• Title/Summary/Keyword: radioactivity

검색결과 972건 처리시간 0.025초

$\textrm{N}_{G}$-Monomethyl-L-arginine의 대사 : 흰쥐에서 N-monomethylurea의 생성 (Metabolism of $\textrm{N}_{G}$-Monomethyl-L-arginine Formation of N-Monomethylurea in rat)

  • 조영봉
    • Environmental Analysis Health and Toxicology
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    • 제1권1호
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    • pp.81-86
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    • 1986
  • $^{14}$ C로 표지된 $N^{G}$ -mono[$^{14}$ C-methyl]-L-arginine을 흰쥐에 경구투여 하여 7일동안에 66.3%의 방사능이 회수되었다. 회수된 총방사능의 86.2%는 처음 24시간내에 배설되었으며, 그 분포는 산성 물질, 염기성물질, 중성물질 및 회수된 $N^{G}$ -monomethyl-L-arginine에 서 각각 33.3%, 40.2%, 12.5% 및 0.3%이었다. 중성물질 방사능의 약 50%는 N-monomethylurea에 해당하며 이는 투여한 전체방사능의 6%이었다.

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실내 환경 모니터링을 위한 다중 방사능계측 시스템 설계 (Multi-Radioactivity Measurement System Design for Indoor Environmental Monitoring)

  • 사공병일;김남호
    • 한국정보통신학회:학술대회논문집
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    • 한국정보통신학회 2022년도 춘계학술대회
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    • pp.459-461
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    • 2022
  • 본 논문에서는 실내 환경에서 검출되는 방사능을 측정하기 위한 계측 시스템을 제시한다. 일반 가정, 작업장, 연구소 등 다양한 공간에서 발생되는 방사능을 측정하고 이에 대한 예방을 위함이다. 다중 방사능 센서를 이용해서 여러 공간을 동시에 측정한다. 측정된 방사능 데이터는 지그비를 통해서 실시간으로 PC로 전달하여 모니터링하는 시스템이다. 소량의 방사능이라고 하더라고 만성 피폭으로부터의 예방을 위해 연구소 또는 작업장 같은 방사능 노출이 예상되는 곳은 필수적으로 설치되어야 한다고 생각된다.

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Development of a real-time mobile gamma-ray measurement system for shipboard use

  • Chang-Jong Kim;Mee Jang;Hyuncheol Kim;Jong-Myoung Lim;Wanno Lee;Gyu-Seong Cho
    • Nuclear Engineering and Technology
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    • 제55권11호
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    • pp.4077-4082
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    • 2023
  • Large areas must be rapidly screened to monitor radiation in marine environments. For this purpose, this study developed a mobile real-time gamma-ray measurement system for shipboard use and evaluated its performance. The system was developed to measure engine or generator cooling water by installing a canister inside the ship. The minimum detectable activity of the system is about 0.8 Bq/L for a 60 s measurement period, and real-time data transmission and remote control are possible. The system was tested in the field and is currently being installed and operated on ships in service. Such a ship-based real-time gamma-radiation measurement system is suitable for a wide range of marine radiation surveillance applications and is expected to be rapidly deployed.

제 3세대 백금착체 항암제 신약개발 3. General pharmacology and pharmacokinetic study of SKI 2053R

