• 약학회지
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• 제39권6호
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• pp.577-584
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• 1995

On the combination of antacid, the pharmacokinetics and gastric adhesion of [$^{14}c$]aceglutamide aluminium complex([$^{14}C$]AGA) were examined in rats. Specially, this study was focused on the drug interaction that the co-administration of antacid may affect the oral absorption and gastric adhesion of aceglutamide aluminium complex(AGA). In the study of the oral co-administration of [$^{14}C$] AGA and antacid(aluminium hydroxide and magnesium hydroxide(AM)), the radioactivity of plasma and urinary recovery was lower than that of [$^{14}C$]AGA alone administered group. However, the cumulative recovery of radioactivity in feces was increased significantly. The comparative bioavailability of [$^{14}C$] AGA from the plasma concentration-time curve and urinary recovery was about 60%. In vitro, the effect of antacid on the gastric adhesion of AGA was not significatly different between AGA and AGA/antacid treatment. And it accorded well with the result of in vivo experiment. In conclusion, on the combination of antacid, the oral absorption of AGA was decreased by the gastric adhesion was not affected in respect of drug interaction.

• Journal of Radiation Protection and Research
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• 제45권1호
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• pp.16-25
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• 2020

Background: To investigate radiological effects on biota, it is necessary to assess radiation dose for flora and fauna living in a terrestrial ecosystem. This paper presents a dynamic model to assess radioactivity concentration and radiation dose of terrestrial flora and fauna after a nuclear accident. Materials and Methods: Litter, organic soil, mineral soil, trees, wild crops, herbivores, omnivores, and carnivores are considered the major components of a terrestrial ecosystem. The model considers the physicochemical and biological processes of interception, weathering, decomposition of litter, percolation, root uptake, leaching, radioactive decay, and biological loss of animals. The predictive capability of the model was investigated by comparison of its predictions with field data for biota measured in the Fukushima forest area after the Fukushima nuclear accident. Results and Discussion: The predicted radioactive cesium inventories for trees agreed well with those for evergreens and deciduous trees sampled in the Fukushima area. The predicted temporal radioactivity concentrations for animals were within the range of the measured radioactivity concentrations of deer, wild boars, and black bears. The radiation dose for the animals were, for the whole simulation time, estimated to be much smaller than the lower limit (0.1 mGy·d^-1) of the derived consideration reference level given by the International Commission on Radiological Protection for terrestrial flora and fauna. This suggested that the radiation effect of the accident on the biota in the Fukushima forest would be insignificant. Conclusion: The present dynamic model can be used effectively to investigate the radiological risk to terrestrial ecosystems following a nuclear accident.

• 분석과학
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• 제13권6호
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• pp.693-698
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• 2000

본 일련의 실험은 가동중인 핵시설 주위의 자연환경내 방사성탄소 농도준위 변화의 간접적인 추적을 통하여 체계적이고 장기간에 걸친 환경감시 목적으로 수행되었다. 나무 나이테 분석을 이용한 방사성탄소 농도 측정 결과는 핵시설 가동 후 농도 준위가 증가한 것을 나타내었으며, 그 변화는 발전량과 밀접한 상관관계가 있음을 알 수 있었다. 한편 섬유소 처리를 통한 안정 동위원소비, ${\delta}^{13}C$을 측정한 결과는 -30‰을 나타내었으며, 이 값은 수동법 및 능동법으로 채취한 대기 시료중의 $^{13}C$값 -17‰ 및 -8‰과는 매우 다른 결과를 나타내었다. 이런 차이는 광합성에 의한 동위원소 분별효과라고 가정할 수 있으나, 이 문제는 심도있는 연구가 필요하다.

• Nuclear Medicine and Molecular Imaging
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• 제42권4호
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• pp.261-266
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• 2008

We established a model to calculate radioactive waste from sewage disposal tank of hospitals to optimize the number of patients receiving inpatient radioiodine therapy within the safety guideline in our country. According to this model and calculation of radioactivity concentration using the number of patients per week, the treatment dose of radioiodine, the capacity and the number of sewage tanks and the daily amount of water waste per patient, estimated concentration of radioactivity in sewage waste upon disposal from disposal tanks after longterm retention were within the safety guideline (30 Bq/L) in all the hospitals examined. In addition to the fact that we could increase the number of patients in two thirds of hospitals, we found that the daily amount of waste water was the most important variable to allow the increase of the number of patients within the safety margin of disposed radioactivity. We propose that saving the water amount be led to increase the number of patients and they allow two patients in an already furnished hospital inpatient room to meet the increasing need of inpatient radioiodine treatment for thyroid cancer.

