• 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 %.

• Nuclear Engineering and Technology
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• 제15권2호
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• pp.110-116
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• 1983

육상식물인 대두(Glycine max)에 있어서 Sr-90의 흡수 및 이행과정을 온실조건하에서 실험하여 다음과 같은 결과를 얻었다. 엽면처리한 Sr-90은 식물체의 다른 부위로 일부분만이 이행하였고 대부분은 잎에 그대로 잔류하여 낙엽에 의한 토양오염의 원인이 되고 있었다. 토양처리한 Sr-90은 뿌리를 통하여 흡수된 다음 잎, 줄기, 종자, 뿌리등 각 부위로 널리 분포되는데 식물의 생육단계에 따라 그 패턴이 달리 나타났다.

• Nuclear Engineering and Technology
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• 제54권2호
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• pp.469-478
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• 2022

Tritium was extracted from tritium-contaminated aluminum samples by heating it in a high-temperature furnace at 200, 300, or 400 ℃ for 15 h. The extracted tritium was analyzed by using a liquid scintillation counter (LSC); the sample thicknesses were 0.4 and 2 mm. The differences in tritium extraction over time were also investigated by cutting aluminum stick samples into several pieces (1, 5, 10, and 15) with the same thickness, and subsequently heating them. The results revealed that there are most of the hydrated material based on tritium on the surface of aluminum. When the temperature was increased from 200 or 300 ℃-400 ℃, there are no large differences in the heating duration required for the radioactivity concentration to be lower than the MDA value. Additionally, at the same thickness, because the surface of aluminum is only contaminated to tritiated water, cutting the aluminum samples into several pieces (5, 10, and 15) did not have a substantial effect on the tritium extraction fraction at any of the applied heating temperatures (200, 300, or 400 ℃). The proportion of each tritium-release materials (aluminum hydrate based on tritium) were investigated via diverse analyses (LSC, XRD, and SEM-EDS).

• 한국방사선학회논문지
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• 제8권6호
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• pp.293-299
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• 2014

Compton suppression 장치는 Compton 산란 반응을 이용하여, 스펙트럼의 Compton continuum 부분을 억제함으로써 Compton continuum 영역 내에서의 감마선 피크들의 분석을 보다 명확하게 할 수 있게 해주는 장치이다. 표층토양 시료에서 검출된 인공 방사능인 $^{137}Cs$과 자연 방사능인 $^{40}K$핵종의 방사능 농도 값들에 대한 방사능 계수치가 백그라운드를 상회하는 측정값이 발생되거나, 불필요한 방해피크나 비해석 대상 피크에 대하여 검출된 표준선원의 방사능 농도 값들의 실측치에 대한 background를 비억제 스펙트럼(Compton Unsuppression)과 억제 스펙트럼(Compton suppression)을 적용시켜 측정 에너지에 대한 교정을 알고자 점선원인 $^{137}Cs$을 거리별에 따라 측정하여, 몬테칼로 시뮬레이션과 비교 분석함으로서 효율적인 검출 능력을 얻고자 함이며, Compton 억제 인자를 보면 거리가 멀어짐에 따라 CSF 값이 클수록 더 많은 Compton suppression가 이루어졌음을 알 수 있고, $^{137}Cs$을 이용한 컴프턴 비억제 모드와 억제모드로 측정된 스펙트럼에서 컴프턴 연속에 의한 백그라운드가 감소함을 알 수 있었다.

