• 한국산업보건학회지
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• 제31권4호
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• pp.342-352
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• 2021

Objectives: This study analyzed the local exposure levels of radiation emitted from the equipment with soft X-ray ionizers to investigate the radiation exposure levels in Liquid Crystal Display(LCD) manufacturing processes. Methods: This study measured the local radiation levels for the equipment installed in two LCD manufacturing companies. The equipment were installed at diverse processes and equipped with various number of ionizers. The local radiation levels were measured on the surface of the equipment by using direct reading equipment, and the measurements were converted into annual effective dose by considering the radiation exposure time of workers. Statistical analyses were performed to investigate the radiation exposure characteristics. Results: Annual effective doses for 97.6% of the equipment being measured were less than 1 mSv. However, the range of annual effective doses was 0.004 mSv ~ 2.167 mSv, which indicated a large variation among the equipment. Statistical analyses of the study found that this large variation was raised due to improper shielding of the equipment rather than process and/or equipment characteristics. To pinpoint the cause of this large variation in annual effective dose, this study improved the shielding of the equipment being radiated over 1 mSv and found that their average effective dose was reduced from 1.604 mSv to 0.126 mSv after shielding improvement. Conclusions: Relatively high exposure levels of radiation were observed in some equipment where their shielding were insufficiently thick and/or sealed. This finding implies that the shielding of the equipment is an important engineering countermeasure to control the radiation exposure levels in industries.

• 한국건축시공학회지
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• 제20권2호
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• pp.129-135
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• 2020

핵 및 방사능전 상황에서 방사선에 의한 인명피해를 줄이기 위한 방안으로서 유개호에 자철석이 포함된 중량 콘크리트의 적용 가능성을 확인해보았다. 이에 본 연구에서는 자철광 콘크리트의 방사선 차폐효과를 분석하기 위하여 감마선원을 사용하여 차폐실험을 진행하였고 실험조건과 동일한 몬테칼로 모델링도 하였다. 그 결과 자철광의 함량이 증가할수록 감마선에 대한 차폐효과가 향상됨을 확인할 수 있었다. 향후 자철광 콘크리트가 군사적 목적의 시설물에 적용될 경우 방사선 차폐 측면에서 효과를 얻을 수 있을 것이라 기대한다.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1519-1526
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• 2023

For the first time Aluminium-BariumeZinc oxide nanocomposite (ZABONC) was synthesized by solution combustion method where calcination was carried out at low temperatures (600℃) to study the electromagnetic (EM) (X/γ) radiation shielding properties. Further for characterization purpose standard techniques like PXRD, SEM, UV-VISIBLE, FTIR were used to find phase purity, functional groups, surface morphology, and to do structural analysis and energy band gap determination. The PXRD pattern shows (hkl) planes corresponding to spinel cubic phase of ZnAl₂O4, cubic Ba(NO₃)₂, α and γ phase of Al₂O₃ which clearly confirms the formation of complex nano composite. From SEM histogram mean size of nano particles was calculated and is in the order of 17 nm. Wood and Tauc's relation direct energy band gap calculation gives energy gap of 2.9 eV. In addition, EM (X/γ) shielding properties were measured and compared with the theoretical ones using standard procedures (NaI (Tl) detector and multi channel analyzer MCA). For energy above 356 keV the measured shielding parameters agree well with the theory, while below this value slight deviation is observed, due to the influence of atomic/crystallite size of the ZABONC. Hence synthesized ZABONC can be used as a shielding material in EM (X/γ) radiation shielding.

• Nuclear Engineering and Technology
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• 제55권9호
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• pp.3268-3276
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• 2023

The practice of identifying the potential zones for mineral exploration in a speedy and low-cost method includes the use of satellite imagery analysis as a part of remote sensing techniques. It is challenging to explore the iron mineralization of a region through conventional methods which are a time-consuming process. The current study utilizes the Hyperion satellite imagery for mapping the iron mineralization and associated geological features in the Irikkur region, Kannur, Kerala. Along with the remote sensing results, the field study and laboratory-based analysis were conducted to retrieve the ground truth point and geochemical proportion to verify the iron ore mineralization. The MC simulation showed for shielding properties indicate an increase in the linear attenuation coefficient with raising the Fe₂O₃+SiO₂ concentrations in the investigated rocks where it is varied at 0.662 MeV in the range 0.190 cm^-1 - 0.222 cm^-1 with rising the Fe₂O₃+SiO₂ content from 57.86 wt% to 71.15 wt%. The analysis also revealed that when the γ-ray energy increased from 0.221 MeV to 2.506 MeV, sample 1 had the largest linear attenuation coefficient, ranging from 9.33 cm1 to 0.12 cm^-1. Charnockite rocks were found to have exceptional shielding qualities, making them an excellent natural choice for radiation shielding applications.

