• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 추계학술대회
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• pp.765-768
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• 2003

The objective of the present study was to visualize the pulsatile flow field in a branching model by using the high-resolution PIV system. A bifurcated flow system was built for the experiments in the pulsatile flow. Harvard pulsatile pump was used to generate the pulsatile velocity waveforms. Conifer powder as the tracing particles was added to water to visualize the flow fields. Two consecutive particle images at several cross sections of the flow filed were captured by the CCD cameras ($1K{\ast}1K$ and $640{\ast}480$). The results after the image processing clearly showed the recirculation zones and the formation of the paired secondary flows from the distal to the apex in the bifurcated model. The results also indicated that the flow velocities in the inner wall moved faster than those in the outer wall due to the inertial force effects and the helical motions generated in the branch flows as the flow proceeded toward the outer wall. While the PIV images from the $1K{\ast}1K$ camera were closer to the simulation results thantheimagesfromthe640${\ast}$480camera,bothresultsofthePIVexperimentsusingthetwocamerasgenerallyagreed quitewellwiththeresultsfromthenumericalsimulation.

• Journal of Radiation Protection and Research
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• 제48권1호
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• pp.44-51
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• 2023

Background: Aptamers are currently being used in various fields including medical treatments due to their characteristics of selectively binding to specific molecules. Due to their special characteristics, the aptamers are expected to be used to remove radionuclides from a large amount of liquid radioactive waste generated during the decommissioning of nuclear power plants. The radiological effects on the aptamers should be evaluated to ensure their integrity for the application of a radionuclide removal technique. Materials and Methods: In this study, Monte Carlo N-Particle transport code version 6 (MCNP6) and Monte Carlo damage simulation (MCDS) codes were employed to evaluate the radiological effects on the aptamers. MCNP6 was used to evaluate the secondary electron spectrum and the absorbed dose in a medium. MCDS was used to calculate the DNA damage by using the secondary electron spectrum and the absorbed dose. Binding experiments were conducted to indirectly verify the results derived by MCNP6 and MCDS calculations. Results and Discussion: Damage yields of about 5.00×10^-4 were calculated for 100 bp aptamer due to the radiation dose of 1 Gy. In experiments with radioactive materials, the results that the removal rate of the radioactive ⁶⁰Co by the aptamer is the same with the non-radioactive ⁵⁹Co prove the accuracy of the previous DNA damage calculation. Conclusion: The evaluation results suggest that only very small fraction of significant number of the aptamers will be damaged by the radioactive materials in the liquid radioactive waste.

• 한국군사과학기술학회지
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• 제20권4호
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• pp.491-496
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• 2017

The hydrogen($H_2$) is promising energy carrier of renewable energy in the microgrid system such as small village and military base due to its high energy density, pure emission and convenient transportation. $H_2$ can be generated by photocatalytic water splitting, gasification of biomass and water electrolysis driven by solar cell or wind turbine. Solid oxide electrolysis cells(SOECs) are the most efficient way to mass production due to high operating temperature improving the electrode kinetics and reducing the electrolyte resistance. The SOECs are consist of nickel-yttria stabilized zirconia(NiO-YSZ) fuel electrode / YSZ electrolyte / lanthanum strontium manganite-YSZ(LSM-YSZ) air electrode due to similarity to Solid Oxide Fuel Cells(SOFCs). The Ni-YSZ most widely used fuel electrode shows several problems at SOEC mode such as degradation of the fuel electrode because of Ni particle's redox reaction and agglomeration. Therefore Ni-YSZ need to be replaced to an alternative fuel electrode material. In this study, We studied on the Double perovskite $PrBrMnO_{5+{\delta}}$(PBMO) due to its high electric conductivity, catalytic activity and electrochemical stability. PBMO was impregnated into the scaffold electrolyte $La_{0.8}Sr_{0.2}Ga_{0.85}Mg_{0.15}O_{3-{\delta}}$(LSGM) to be synthesized at low temperature for avoiding secondary phase generated when it exposed to high temperature. The Half cell test was conducted at SOECs and SOFCs modes.