  • 정명희;김명석;김용식;고광호;이신웅;신상구;방영주;조용백;류근호
    • 한국응용약물학회:학술대회논문집
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    • 한국응용약물학회 1993년도 제2회 신약개발 연구발표회 초록집
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    • pp.75-75
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    • 1993
  • The general pharmacological profiles of SKI 2053R were investigeted on the central nervous system, autonomic nervous system, respiratory-cardiovascular system, digestive system and other systems. SKI 2053R had no significant pharmacological effects. Pharmacokinetic studies on time-course of blood levels, tissue distribution and excretion of SKI 20S3R were performed in rats and beagle dogs after intravenous administration of $^{14}$ C-labeled SKI 2053R. The blood level of radioactivity decreased in bi-or tri-exponential manners: rapidly decreased at $\alpha$-phase but slowly decreased at $\beta$-or ${\gamma}$-phase. $^{14}$ C SKI 2053R was well distributed to all tissues except central nervous system. Tissue concentration profiles of radioactivity were almost consistent wi th those of blood, but higher than those of plasma from 1 to 168 hrs after administration. Also, these results were consistent wi th those of whole body ARG study. The urinary and fecal excretions of radioactivity within 168 hr after administration were 84-87 and 9-11 % of total radioactivity of $^{14}$ C-SKI 2053R administered. In lactating rats, the levels of radioactivity in the milk were significantly lower than that in the blood, but slightly higher than that in the plasma. The disapperance of the radioactivity from the milk was similar as that in the plasma.

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방사능 관련 안전정보의 수산물 소비 영향에 관한 연구 (A study on the consumption of fishery products in relation with radioactivity-related safety information)

  • 강종호
    • 수산경영론집
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    • 제46권1호
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    • pp.145-155
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    • 2015
  • This study aims to look at the change in consumer awareness and behavior after Japan's 2013 nuclear power plant's radioactive water leakage and draw implications about them. Findings show that 81% of respondents decreased their consumption of fishery products after the nuclear incident, and kept on showing avoidance of imported fishery products including those from Japan. Also it showed that consumers more importantly considered safety when buying imported fishery products after the nuclear incident. The most common channel of receiving radioactivity safety information on fishery products were TV and online. However, the main reason for decreasing the consumption of fishery products was founded to be based on the inaccuracy of the information provided. However, many people said that they will increase their consumption of all fishery products if provided with accurate radioactivity information. Therefore, if accurate radioactivity information were to be spread effectively to the public, positive consumption rates of fishery products can be shown in the future. The inaccuracy of radioactivity safety information caused the rapid decrease of fishery products consumption in 2013 to be amplified. Therefore, this study showed the importance of the delivery of rapid, accurate and consistent information to consumers.

Study on the characteristics of airborne gross alpha and gross beta activities in the vicinity of nuclear facilities

  • Da-Young Gam;Chae-yeon Lee;Ji-Young Park;Hyuncheol Kim;Jong-Myoung Lim
    • Nuclear Engineering and Technology
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    • 제55권12호
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    • pp.4554-4560
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    • 2023
  • Continuous monitoring of radioactive substances over a prolonged duration can yield crucial insights into the levels of radiation exposure through inhalation, both in the vicinity of nuclear facilities and/or general environments. In this study, we evaluated long-term measurements (2012-2022) of gross alpha-beta activities in the air in the vicinity of nuclear facilities and reference site, distribution characteristics of temporal trends and spatial fluctuations, and factors affecting radioactivity levels. The average airborne gross-α (in mBq m-3) for onsite and off-site were 0.124 and 0.117, respectively, and the average airborne gross-β (in mBq m-3) measurements were 1.10 and 1.04, respectively. The activity ratio (AR) of gross-α and gross-β were calculated as a ratio of 0.12. The distribution characteristics of gross-α and gross-β activities in this study area are likely influenced by the meteorological factors and variations in airborne PM concentrations rather than the operation of the nuclear facility.

Bone Scan 검사 시 실제 환자에게 투여되는 용량 계산을 위한 실험 (Experiment to Calculate the Dosage of Radiopharmaceutical Products during the Bone Scan Tests)