• 문화기술의 융합
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• 제10권3호
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• pp.819-825
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• 2024

진단용방사선발생장치를 사용함에 있어서 선량데이터를 기록하는 이유는 의료진 및 환자의 피폭선량을 기록하고 관리하기 위함이다. 진단용방사선발생장치를 사용함에 있어서 방사선량의 차이를 검증하고 위험성과 차폐체 착용의 유무의 상황에서 피폭선량에 대한 측정과 분석을 통해 사용자의 피폭선량 경감에 대한 인식을 알리고자 하였다. 에스레이튜브와 II튜브에 따라 구분하여 장비를 한국 C-arm 2대, 독일 C-arm 2대장비를 대상으로 각 장비별 선량분석결과 한국 FPD type C-arm 이 가장 높은 선량값이 측정되었고, 독일 I.I type C-arm, 독일 FPD type C-arm, 한국, I.I type C-arm 순서로 피폭선량값이 측정되었다. 차폐체 유무에 따른 피폭선량 분석결과 일반적인 대기상태에 인체팬텀을 놓고 측정결과 산란선에 의해 피폭선량이 약 2배 증가하였으나 차폐체(0.5mm/납앞치마)를 착용하니 약 5배의 피폭선량 감소하는 결과가 나타났다. 피폭선량과 차폐체를 통해 피폭선량의 관리가 중요한 역할을 하며 방사선 피폭을 줄이는 방법을 유추할 수 있다. 또한, 장비마다 출력되는 피폭선량이 다른 특성을 갖고 있음으로 차폐체를 유무를 선별하는데 선량정보로 제공을 할 것으로 기대 한다.

• 한국수소및신에너지학회논문집
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• 제30권6호
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• pp.540-548
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• 2019

This study was conducted to develop insulation for solid oxide fuel cell (SOFC). The developed insulation is based on the lamination technology and the radiation shielding technology of the satellite insulation. The insulation material is consisting of insulation material for conduction resistance, spacer, and radiation shielding material. The experimental apparatus consisting vacuum bell jar, pump, heater and temperature recording device has developed to verify the performance of the insulation. The experimental values were used as reference data for the modeling development. In this paper, heat transfer is assumed to be one- dimensional phenomena for the prediction of insulation performance and internal temperature distribution in high temperature region of SOFC. The developed model was used to compare the performance difference of insulation types according to composition materials. The analysis result shows that the insulation including spacer and radiation shielding has better heat insulation performance than other cases. In this study, the thickness reduction effect of about 20% was shown compared to the insulation including only conductive material. It is noted that the radiant shielding material should be carefully selected for durability, because SOFC insulation should be used for a long time at high temperature.

• 한국방사선학회논문지
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• 제7권6호
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• pp.403-408
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• 2013

본 연구에서는 기존의 납을 대체할 수 있는 의료 방사선 차폐제품 적용을 위해 몬테카를로 시뮬레이션을 통해 바륨화합물의 두께별 차폐능을 모의 추정하였다. 차폐재 물질로는 황산바륨($BaSO_4$)을 이용하였고, 시편의 면적은 $15{\times}15cm^2$, 황산바륨의 밀도는 $4.5g/cm^3$, 납의 밀도 $11.34g/cm^3$를 적용하여 차폐재 시편의 두께를 0.1 mm부터 5 mm까지 시뮬레이션 하였다. 입력 선원은 연속 X-ray 에너지 스펙트럼(40 kVp ~ 120 kVp)에서 10kVp Step으로 시뮬레이션하였다. 40 kVp ~ 60 kVp에서의 흡수확률은 3 mm ~ 5 mm 두께에서는 납과 동일한 차폐능을 나타내었으나, 2 mm 이하에서는 차폐능이 기존 납 차폐재에 비해 다소 차폐능이 떨어지는 결과로 나타났다. 또한 70 kVp ~ 120 kVp 에너지 대역에서의 차폐능은 기존 납 차폐재와 유사한 성능을 보였지만, 0.5 mm 이하에서는 다소 낮은 차폐능으로 모의 추정되었다. 본 연구는 몬테카를로 시뮬레이션을 통해 의료용 엑스선 에너지 대역에 대한 두께 함수로써 바륨화합물의 차폐능을 추정하여 기존의 납과 비교 분석하였다. 또한 순수한 황산바륨의 의료용 방사선 차폐제품 적용가능성을 검증하고자 하였다. 그 결과 의료 방사선 에너지 대역 70 kVp ~ 120 kVp 에서 최소 2 mm 이상의 바륨화합물 두께에서 기존 납 1.5 mm 대비 95% 이상의 차폐효과가 있는 것으로 추정되었으며, 본 결과는 의료용 방사선 차폐제품의 경량화 제작에 기초 자료로 제공될 수 있을 것으로 사료된다.