• 한국농공학회논문집
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• 제64권3호
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• pp.25-32
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• 2022

To understand the distribution characteristics of PM_2.5 concentration in the Saemangeum Reclamation Area and nearby areas, three points of the background area, the occurrence area, and the affected area were selected and samples were collected for each season. The chemical composition was determined. As a result of analyzing the chemical composition contained in PM_2.5, NO₃^- (7.2 ㎍/m³), SO₄^2- (4.3 ㎍/m³), NH₄+ (4.3 ㎍/m³), OC (2.5 ㎍/m³), Si (1.3 ㎍/m³) m³) and EC (0.5 ㎍/m³) seemed to be the main components, and NO₃-, SO₄^2-, NH₄⁺, which are components that form secondary particles, occupied a large proportion. The composition ratio of PM_2.5 was investigated in the order of ion component (56.8%) > Unknown (27.4%) > carbon component (11.8%) > heavy metal component (4.0%). During the PM_2.5 high concentration case days, the ionic component accounted for 90.7% during atmospheric stagnation cases, whereas the chemical composition ratio was in the order of ionic component (51.7%) > heavy metal component (41.5%) > carbon component (6.8%) during yellow dust cases. It was found that the characteristic of PM_2.5 in the Saemangeum reclaimed land and surrounding areas is mainly influenced by outside (domestic and overseas) throughout the year. Ion components accounted for the largest portion of PM_2.5 components in this area, but there were few sources of SOx and NOx emission in the Seamangeum area, which are precursors for secondary particle formation. Therefore, it is judged that most of these are generated and influenced as a secondary reaction in the atmosphere from the outside.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2009년도 제38회 동계학술대회 초록집
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• pp.101-101
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• 2010

ZnO shows a direct band gap of 3.37eV, large exciton binding energy (~60 meV), high oxidation ability, high sensitivity to many gases, and low cost, and it has been used in various applications such as transparent electrodes, light emitting diodes (LEDs), gas sensors and photocatalysts. Among these applications ZnO as photocatalyst has considerably attracted attention over the past few years because of its high activities in removing organic contaminants generated from industrial activities. In this research, ZnO nanoparticles were synthesized by spray-pyrolysis method using the zinc acetate dihydrate as starting material at synthesis temperature of $900^{\circ}C$ with concentration varied from 0.01 to 1.0M. The physical and chemical properties of the synthesized ZnO nanoparticles were examined by X-ray Diffraction (XRD), Scanning Electron Microscopy (SEM), Fourier Transformation Infrared (FT-IR), and UV-vis spectroscopy. The Miller indices of XRD patterns indicate that the synthesized ZnO nanoparticles showed a hexagonal wurtzite structure. With increased precursor concentration, a primary, secondary particle sizes of ZnO nanoparticles increased by 0.8 to $1.5{\mu}m$ and 15 to 35nm, and their crystallinity was improved. Methyleneblue (MB) solution ($1{\mu}M$) as a test comtaminant was prepared for evaluating the photocatalytic activities of ZnO nanoparticles synthesized in different precursor concentration. The results show that the photocatalytic efficiency of ZnO nanoparticles was gradually enhanced by increased precursor concentration.

• 한국환경과학회지
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• 제19권11호
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• pp.1423-1436
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• 2010