• 한국환경농학회지
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• 제6권1호
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• pp.7-16
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• 1987

수도체(水稻體) 및 담수토양중(湛水土壤中) carbofuran의 행적(行跡)을 구명(究明)하기 위하여 토양표면(土壤表面)에 $3-^{14}C-carbofuran$을 처리(處理)하고 시기별(時期別)로 수도체(水稻體)로의 흡수(吸收), 이행(移行) 및 대사양상(代謝樣相)을 조사(調査)하였다. 토양표면(土壤表面)에 처리(處理)한 carbofuran은 근부(根部)를 통(通)하여 수도체내(水稻體內)로 신속히 흡수(吸收), 이행(移行)되었으며 처리(處理) 후(後) 2일이내(以內)에 엽선단(葉先端)에 도달하고 축적(蓄積)되는 경향(傾向)을 보였다. 약제처리(藥劑處理) 20日 후(後) 수도체(水稻體)로 흡수(吸收)된 방사능(放射能) 총(總) 처리방사능(處理放射能)20%이상(以上)었다. 수도체중(水稻體中)arbofuran의 주요(主要) 대사산물(代謝産物)은 3-hydroxycarbofuran이었고, 3-ketocarbofuran 및 3종(種)의 phenol성(性) 대사물(代謝物)이 검출(檢出)되었다. 수용성(水溶性) conjugates의 대부분(大部分)은 glycoside결합형태(結合形態)이었으며 주요 aglycon은 3-hydroxycarbofuran이었다. 토양중(土壤中) 방사능(放射能)은 처리(處理) 3日 후(後)까지는 빠른 속도(速度)로 감소(減少)하였으나 그 이후(以後) 거의 일정(一定)한 수준(水準)을 보였다. 비추출성(非抽出性) 방사능(放射能)은 시간(時間)이 경과(經過)함에 따라 증가(增加), 처리(處理) 20일(日) 후(後) 총(總) 처리(處理) 방사능(放射能)의 50%이상(以上)을 차지하였으며 유기물(有機物) 분획별(分劃別) 분포(分布)는 humin>fulvic acid>humic acid 순(順)이었다. B두캐력무 ring의 개열반응(開裂反應)에 의한 $^{14}CO_2$방출(放出)은 처리(處理) 후(後) 20일(日)까지 1.8%로 미미한 수준(水準)을 나타내었다.

• 한국지하수토양환경학회:학술대회논문집
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• 한국지하수토양환경학회 2003년도 추계학술발표회
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• pp.293-297
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• 2003

A series of laboratory experiments was conducted to investigate the fixation characteristics of poly(vinylalcohol)-poly(methacrylic acid)(PVA-PMAA) mixed solution on the soluble (equation omitted)-radionuclides. Using the potentiometric titration technique, it was found out that the PVA and PMAA in a solution form intermacromolecular complex. The mobilized portion of each radionuclide by water from sand surface treated with a fixative was measured by ${\gamma}$-ray spectroscopy, The mobilized portion of minor radionuclides such as $^{241}$ Am, $^{154}$ Eu, $^{155}$ Eu and $^{144}$ Ce were higher than those of $^{134}$ Cs and $^{137}$ Cs. The capability of PVA-PMAA system was better among the candidate solutions for the fixation of total (equation omitted)-radioactivity, $^{134,137}$Cs which is composed of more than 85 % of total ${\gamma}$-radioactivity could be fixed effectively by the PVA-PMAA solution.

• Nuclear Engineering and Technology
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• 제32권3호
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• pp.205-213
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• 2000

A series of laboratory experiments was conducted to investigate the fixation characteristics of poly(vinylalcohol)-poly(methacrylic acid)(PVA-PMAA) mixed solution on the soluble ${\gamma}$- radionuclides. Using the potentiometric titration technique, it was found out that the PVA and PMAA in a solution form intermacromolecular complex. The mobilized portion of each radionuclide by water from sand surface treated with a fixative was measured by ${\gamma}$-ray spectroscopy. The mobilized portion of minor radionuclides such as 241Am, 154Eu, 155Eu and 144Ce were higher than those of 134Cs and 137Cs. The capability of PVA-PMAA system was better among the candidate solutions for the fixation of total ${\gamma}$-radioactivity. 134,137Cs which is composed of more than 85 % of total ${\gamma}$-radioactivity could be fixed effectively by the PVA-PMAA solution.

