• Journal of Radiation Industry
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• v.7 no.2_3
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• pp.201-207
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• 2013

Soil liquefaction by tsunami or wave induced currents can cause serious damages to coastlines and coastal infrastructures. Although liquefaction caused by regular waves over sea beds has been extensively investigated, studies of tsunami-induced liquefaction near coastal area have been relatively rare. In this work, the hydraulic scale model has been designed and constructed to investigate the variations of wave height and sediment transport by tsunami. The distorted hydraulic scale model based on the Froude similarity was adopted to represent hydrodynamics and sediment transport in a coastal area. The scale model was composed of control box, screw axis, wave paddle and rotating coastal structure.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.1
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• pp.95-106
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• 2019

The decommissioning of nuclear power plants should be prepared by quantitative and qualitative risk assessment. Radiological and non-radiological hazards arising during decommissioning activities must be assessed to ensure the safety of decommissioning workers and the public. Decommissioning experiences by U.S. operators have mainly focused on deterministic risk assessment, which is standardized by the U.S. Nuclear Regulatory commission (NRC) and focuses only on the consequences of risk. However, the International Atomic Energy Agency (IAEA) has suggested an alternative to the deterministic approach, called the risk matrix technique. The risk matrix technique considers both the consequence and likelihood of risk. In this study, decommissioning stages, processes, and activities are organized under a work breakdown structure. Potential accidents in the decommissioning process of NPPs are analyzed using the composite risk matrix to assess both radiological and non-radiological hazards. The levels of risk for all potential accidents considered by U.S. NPP operators who have performed decommissioning were estimated based on their consequences and likelihood of events.

• Nuclear industry
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• v.16 no.8 s.162
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• pp.38-44
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• 1996

과학기술처는 지난 7월 기존의 $\lrcorner$원자력 관계 보고 규정$\lrcorner$을 첨삭$\cdot$보완하여 $\ulcorner$원자력 시설의 사고$\cdot$고장 발생시 보고에 관한 규정$\lrcorner$을 새로이 제정했다. 이는 그동안 원자력법령에 의하여 원자력 관계 사업자가 보고해야 할 사항이 원자력법, 원자력발전소 운영기술지침서, 방사선 비상계획서, 계량관리 및 방호규정 등에 산재되어 있어, 사업자나 규제기관 모두 혼란이 있어온 점을 해결한 것으로, 보고 대상과 보고 방법 등을 세분화하였으며, 또한 사업자에게 불합리하게 적용되는 일부 사항들을 발굴$\cdot$정리하였다.

• Journal of the Korean Society of Radiology
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• v.16 no.7
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• pp.815-824
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• 2022

The current radiation safety management system is also applied to radiation practices at universities. The application of the law raised concerns about poor radiation practice education and hindering the development of radiology. Accordingly, the Korean Radiology Professors Association needed to grasp the reality of the management system for radiation practice education at each university and the current radiation safety management system in the department of Radiological science. So, a survey was conducted on heads of radiological science departments across the country. Through the survey, it was found that the current application of the Nuclear Safety Act to radiation safety management in the department of Radiological science is excessively restrictive and not very effective. In addition, radiology practice education for the purpose of training health and medical professionals should be controlled by the Ministry of Health and Welfare and the Korea Centers for Disease Control, but there is a problem of being supervised by the Nuclear Safety and Security Commission. Therefore, in this study, as a legal improvement plan to solve this problem, first, a plan according to a partial amendment to the Higher Education Act, second, a plan to be supervised by the Ministry of Health and Welfare through the amendment of article 37 of the Medical Service Act, third, article 20-2 of the Enforcement Decree of the Medical Service Technologists Act was newly inserted to propose three measures to be supervised by the Ministry of Health and Welfare.

• Journal of Radiation Industry
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• v.18 no.3
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• pp.227-233
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• 2024

Polyolefins (PO) are used in various industrial fields due to their excellent mechanical properties, processability, and chemical resistance. However, they have low flame retardancy, and when exposed to high temperatures, there are problem that mechanical properties deteriorate due to oxidation. In this study, we developed PO/metal hydroxide composites that exhibit excellent mechanical strength, heat resistance, and flame retardancy by using antioxidants and radiation crosslinking technology. To improve mechanical strength, heat resistance, and flame retardancy, PO/metal hydroxide/antioxidant composites were prepared and irradiated with an electron beam. Specifically, at temperatures above 200℃, the PO/metal hydroxide composites with primary and secondary antioxidants added and irradiated with a 100 kGy electron beam exhibited excellent thermal stability with a thermal shrinkage rate of less than 3%. In addition, the flame retardancy of the PO/metal hydroxide/antioxidant composites was improved due to enhanced thermal stability from electron beam irradiation and reduced thermal decomposition rate from the antioxidants. These results indicate that radiation crosslinking and antioxidants are effective method to simultaneously achieve mechanical properties, heat resistance, and flame retardancy.