  • 이왕희;안성민
    • 한국콘텐츠학회논문지
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    • 제15권4호
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    • pp.357-362
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    • 2015
  • 본 실험에서는 조영제를 사용하는 CT 혹은 MRI 검사 후, 3-way를 제거하지 않고, Bone scan 검사를 위해 내원한 50명의 환자를 대상으로 방사성 의약품 99mTc-MDP가 표지된 동위원소를 주사 할 때, 주사기와 3-way에 남게 되는 방사능을 측정하여, 실제 환자에게 투여된 방사능을 확인했다. 핵의학과 Bone scan 검사를 위해 내원한 환자 중 CT 혹은 MRI 검사 후 3-way를 유지하고 있는 50명의 환자를 대상으로 3-way를 통해 99mTc-MDP로 표지된 동위원소를 주사 한 후, 주사기와 3-way에 남아있는 방사능을 검량기로 측정하여 실제 투여된 용량을 확인 했다. 방사성의약품을 투여하기 전의 주사기의 방사능과 투여한 후 주사기와 3-way의 방사능을 측정한 결과, 투여 전 주사기의 방사능은 평균 31.75 mCi, 투여 후 주사기에 남은 방사능은 평균 1.22 mCi, 투여 후 3-way에 남은 방사능은 평균 0.95 mCi으로 측정되었다. 실제 환자에게 투여된 방사능은 평균 29.57 mCi로 처음 환자에게 투여하고자 했던 용량보다 평균2.18 mCi 가 환자에게 덜 투여됨을 알 수 있었다. Bone scan 검사 시, 3-way와 실린지에 남게 되는 방사능을 감안하여 투여 용량을 결정한다면, 실제 환자에게 투여하고자 하는 목적 용량을 좀 더 정확하게 투여 할 수 있을 것이다.

갑상선암 수술 전 진단목적의 $^{18}F$-FDG PET/CT Dual Time Point영상에서 SUV값과 방사능 농도 측정법의 유용성 평가 (The Preoperative Diagnosis of Thyroid Cancer in $^{18}F$-FDG PET/CT Dual Time Imaging of SUV and Evaluation of Radioactivity Measurement)

  • 이현국;강현수;양승오;한만석
    • 핵의학기술
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    • 제16권2호
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    • pp.99-105
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    • 2012
  • Purpose : This study is designed to compare two parameters reflecting $^{18}F$-FDG uptake, SUV and radioactivity, for diagnosis of thyroid cancer in dual time $^{18}F$-FDG PET/CT imaging and to find which parameter is more useful to decide whether the tumor is malignant or not. Materials and Methods : We performed retrospective study for 40 patients. All patients are diagnosed as primary thyroid cancer and examined $^{18}F$-FDG PET/CT. First, we got the dispersion of scattering beam of neck and lung apex to set a background and compared each dispersion, mean value, standard deviation of maxSUV and radioactivity. Also, mean maxSUV, ${\Delta}maxSUV$, ${\Delta}maxBq$/ml(%) and radioactivity between groups according to lesion's size based on biopsy are compared with independent-sample t-test. Results : the values that were from maxSUV and radioactivity measurement technique were compensated and calculated to practical values for mean comparison and patients were divided to two groups based on tumor size, Group1 ($size{\leq}1$ cm, n=21), Group2 (size>1 cm, n=19) for accurate comparison. In Group1, maxSUV (semi-quantitative analysis) was increased from $5.64{\pm}5.85$ (1.89~17.84) at first image to $5.90{\pm}5.01$ (1.95~18.22) at second image and radioactivity (Bq/ml) (quantitative analysis) showed similar increase from $5.93{\pm}6.38$ (2.50~16.75) at first image to $6.01{\pm}5.25$ (2.66~16.58) at second image. In Group2, TFmaxSUV was $10.54{\pm}14.36$ (2.54~33.89) in true first image, TSmaxSUV was $9.85{\pm}12.88$ (2.62~26.20) in true second image separately. The maxSUV showed a significant difference in the mean comparison between the two groups (p=0.035) But, mean radioactivity (Bq/ml) was $5.93{\pm}6.38$ (4.81~40.99) in true first image, $6.01{\pm}5.25$ (4.51~36.93) in true second image and didn't show a significant difference statistically (p=0.126) Conclusion : In diagnosis of thyroid tumor, SUV and radioactivity depending on $^{18}F$-FDG uptake showed high similarity with coefficient of determination (R2=0.939) and malignant evaluation results using dual time also showed similar aspect. Radioactivity for evaluation of malignant tumor didn't show better specificity or sensitivity than maxSUV.

