air purifier, five specimens were collected at different positions of each filter-pre-filter, high-efficiency particulate air filter, and charcoal filter-installed in the cyclotron production room. The concentrations of F-18, I-123, I-131, and Tl-201 generated in the radioiodine production room were $13.5Bq/m^3$, $27.0Bq/m^3$, $0.10Bq/m^3$, and $11.5Bq/m^3$, respectively; the concentrations of F-18, I-123, and I-131 produced in the radioisotope production room were $0.05Bq/m^3$, $16.1Bq/m^3$, and $0.45Bq/m^3$, correspondingly; and those of F-18, I-123, I-131, and Tl-201 generated in the accelerator room were $2.07Bq/m^3$, $53.0Bq/m^3$, $0.37Bq/m^3$, and $0.15Bq/m^3$, respectively. The maximum radiation concentration of I-123 generated in the radioiodine production room was 1,820 Bq/g, which can be disposed after 2 days. The maximum radiation concentration of Tl-202 generated in the radioisotope production room was 205 Bq/g, and this isotope must be stored for 53 days. The I-123 generated in the radioiodine production room had a maximum concentration of 1,530 Bq/g and must be stored for 2 days. The maximum radiation concentration of Na-22 generated in the radioisotope production room was 0.18 Bq/g and this isotope must be disposed after 827 days. To manage the exhaust, the efficiency of air purification must be enhanced by selecting an air purifier with a long life and determining the appropriate replacement time by examining the differential pressure through systematic measurements of the airborne radiation contamination level.

30 MeV 사이클로트론 시설 위험성 평가 (Risk Assessment of 30 MeV Cyclotron Facilities)

  • 정교성;김종일;이진우
    • 방사선산업학회지
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    • 제11권1호
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    • pp.39-45
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    • 2017
  • A cyclotron is a kind of particle accelerator that produces a beam of charged particles for the production of medical, industrial, and research radioisotopes. More than 30 cyclotrons are operated in Korea to produce $^{18}F$, an FDG synthesis at hospitals. A 30-MeV cyclotron was installed at ARTI (Advanced Radiation Technology Institute, KAERI) mainly for research regarding isotope production. In this study, we analyze and estimate the items of risk such as the problems in the main components of the cyclotron, the loss of radioactive materials, the leakage of coolant, and the malfunction of utilities, fires and earthquakes. To estimate the occurrence frequency in an accident risk assessment, five levels, i.e., Almost certain, Likely, Possible, Unlikely, and Rare, are applied. The accident consequence level is classified under four grades based on the annual permissible dose for radiation workers and the public in the nuclear safety law. The analysis of the accident effect is focused on the radioactive contamination caused by radioisotope leakage and radioactive material leakage of a ventilation filter due to a fire. To analyze the risks, Occupation Safety and Health Acts is applied. In addition, action plans against an accident were prepared after a deep discussion among relevant researchers. In this acts, we will search for hazard and introduce the risk assessment for the research 30-MeV cyclotron facilities of ARTI.

의료기관의 환자 피폭선량 관리 실태조사 (A Survey of the Management of Patient Dose at Medical Center)

  • 전고은;진계환
    • 한국방사선학회논문지
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    • 제3권1호
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    • pp.23-28
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    • 2009
  • 방사선동위원소 I-131을 이용한 질병의 치료는 핵의학 분야의 아주 중요한 부분을 차지하고 있다. 환자피폭에서 주의사항으로는 첫째 진료목적상 필요로 하는 선량을 초과하지 말아야 한다. 둘째 불필요한 피폭을 억제하여야 한다. 셋째 방사선을 사용하지 않고 동일한 진료목적을 달성할 수 있는지 면밀히 검토해봐야 한다. 이러한 목적을 달성하기 위해서는 환자에 대한 피폭선량의 평가가 필요하다. 본 연구에서는 치료병실 환자의 안전관리를 도모하고자 에어샘플러를 이용하여 공기를 채집하고, 채집한 시료의 방사선을 HPGe 감마카운터로 측정하였다. 치료병실에서 채집한 시료의 I-131 측정결과의 최고값은 $404.11Bq/m^3$, 평균값은 $228.27Bq/m^3$, 최저값은 $126.17Bq/m^3$ 이었다.

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$Na^{131}I$에 의(依)한 오염도(汚染度) 및 오염제거(汚染除去)의 실험적(實驗的) 연구(硏究) (An Experimental Study on Airborne Contamination and Decontamination for $Na^{131}I$ Solution)

  • 추성실;박창윤
    • Journal of Radiation Protection and Research
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    • 제9권2호
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    • pp.112-117
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    • 1984
  • A lot of radioisotopes are applied to medical fields. It's very important to measure the activities on airborne radioiodine discharged in air from $Na^{131}I$ solutions and from patients treated with radioiodine. Also surface decontamination is another one important problem to be completly solved in the isotope laboratory where there is always the possibility of radiation contamination. The Authors measured the activities on airborne radioiodine with RI collector and scintillation counter. 1. The mean accumulative activity of airborne radioiodine discharged into air from $Na^{131}I$ solution was measured as $1.3{\times}10^{-3}/hr$ rate, and the maximum value was $1.8{\times}10^{-3}/hr$. 2. Radioactivity rate per hour of airborne iodine discharged into air from patients treated with $Na^{131}I$ was measured as $6.2{\times}10^{-5}/hr$ at 8 hour after administration of radioiodine and decreased into $2{\times}10^{-6}/hr$ after 24 hour. 3. Metalic surfaces such as stainless steel or aluminum are decontaminated 5 to 6 times more rapidly than wood and concrete surfaces. 4. Decontamination with wet wiping with detergent was 9 to 10 times more rapidly than dry wiping method, but dry wiping was useful for the first step to prevent spreading and flowing from liquid radioactive materials.

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