• Analytical Science and Technology
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• v.21 no.5
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• pp.403-411
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• 2008

Dimethyldibutyltetradecylmalonamide (DMDBTDMA) extractant was used in a solvent extraction process for a radioactive liquid waste treatment. For the study of radiolysis phenomena, DMDBTDMA was synthesized and the degradation compounds (n-methylbutylamine, tetradecane, 1-tetradecanol) in the DMDBTDMA extractant, irradiated with $^{60}Co$ gamma ray, were identified and determined as radiolysis products by a Fourier transform infrared (FT-IR), gas chromatograph/mass spectrometer (GC/MS) analysis and GC/MS with selected ion monitoring (SIM) mode. Retention behavior of n-methylbutylamine, n-dodecane, tetradecane and 1-tetradecanol in the total ion chromatogram with the standard materials and n-dodecane as the internal standard (ISTD) were 2.35 min., 8.83 min., 10.68 min. and 12.75 min., respectively. In the case of tetradecane, there was a linear relationship between the concentration of the tetradecane and the absorbed dose of the ${\gamma}$-ray irradiated DMDBTDMA.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.899-905
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• 1995

포항방사광가속기(Pohang Llght Sousrc)의 시운전기간동안 저장링건물에서의 방사선발생량을 측정하였다. Ionization Chamber와 Moderated BF$_3$ Counter로 구성된 지역방사선감시기시스템(RMS)외에 Pocket Inonization chamber, 연속기록이 가능한 Surveymeter를 고정 또는 이동시키면서 사용하였다. 시운전기간동안 선형가속기로부터의 입사시기와 저장시기에서의 방사선방출분포 및 선량의 정도가 명확히 구별되었으며 RF Cavity나 Bump Magnet등의 오동작에 의한 방사선 발생경로를 추정해 볼 수 있었다 여기서는 저장링실험지역 등에서의 공간선량분포와 부분차폐에 따른 변화를 측정하였으며 측정결과로부터 차폐계산시 사용된 방법을 통해 역으로 각 지역의 빔손실정도를 추정하고 계산식의 타당성을 검토해 보았다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.115-120
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• 1997

영광3호기 방사선관리구역에 대한 중성자선량률을 정확히 평가하기 위하여 MCNP4A 전산코드를 이용, 방사선관리구역에서의 중성자 스펙트럼 계산을 수행하였다. 영광3호기에 대한 보다 정확하고 정밀한 3차원 몬테칼로 모델을 구축하기 위하여 핵연료집합체 구성요소 및 원자로심을 둘러싸고 있는 baffle, barrel,압력용기 등을 정확하게 묘사하였으며, 특히 방사선관리구역 주위의 구조물에 대해서도 3자원 MCNP 모델을 구축함으로써 원자로심부터 방사선관리구역까지 완전한 몬테칼로 모사(full-scope Monte Carlo simulation)를 이용한 계산을 수행하였다. 계산결과는 에너지 구간에 따른 중성자속 스펙트럼으로 나타내었으며 이 결과를 바탕으로 중성자속에 대한 선량률 환산인자를 고려하여 중성자선량률을 계산할 수 있다.

• Nuclear Engineering and Technology
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• v.10 no.2
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• pp.93-107
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• 1978

• Journal of Radiation Industry
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• v.10 no.4
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• pp.189-192
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• 2016

$^{68}Ga$ has emerged as a promising candidate for non-invasive diagnostic imaging within Positron Emission Tomography (PET) because of its advantageous radiochemical characteristics ($t_{1/2}=68min$, ${\beta}^+$ yield ~89%). $^{68}Ga$ forms a stable chelation with various ligands and it is possible to be quickly and easily study using a $^{68}Ge/^{68}Ga$ generator. Commercial $^{68}Ge/^{68}Ga$ generators are chromatographic system using the inorganic materials such as alumina and tin dioxide which are employed as column matrixes for $^{68}Ge$. In this study, we tried out to make $^{68}Ge/^{68}Ga$ generator system with the $^{68}GeO_2$ microstructures for column matrix. $^{68}Ge$ tends to have stable bond with oxide as $^{68}GeO_2$ microstructures. The $^{68}GeO_2$ has been synthesized by hydrolysis of $GeCl_4$ (sol-gel method) and characterized by X-ray diffraction and scanning electron microscope for geometrical analysis. The stability of $GeO_2$ was tested using eluents with diverse solvents(water, ethanol and 0.1 N HCl). The radioactivity of $^{68}Ga^{3+}$ in eluate through $GeO_2$ was measured to prove a function as column material for a generator.