• Nuclear Engineering and Technology
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• 제52권9호
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• pp.2078-2084
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• 2020

Magnesium oxide (MgO) and Zinc oxide (ZnO) nanoparticles (NPs) have been successfully synthesized by solid-solid reaction method. The structural properties of ZnO and MgO NPs were studied using X-ray diffraction (XRD) and scanning electron microscopy (SEM). XRD results indicated a formation of pure MgO and ZnO NPs. The mean diameter values of the agglomerated particles were around to be 70 and 50 nm for MgO and ZnO NPs, respectively using SEM analysis. Further, a wide-range of nuclear radiation shielding investigation for gamma-ray and fast neutrons have been studied for Magnesium oxide (MgO) and Zinc oxide (ZnO) samples. FLUKA and Microshield codes have been employed for the determination of mass attenuation coefficients (μ_m) and transmission factors (TF) of Magnesium oxide (MgO) and Zinc oxide (ZnO) samples. The calculated values for mass attenuation coefficients (μ_m) were utilized to determine other vital shielding properties against gamma-ray radiation. Moreover, the results showed that Zinc oxide (ZnO) nanoparticles with the lowest diameter value as 50 nm had a satisfactory capacity in nuclear radiation shielding.

• 방사성폐기물학회지
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• 제20권3호
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• pp.349-356
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• 2022

Nuclear power plant decommissioning generates significant concrete waste, which is slightly contaminated, and expected to be classified as clearance concrete waste. Clearance concrete waste is generally crushed into rubble at the site or a satellite treatment facility for practical disposal purposes. During the process, workers are exposed to radiation from the nuclides in concrete waste. The treatment processes consist of concrete cutting/crushing, transportation, and loading/unloading. Workers' radiation exposure during the process was systematically studied. A shielding package comprising a cylindrical and hexahedron structure was considered to reduce workers' radiation exposure, and improved the treatment process's efficiency. The shielding package's effect on workers' radiation exposure during the cutting and crushing process was also studied. The calculated annual radiation exposure of concrete treatment workers was below 1 mSv, which is the annual radiation exposure limit for members of the public. It was also found that workers involved in cutting and crushing were exposed the most.

• Journal of Radiation Protection and Research
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• 제32권4호
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• pp.190-193
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• 2007

The objective of this study is to recommend the radiation protection design parameters from the shielding point of view for concrete wall between the decay tank room and the primary pump room in TRIGA Mark-II Research Reactor Facility. The shield design for this concrete wall has been performed with the help of Point-kernel Shielding Code Micro-Shield 5.05 and this design was also validated based on the measured dose rate values with Radiation Survey Meter (G-M Counter) considering the ICRP-60 (1990) recommendations for occupational dose rate limit ($10{\mu}Sv/hr$). The recommended shield design parameters are: (i) thickness of 114.3 cm Ilmenite-Magnetite Concrete (IMC) or 129.54 cm Ordinary Reinforced Concrete (ORC) for concrete wall A (ii) thickness of 66.04 cm Ilmenite-Magnetite Concrete (IMC) or 78.74 cm Ordinary Reinforced Concrete (ORC) for concrete wall B and (iii) door thickness of 3.175 cm Mild Steel (MS) on the entrance of decay tank room. In shielding efficiency analysis, the use of I-M concrete in the design of this concrete wall shows that it reduced the dose rate by a factor of at least 3.52 times approximately compared to ordinary reinforced concrete.