• Journal of Radiation Protection and Research
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• 제45권4호
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• pp.154-162
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• 2020

Background: Several studies have reported that wild mushrooms contain high amounts of radioactive cesium (137Cs). After the Fukushima Daiichi Nuclear Power Plant Accident, a significantly high concentration of 137Cs has been detected in wild mushrooms, and their consumption may be the cause of the chronic internal exposure of local consumers to radioactivity. Therefore, an accurate evaluation of the internal radioactivity resulting from mushroom ingestion is needed. Materials and Methods: The 137Cs elution rate through the cooking and digestion stages was evaluated using in vitro experiments. The edible mushroom Pleurotus djamor was taken as a sample for the experiments. The mushrooms were cultivated onto solid media containing 137Cs. We evaluated the internal dose based on the actual conditions using the elution rate data. For various cooking methods, the results were compared with those of other wild edible mushrooms. Results and Discussion: From the elution experiment through cooking, we proved that 25%-55% of the 137Cs in the mushrooms was released during soaking, boiling, or frying. The results of a simulated digestion experiment after cooking revealed that almost all the 137Cs in the ingested mushrooms eluted in the digestive juice, regardless of the cooking method. The committed effective dose was reduced by 20%-75% when considering the dissolution through the cooking process. Conclusion: We found that cooking lowers 137Cs concentration in mushrooms, therefore reducing the amount of radioactivity intake. Besides, since there were differences between mushroom types, we demonstrated that the internal exposure dose should be evaluated in detail considering the release of 137Cs during the cooking stages.

• Journal of Radiation Protection and Research
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• 제48권2호
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• pp.84-89
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• 2023

Background: Food consumption is one of the most important routes for radionuclide intake for the public; therefore, there is the need to have a comprehensive understanding of the amount of radioactivity in food products. Consumption of radionuclide-contaminated food could increase potential health risks associated with exposure to radiation such as cancers. The present study aims to determine radioactivity levels in some food products (milk, rice, sugar, and wheat flour) consumed in Mali and to evaluate the radiological effect on the public health from these radionuclides. Materials and Methods: The health impact due to ingestion of radionuclides from these foods was evaluated by the determination of activity concentration of radionuclides ²³⁸U, ²³²Th, ⁴⁰K, and ¹³⁷Cs using gamma spectrometry system with high-purity germanium detector and radiological hazards index in 16 samples collected in some markets, mall, and shops of Bamako-Mali. Results and Discussion: The average activity concentrations were 9.8±0.6 Bq/kg for ²³⁸U, 8.7±0.5 Bq/kg for ²³²Th, 162.9±7.9 Bq/kg for ⁴⁰K, and 0.0035±0.0005 Bq/kg for ¹³⁷Cs. The mean values of radiological hazard parameters such as annual committed effective dose, internal hazard index, and risk assessment from this work were within the dose criteria limits given by international organizations (International Commission on Radiological Protection and United Nations Scientific Committee on the Effects of Atomic Radiation) and national standards. Conclusion: The results show low public exposure to radioactivity and associated radiological impact on public health. Nevertheless, this study stipulates vital data for future research and regulatory authorities in Mali.

• 한국의학물리학회지:의학물리
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• 제6권2호
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• pp.71-81
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• 1995

Acetazolamide (Diamox) 사용전후 〔Tc-99m〕ECD SPECT를 이용한 연속 뇌촬영은 뇌혈관의 혈역학 예비를 평가하기 위하여 사용되고 있다. 그러나 SPECT Diamox 영상의 정량적 평가 가능성은 검출기의 해상도, 감쇄, 산란, 노이즈, 그리고 데이타 분석 방법들에 의해 제한되고 있다. 알고 있는 양의 방사능을 채운 팬텀을 측정함으로써 민감도를 측정하거나 또는 분석할 수도 있다. 그러나 임상환경에서 환자를 시뮬레이션하는 현실성 있는 팬텀을 만드는 것은 매우 어렵다. Diamox 사용전후 ECD SPECT의 민감도가 컴퓨터 시뮬레이션에 의해 측정되었다. 민감도는 ($\Delta$N/N)/($\Delta$S/S)$\times$100%로 정의되고 $\Delta$N 은 측정된 데이타에서 Diamox 사용후와 사용전의 평균값 차이이고, $\Delta$N은 측정된 데이타에서 Diamox 사용전 평균값이고, $\Delta$S 는 모형에서 Diamox 사용후와 사용전의 평균값이고, S는 모형에서 Diamox 사용전 평균값이었다. Diamox를 이용한 임상연구에서는 Diamox 후에서 Diamox 전 데이타를 감산한 후 Diamox 에 의한 방사능 양의 변화를 측정함으로써 방사능의 변화율이 결정 될 수 있다. 그러나 100% 민감도를 위한 최적의 감산 양은 알려져 있지 않고 이것은 컴퓨터 시뮬레이션을 이용 철저한 민감도 분석을 요한다. Diamox 사용전후 연속 뇌 SPECT 영상 모형을 위하여 30% 증가된 방사능 양을 Diamox 영향으로 했을때 민감도는 0, 100, 150, 200% 감산에 대해 각각 51.03, 73.40, 94.00, 130.74%로 측정되었다. 민감도분석은 검출기의 해상도에 의한부분용적 효과와 통계적 노이즈는 방사능측정의 과소 평가가 된다는 것을 보였고 과소 평가 되는 양은 방사능 양이 몇 % 증가했는가 또는 Diamox 후 데이타에서 Diamox 전 데이타를 몇 % 감산 했는가에 의존된다는 것을 보였다. 임상에서 방사능 양의 변화가 약 30% 라 기대했을때 150%의 감산이 최적인 것으로 나타났다. 컴퓨터 시뮬레이션은 Diamox 전후의 ECD SPECT 민감도를 연구하는데 매우 중한 기술로 생각된다.