The effects of meteorological and reclaiming conditions on the reduction of suspended particles are investigated using a computational fluid dynamics (CFD) model with the k-$\varepsilon$ turbulence closure scheme based on the renormalization group (RNG) theory. Twelve numerical experiments with different meteorological and reclaiming conditions are performed. For identifying the meteorological characteristics of the target area and providing the inflow conditions of the CFD model, the observed data from the automatic weather station (AWS) near the target area is analyzed. Complicated flow patterns such as flow distortion, horse-shoe vortex, recirculation zone, and channeling flow appeared due to the topography and buildings in the domain. Specially, the flow characteristics around the reclamation area are affected by the reclaiming height, reclaiming size and windbreak height. Reclaiming height affected the wind speed above the reclaiming area. Windbreak induces more complicated flow patterns around the reclaiming area as well as within the reclaiming area. In front of the windbreak, flow is distorted as it impinges on the windbreak. As a result, upward flow is generated there. Behind the windbreak, a secondary circulation, so called, a recirculation zone is generated and flow is reattached at the end of the recirculation zone (reattachment point). At the lower part of the recirculation zone, there is a reverse flow toward the windbreak. Flow passing to the reattachment point starts to be recovered. Total amounts of suspended particles are calculated using the frictional and threshold frictional velocities, erosion potential function, and the number of surface disturbance. In the case of a 10 m-reclaiming and northerly wind, the amount of suspended particles is largest. In the presence of 5 m windbreak, the friction velocity above the reclaiming area is largely reduced. As a result, the total amount of the suspended particles largely decreases, compared to the case with the same reclaiming and meteorological conditions except for the windbreak The calculated suspended particle amounts are used as the emission rate of the dispersion model simulations and the dispersion characteristics of the suspended particles are analyzed.

• 자원리싸이클링
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• 제32권1호
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• pp.50-59
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• 2023

전기로에서 고철(Scrap)의 용해과정에서 발생되는 분진량은 고철장입량의 약1.5%정도이며, 주로 백필터(Bag Filter)에서 포집된다. 전기로 제강분진의 주요한 구성원소인 아연(Zn)과 철(Fe)중에서 아연성분은, 제강분진에 탄소계의 환원재(코크스, 무연탄)와 석회석(C/S제어)을 첨가하여 Pellet형태로 가공한 후에 반응로(Rotary Kiln 또는 RHF)에 장입하여 환원, 휘발, 재산화의 단계적인 세부반응을 거쳐서, 60wt%Zn을 함유한 조산화아연(Crude Zinc Oxide)으로 회수된다. 한편 제강분진 중의 철(Fe)성분은, Fe-Base의 Clinker(2차부산물)라고 하는 고형물의 형태로 반응기로부터 배출된다. 기존의 Fe-Clinker의 처리방법은, 각국의 상황에 따라서 다양한 방안들이 시행되고 있는데, 대표적인 처리방법으로는 매립, 재활용(로반재, 콘크리트용 골재, 시멘트제조용 Fe-Source), 그 외에 다양한 처리방법들이 있다. 이들 방법들 중에서 매립의 경우는, 침출수에 의한 환경오염, 고가의 매립비용, Fe자원의 낭비 등의 이유로, 결코 바람직한 처리방법이라고 할 수는 없다. 그러나 Fe-Clinker중의 Fe성분을 전기로를 이용하여 직접적으로 재활용하는 방법에 대한 연구결과는 거의 찾아볼 수 없었다. 따라서 본 연구에서는 Fe-Clinker중의 Fe성분을 보다 적극적으로 회수하기 위한 방법으로서, 먼저 Fe-Clinker를 분쇄하고 이어서 비중선별과 자력선별을 순차적으로 실시하여, Fe-성분이 농축된 조분(Coarse particle, >약10㎛)과 슬래그성분을 주로 함유한 미분(Fine particle, <약10㎛)으로 분리하였다. 이렇게 분리한 조분에 탄소계 환원제(코크스, 무연탄)와 점결재(전분)를 첨가하여 단광 Clinker를 제조하여, 전기로에 고철을 장입할 때에 소량(1~3wt%)의 단광Clinker를 함께 장입하여, 단광Clinker의 첨가재(가탄재, Fe-Source, 발열재 등으로서의 역할)로서의 사용가능성을 조사하였다. 그 결과, 비록 소량이지만, 전력원단위와 생산수율이 다소 향상되는 효과를 나타내었으며, 용융금속에 대한 가탄효과도 확인할 수 있었다.