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TRIGA Mark-II, III 연구로 시절의 폐로를 위한 시설의 잔류 방사선/능 평가 (Evaluation of Residual Radiation and Radioactivity Level of TRIGA Mark-II, III Research Reactor Facilities for Safe Decommissioning)

  • 이봉재;장시영;박승국;정운수;정기정
    • Journal of Radiation Protection and Research
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    • 제24권2호
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    • pp.109-120
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    • 1999
  • TRIGA Mark-II, III 연구로를 폐로함에 따라, 원자로를 비롯한 관련 시설로부터 작업자의 방사선피폭을 최소화하고 환경으로의 방사성물질 누출을 사전에 방지하며, 안전한 해체방법을 모색하여 해체공사시의 기술기준을 수립하기 위하여 해체대상 시설내에 잔존하고 있는 방사성물질의 방사선/능 준위를 측정 및 분석 평가하였다. 측정대상은 시설내의 바닥 및 벽면과 잔존 실험시설물의 표면, 수조내 방사화 물질의 표면, 시설내 잔존하고 있는 냉각수 등이다. 이들 측정대상에 대한 방사선량율과 표면오염도, 핵종 등을 측정, 분석 및 평가하였다. 또한 전산코드 Fispin 을 사용하여 원자로 수조내의 주요 방사화 물질에 대한 방사능양과 핵종을 평가하였다. 본 평가 결과는 해체계획서 작성시 기본자료로서 유용하게 사용되었다.

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국내 석탄연소 발전소에서 취급하는 천연방사성물질의 방사능 농도 분석 (Analysis of Radioactivity Concentration in Naturally Occurring Radioactive Materials Used in Coal-Fired Plants in Korea)

  • 김용건;김시영;지승우;박일;김민준;김광표
    • 방사선산업학회지
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    • 제10권4호
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    • pp.173-179
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    • 2016
  • Coals and coal ashes, raw materials and by-products, in coal-fired power plants contain naturally occurring radioactive materials (NORM). They may give rise to internal exposure to workers due to inhalation of airborne particulates containing radioactive materials. It is necessary to characterize radioactivity concentrations of the materials for assessment of radiation dose to the workers. The objective of the present study was to analyze radioactivity concentrations of coals and by-products at four coal-fired plants in Korea. High purity germanium detector was employed for analysis of uranium series, thorium series, and potassium 40 in the materials. Radioactivity concentrations of $^{226}Ra$, $^{228}Ra$, and $^{40}K$ were $2{\sim}53Bq\;kg^{-1}$, $3{\sim}64Bq\;kg^{-1}$, and $14{\sim}431Bq\;kg^{-1}$ respectively in coal samples. For coal ashes, the radioactivity concentrations were $77{\sim}133Bq\;kg^{-1}$, $77{\sim}105Bq\;kg^{-1}$, and $252{\sim}372Bq\;kg^{-1}$ in fly ash samples and $54{\sim}91Bq\;kg^{-1}$, $46{\sim}83Bq\;kg^{-1}$, and $205{\sim}462Bq\;kg^{-1}$ in bottom ash samples. For flue gas desulfurization (FGD) gypsum, the radioactivity concentrations were $3{\sim}5Bq\;kg^{-1}$, $2{\sim}3Bq\;kg^{-1}$, and $22{\sim}47Bq\;kg^{-1}$. Radioactivity was enhanced in coal ash compared with coal due to combustion of organic matters in the coal. Radioactivity enhancement factors for $^{226}Ra$, $^{228}Ra$, and $^{40}K$ were 2.1~11.3, 2.0~13.1, and 1.4~7.4 for fly ash and 2.0~9.2, 2.0~10.0, 1.9~7.7 for bottom ash. The database established in this study can be used as basic data for internal dose assessment of workers at coal-fired power plants. In addition, the findings can be used as a basic data for development of safety standard and guide of Natural Radiation Safety Management Act.