• 공업화학
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• 제9권4호
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• pp.516-522
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• 1998

아크릴산과 가교제로서 1,2-propandiol dimethacrylate (PDDMA) 및 1,1,1-trimethylolethane triacrylate (TMETA)를 셀룰로오스에 방사선 그라프트 중합시킨 후 5% 수산화나트륨 수용액으로 처리하여 흡수성 재료를 제조한 다음, 순수한 물과 염화나트륨 수용액에 대한 흡수성에 대하여 고찰하였다. 가교제로서 다관능성 단량체가 포함된 아크릴산 그라프트 셀룰로오스의 흡수력은 PDDMA는 0.75부피%에서 TMETA는 1.0부피%에서 최대점을 나타내었다. 방사선 그라프트 중합법에 의하여 제조한 흡수성 셀룰로오스와 상용화된 여성용 생리용품과의 물 및 염화나트륨 수용액에 대한 흡수율을 비교해 본 결과 여성용 생리용품의 경우 물에 대한 흡수율은 21 g/g이고 염화나트륨 수용액에 대한 흡수율은 22 g/g을 나타내었으나, 본 방사선 그라프트 중합법에 의하여 제조한 셀룰로오스는 물과 염화나트륨 수용액에 대하여 최대 298 g/g, 54 g/g의 우수한 흡수능을 나타내었다.

• Journal of Radiation Protection and Research
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• 제22권4호
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• pp.251-261
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• 1997

방사성 동위원소 등의 고준위 방사성물질을 운반하기 위한 운반용기는 국내외의 관련법규에 따라 정상수송은 물론 가상사고조건에서도 방사성물질의 누설이 발생되지 않도록 방사선차폐, 열 및 구조적 건전성이 유지되어야 한다. 운반용기의 건전성 평가는 시험모델을 이용한 시험적 방법과 전산해석 코드를 이용한 해석적 방법에 의하여 이루어지고 있다. 본 논문에서는 원자력연구소의 하나로에서 생산되는 동위원소를 동위원소 생산시설까지 이송하기 위한 HTS (Hydraulic Transfer System) 방사성 동위원소 운반용기의 안전성을 평가하였다. 방사선차폐해석, 열해석 및 구조해석을 수행한 결과 동위원소 운반용기는 정상수송조건 뿐만 아니라 가상사고조건에서도 건전성이 유지되는 것으로 나타났다.

• Journal of Radiation Protection and Research
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• 제43권2호
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• pp.75-84
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• 2018

Background: Gamma-ray spectrometry helps in radiation shielding problems and different applications of radioisotopes. Experimental arrangements including broad beam geometries are widely used. The aim is to investigate and evaluate the ${\gamma}-ray$ spectra via attenuation by environmental materials. Materials and Methods: The photo peak to nominated parts in the ${\gamma}-ray$ spectra and the attenuation coefficients ${\mu}_b/{\rho}$ from broad beam geometries are measured for the materials water, soil, sand and cement at the energies 0.662, 1.25, and 1.332 MeV with a $3{^{\prime}^{\prime}}{\times}3{^{\prime}^{\prime}}$ NaI(Tl) detector. Results and Discussion: The ${\gamma}-ray$ spectra vary according to changes in the effective atomic number $Z_{eff}$ of the attenuator, the photon energy and the solid angle. The peak to total ratios are the most sensitive parts to variations in the experimental conditions and overturn in the region 0.663 MeV to 1.332 MeV. This is indicated as inversion trend. The results are discussed in view of $Z_{eff}$ and the experimental conditions. The intensity build-up is larger at the lower energy and larger scattering angles in agreement with Klein-Nishina formula and other results. The build-up factor B is$${\sim_=}$$1 at high ${\gamma}-energies$ and small scattering angles. Conclusion: The sensitivity to material characteristics decrease gradually from peak: to total, to Compton valley, to Compton plateau ratios. Rigorous collimation is necessary at small energies. Cement, of the largest $Z_{eff}$, is characterized by the maximum broad beam mass attenuation coefficients ${\mu}_b/{\rho}$. The obtained results provide information to decide for the suitable experimental set-up based on aim of the work.