• 대한미생물학회지
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• 제35권3호
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• pp.203-214
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• 2000

Porphyromonas gingivalis has been implicated in periodontal diseases. Accumulating evidence suggests that cardiovascular disease is the most prevalent medical problem in patients with periodontal diseases. In order to check the possibility that P. gingivalis is involved in coronary heart disease, the present study was performed to observe P. gingivalis adherence and invasion of human coronary artery endothelial cells (HCAEC) and production of cytokines and growth factors by HCAEC upon P. gingivalis infection. $^3H$-labeled P. gingivalis 381 was incubated with HCAEC for 90 min. The radioactivity of the washed HCAEC was a measure of the absorbed (adhering and invading) P. gingivalis. The absorption radioactivity of the HCAEC infected by P. gingivalis was determined to be 59.58% of the input bacterial cells. In contrast, the absorption radioactivity of the cells infected by S. gordonii Challis which was employed as a control was negligible (0.59%). DPG3, a P. gingivalis mutant defective of fimbriae, appeared to be impaired to some extent in capability of adherence/invasion as compared to that of the parental strain 381, showing 43.04% of the absorption radioactivity. The absorption radioactivity of the HCAEC infected by P. gingivalis 381 in the presence of excessive fimbriae at the concentrations of $50\;{\mu}g$ and $100\;{\mu}g/ml$ was 57.27 and 45.44%, respectively. Invasion of HCAEC by P. gingivalis 381 was observed by an antibiotic (metronidazole) protection assay and transmission electron microscopy (TEM). In the antibiotic protection assay, invasion by the bacterium was measured to be 0.73, 1.09, and 1.51% of the input bacterial cells after incubation for 30, 60, and 90 min, respectively. Invasion by DPG3 was shown to be 0.16% after 90-min incubation. In comparison of invasion efficiency at 90 min of the incubation, the invasion efficiency of DPG3 was 0.37% while that of its parental strain 381 was 2.54%. The immunoblot analysis revealed fimbriae of P. gingivalis did not interact with the surface of HCAEC. These results suggest that fimbriae are not the major contribution to the adherence of P. gingivalis to HCAEC but may be important in the invasion of HCAEC by the bacterium. The presence of cytochalasin D ($1\;{\mu}g/ml$) and staurosporine ($1\;{\mu}M$) reduced the invasion of HCAEC by P. gingivalis 381 by 78.86 and 53.76%, respectively, indicating that cytoskeletal rearrangement and protein kinase of HCAEC are essential for the invasion. Infection of P. gingivalis induced HCAEC to increase the production of TNF-${\alpha}$. by 60.6%. At 90 min of the incubation, the HCAEC infected with P. gingivalis cells was apparently atypical in the shape, showing loss of the nuclear membrane and subcellular organelles. The overall results suggest that P. gingivalis may cause coronary heart disease by adhering to and invading endothelial cells, and subsequently damaging the cells.

• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1259-1265
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• 2020

A beta ray scanner was proposed for in-situ discrimination of beta and gamma ray radioactivity. This scanner is based on the principle that gamma and beta rays experience different changes in detection efficiency in scintillators with different geometries, especially with regard to the scintillator thickness. The ratios of the counting rates of gamma rays (R_gamma), beta rays (R_beta), and sample measurements (R_total) in a thick scintillator to those in a thin one are reported. The parameter X_thick, which represents the counting rate contributed by beta rays to the total counting rate in the thick scintillator, was derived as a function of those ratios. The values of R_gamma and R_beta for ⁶⁰Co and ⁹⁰Sr sources were estimated as 3.2 ± 0.057 and 0.99 ± 0.0049, respectively. The estimated beta ray contributions had relative standard deviations of 2.05-4.96%. The estimated range of the beta rays emitted from ⁹⁰Sr was 19 mm as per the Monte Carlo N-Particle simulation, and this value was experimentally verified. Homogeneous and surface contaminations of ⁶⁰Co and ⁹⁰Sr-⁹⁰Y were simulated for application of the proposed method. The counting rate contributed by the beta rays was derived and found to be proportional to the concentration of ⁹⁰Sr-⁹⁰Y contamination.