• 방사성폐기물학회지
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• 제2권3호
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• pp.219-230
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• 2004

Most of the low-level liquid radioactive wastes generated from PWR plants are classified into high or low total suspended solid(HTDS or LTDS), and into radiochemical and radioactive laundry waste. Although the evaporation process has a high decontami- nation ability, it has several problems such as corrosion, foam, and congestion. A new liquid waste disposal process using the ion-exchange demineralizer(IED), instead of the current evaporation process, has been introduced into the Yonggwang NPP #5 and 6. These two methods have been compared to understand the differences in this study. Aspects compared here were the released radioactivity amount of the liquid radioactive wastes, the dose of off-site residents, the decontamination factor, and the amount of the solid radioactive wastes. The IED system is designed to discharge higher radioactivity about 20% than the evaporating system, and the actual radioactivity released from the evaporating and IED system were 0.473mCi and 1.098mCi, respectively. The radioactivity released from the IED was 2.32 times higher than that of the evaporating system. The dose of off-site residents was $2.97{\times}10^{-6}$mSv for the evaporating system, and $6.47{\times}10^{-6}$mSv for IED. The decontamination factor(DF) of the evaporator is, in most cases, far lower than the lower limits of detection(LLD) with the Ge-Li detector. Due to the low concentration of the liquid wastes collected from the liquid waste system, the decontamination factor of IED is very low. Since there is not enough data on the amount of solid radioactive wastes generated by the evaporation system, the comparison on these two systems has been conducted on the basis of the design, and the comparison result was that the evaporating system generated more wastes about 40% than IED.

• 방사선산업학회지
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• 제17권4호
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• pp.457-469
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• 2023

The clearance level by nuclide is announced by the Nuclear Safety and Security Commission. However, the clearance level of uranium existing in nature has not been announced, and research is needed. Therefore, the purpose of this study was to evaluate the clearance level of uranium nuclides appropriate to domestic conditions preliminary. For this purpose, this study selected major processes for recycling metal wastes and analyzed the exposure scenarios and major input factors by investigating the characteristics of each process. Then, the radiation dose to the general public and workers was evaluated according to the selected scenarios. Finally, the results of the radiation dose per unit radioactivity for each scenario were analyzed to derive the clearance level of uranium in metal waste. The results of the radiation dose assessment for both the general public and workers per unit radioactivity of uranium isotopes were shown to meet the allowable dose (individual dose of 10 µSv y^-1 and collective dose of 1 Man-Sv y^-1) regulated by the Nuclear Safety and Security Commission. The most conservative scenarios for volumetric and surface contamination were evaluated for the handling of the slag generated after the melting of the metal waste and the direct reuse of the contaminated metal waste into the building without further disposal. For each of these scenarios, the radioactivity concentration by uranium isotope was calculated, and the clearance level of uranium in metal waste was calculated through the radioactivity ratio by enrichment. The results of this study can be used as a basic data for defining the clearance level of uranium-contaminated radioactive waste.

• Nuclear Engineering and Technology
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• 제56권6호
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• pp.2317-2323
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• 2024

Medical linear accelerators with an energy of 8 MV or higher are radiated owing to photonuclear reactions and neutron capture reactions. It is necessary to quantitatively evaluate the concentration of radioactive isotopes when replacing or disposing them. HPGe detectors are commonly used to identify isotopes and measure radioactivity. However, because the detection efficiency is generally calibrated using a standard material with a density of 1.0 g/cm³, a self-absorption effect occurs if the density of the measured material is high. In this study, self-absorption correction factors were calculated for tungsten, lead, copper, and SUS-303, which are the main materials of medical linear accelerator head parts, for each gamma-ray energy using MCNP 6.2 code. The self-absorption effect was more pronounced as the energy of the emitted gamma rays decreased and the density of the measured materials increased. These correction factors were applied to the radioactivity measurements of the in-built and portable HPGe detectors. Furthermore, compared to the surface dose rate measured by the survey meter, the accuracy of the measurements of radioactivity improved by an average of 124.31 and 100.53 % for inbuilt and portable HPGe detectors, respectively. The results showed a good agreement, with an average difference of 3.70 and 5.24 %.