• Nuclear Engineering and Technology
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• 제51권8호
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• pp.1991-1997
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• 2019

In this manuscript, we present a method for the direct calculation of an ambient dose equivalent (H^* (10)) for the external gamma-ray exposure with an energy range of 40 keV to 2 MeV in an electronic personal dosimeter (EPD). The designed EPD consists of a 3 × 3 ㎟ PIN diode coupled to a 3 × 3 × 3 ㎣ CsI (Tl) scintillator block. The spectrum-to-dose conversion function (G(E)) for estimating H^* (10) was calculated by applying the gradient-descent method based on the Monte-Carlo simulation. The optimal parameters for the G(E) were found and this conversion of the H^* (10) from the gamma spectra was verified by using ²⁴¹Am, ¹³⁷Cs, ²²Na, ⁵⁴Mn, and ⁶⁰Co radioisotopes. Furthermore, gamma spectra and H^* (10) were obtained for an arbitrarily mixed multiple isotope case through Monte-Carlo simulation in order to expand the verification to more general cases. The H^* (10) based on the G(E) function for the gamma spectra was then compared with H^* (10) calculated by simulation. The relative difference of H^* (10) from various single-source spectra was in the range of ±2.89%, and the relative difference of H^* (10) for a multiple isotope case was in the range of ±5.56%.

• 대한화장품학회지
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• 제22권2호
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• pp.201-210
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• 1996

Predictive tests for the identification of contact sensitizing chemicals have been developed. We measured the sensitization potential with three predictive tests, the in vitro and the in vivo Local Lymph Node Assay(LLNA), ELISA to detect interferon-gamma(IFN-${\gamma}$) from supernatant and flow cytometry to detect change of cell surface proteins, using draining lymph nodes of mice. BALB/c mice were exposed to various chemicals or vehicles on the ears daily for 3 consecutive days in all experiments. With some exceptions of propyl paraben, neomycin sulfate, the in vivo LLNA was able to detect the sensitizing capacity of test chemicals and was more sensitive than the in vitro LLNA for chemicals used in the present study. In another experiment, contact sensitivity was assessed by the ELISA to detect IFN-Υ from the supernatants of the cultured LNCs after sensitization with chemicals. There was a good correlation between the LLNA and the IFN-Υ production for test chemicals. We also examined the change of cell surface proteins on LNCs after sensitization by flow cytometry for some cell adhesion molecules(ICAM-1, E-cadherine, B7 molecule), T cell markers(CD3, CD4, CD8, T$\alpha$$\beta$,T${\gamma}$$\delta$) and B cell markers(LR1, CD45R, I-Ad). The number of ICAM-1 positive cells and B cells in LNCs were increased after sensitization with DNCB, TNCB, isoeugenol and 25%, 50% cinnamic aldehyde compared with that of vehicle as a control. In conclusion, the in vivo LLNA could provide more sensitive screening test for moderate to strong sensitizers and some weak sensitizers including cosmetic raw materials than the in vitro LLNA. The production of IFN-Υ by allergen-activated LNCs might be a values indicators without radioisotopes for the identification of contact allergens. Detection of allergens by testing the increase of ICAM-1 positive cells and B cells in LNCs by flow cytometry might be used as a test method to detect allergens.

• Bulletin of the Korean Chemical Society
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• 제30권5호
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• pp.1107-1112
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• 2009

The aim of this study is to develop and synthesize $5-HT_{1A}$ receptor imaging agents with WAY-100635 moiety and $^{99m}Tc(CO)_3$ core. WAY-100635 is commonly known as $5-HT_{1A}$ antagonist and its labeled compound ([$^{11}C$] WAY-100635) has been used as effective radioligand for imaging brain $5-HT_{1A}$ receptors with PET(Positron Emission Tomography). However, there are several restrictions in using a radioisotope of C-11 and requires for more effective radioisotopes and ligands. In order to produce a structure most similar to WAY-100635, WAY-100635 derivatives containing a cysteine chelator were designed and confirmed by using in silico (Hyperchem). The novel compounds (7a, 7b, 7c) were prepared in five or 7 steps with yields of 16%, 36% and 42%, respectively and radiolabeled with $[^{99m}Tc(CO)_3(H_2O)_3]^{+}$. The labeling yield was 99% for all the newly synthesized compounds. [$^{99m}Tc(CO)_3$]- WAY-100635 derivatives show a neutral charge which were confirmed by paper electrophoresis.

• Korean Chemical Engineering Research
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• 제45권6호
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• pp.627-632
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• 2007

원자력 시설 해체시 발생되는 금속성 폐기물의 용융 제염을 위한 기초 연구를 위해 아크 용융로를 사용하여 스테인레스강과 탄소강의 금속 폐기물 용융시 슬래그 종류, 농도, 염기도에 따라 $^{60}Co$, $^{137}Cs$ 핵종의 주괴, 슬래그, 분진 상으로 분배 특성을 살펴보았다. $^{60}Co$은 90% 이상 주괴상에 균질하게 분포되었으며, 슬래그 상에는 약 10% 미만으로 잔존하며 슬래그 조성에 따라 분배특성이 크게 영향을 받지 않았으나, 유동성이 좋은 염기성 슬래그 형성제가 포함된 슬래그에서는 영향을 받음을 알 수 있었다. $^{137}Cs$는 스테인레스강과 탄소강의 용융체로부터 완전히 제거되어 슬래그상과 분진상 상으로 분배됨을 알 수 있었다.

• 치과방사선
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• 제26권2호
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• pp.165-174
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• 1996

The authors diagnosed a 33 years old female as benign lymphoepithelial lesion after undergoing clinical, radiological and histopathological examinations and the characteristics were as follows : 1. Clinically, the patient complained of painless bilateral swelling of the parotid glands and dryness of the palate. Rheumatoid factor was detected in her serum. 2. Sialograms showed punctate or globular collections of contrast media distributed evenly throughout the parotid glands in so-called 'cherry blossom' or 'leafless fruit-laden tree' appearance. 3. A salivary gland scan showed no uptake of radioisotopes by the parotid glands. 4. At Tl-weighted imaging of PNS MRI, the lesions had the same signal intensity as the rest of the gland. At TI-weighted imaging, the lesions could be seen as high signal intensity 1.3 cm and 2.1 cm in diameter in the left and the right parotid gland respectively. 5. Ultrasonogram showed sonolucent lesions 20×15mm and 17×14mm in size in the lower part of the left parotid gland and another 18×11mm in size in the lower part of the parotid gland as well as many other small sonolucent lesions. 6. Histopathologically, lymphocytic infiltration replacing the normal acini and lymphoid follicles containing germinal centers could be seen. Epimyoepithelial islands were scattered throughout the lesion and benign lymphoepithelial cysts were also observed.

• 대한핵의학회지
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• 제39권1호
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• pp.1-8
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• 2005

상용 PET사이클로트론의 기술적인 변화는 PET의 수요와 밀접한 관계가 있다. PET활용이 일반화 되어 미국을 중심으로 PET의 수요가 급증하게 됨에 따라 사이클로트론의 수요도 증가 하였다. 기존의 사이클로트론은 크기와 무게로 병원에 설치에 공간과 전원 공급 등 여러 문제가 있어 각 사이클로트론 제작사들은 새로운 모델을 출시하게 되었다. 새로운 모델의 특징은 다음과 같다. 첫째 기존의 모델이 양성자와 중양자 등의 2가지 이온을 인출 하였으나 시스템의 복잡성 등의 문제와 양성자로 O-15 생산이 가능하여 양성자 빔만을 인출 하거나 중양자는 선택 사양으로 전환 하였다. 둘째 기존 모델의 경우 양성자의 빔 에너지는 약 16 MeV 이상 가속 시킬 수 있으나 신 모델은 13 MeV 이내로 대폭 낮추어 PET 용 Rl생산에 최적화하였다. 셋째 전자석, RF 장치등의 최적화를 이룩하여 전력소모를 대폭 개선하였으며 외양도 대폭 작아져 무게를 20톤 이내로 대폭 낮추었다. 넷째 새로운 모델 사이클로트론들은 자체 차폐기능이 일반화 되었으나 IBA제품이나 삼영유니텍 제품은 사용자의 견지에 따라 선택 사양이 가능하다.

• 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.