• Geomechanics and Engineering
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• 제15권5호
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• pp.1113-1124
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• 2018

Geological dynamic hazards during deep coal mining are caused by the failure of a composite system consisting of the rock and coal layers, whereas the joint in coal affects the stability of the composite system. In this paper, the compression test simulations for the rock-coal combined body with single joint in coal were conducted using $PFC^{2D}$ software and especially the effects of joint length and joint angle on strength and failure characteristics in a rock-coal combined body were analyzed. The joint length and joint angle exhibit a deterioration effect on the strength and affect the failure modes. The deterioration effect of joint length of L on the strength can be neglected with a tiny variation at ${\alpha}$ of $0^{\circ}$ or $90^{\circ}$ between the loading direction and joint direction. While, the deterioration effect of L on strength are relatively large at ${\alpha}$ between $30^{\circ}$ and $60^{\circ}$. And the peak stress and peak strain decrease with the increase of L. Additionally, the deterioration effect of ${\alpha}$ on the strength becomes larger with the increase of L. With the increase of ${\alpha}$, the peak stress and peak strain first decrease and then increase, presenting "V-shaped" curves. And the peak stress and peak strain at ${\alpha}$ of $45^{\circ}$ are the smallest. Moreover, the failure mainly occurs within the coal and no apparent failure is observed for rock. At ${\alpha}$ between $30^{\circ}$ and $60^{\circ}$, the secondary shear cracks generated in or close to the joint tips, cause the structural instability failure of the combined body. Therefore, their failure models present as a shear failure along partial joint plane direction and partially cutting across the coal body or a shear failure along the joint plane direction. However, at ${\alpha}$ of $60^{\circ}$ and L of 10 mm, the "V-shaped" shear cracks cutting across the coal body cause its final failure. While crack nucleations at ${\alpha}$ of $0^{\circ}$ or $90^{\circ}$ are randomly distributed in the coal, the failure mode shows a V-shaped shear failure cutting across the coal body.

• Journal of Radiation Protection and Research
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• 제45권3호
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• pp.130-141
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• 2020

Background: Concrete activation in cyclotron vaults is a major concern associated with their decommissioning because a considerable amount of activated concrete is generated by secondary neutrons during the operation of cyclotrons. Reducing the amount of activated concrete is important because of the high cost associated with radioactive waste management. This study aims to investigate the capability of the neutron absorbing materials to reduce concrete activation. Materials and Methods: The Particle and Heavy Ion Transport code System (PHITS) code was used to simulate a cyclotron target and room. The dimensions of the room were 457 cm (length), 470 cm (width), and 320 cm (height). Gd₂O₃, B₄C, polyethylene (PE), and borated (5 wt% ^natB) PE with thicknesses of 5, 10, and 15 cm and their different combinations were selected as neutron absorbing materials. They were placed on the concrete walls to determine their effects on thermal neutrons. Thin B₄C and Gd₂O₃ were placed between the concrete wall and additional PE shield separately to decrease the required thickness of the additional shield, and the thermal neutron flux at certain depths inside the concrete was calculated for each condition. Subsequently, the optimum combination was determined with respect to radioactive waste reduction, price, and availability, and the total reduced radioactive concrete waste was estimated. Results and Discussion: In the specific conditions considered in this study, the front wall with respect to the proton beam contained radioactive waste with a depth of up to 64 cm without any additional shield. A single layer of additional shield was inefficient because a thick shield was required. Two-layer combinations comprising 0.1- or 0.4-cm-thick B₄C or Gd₂O₃ behind 10 cm-thick PE were studied to verify whether the appropriate thickness of the additional shield could be maintained. The number of transmitted thermal neutrons reduced to 30% in case of 0.1 cm-thick Gd₂O₃+10 cm-thick PE or 0.1 cm-thick B₄C+10 cm-thick PE. Thus, the thickness of the radioactive waste in the front wall was reduced from 64 to 48 cm. Conclusion: Based on price and availability, the combination of the 10 cm-thick PE+0.1 cmthick B₄C was reasonable and could effectively reduce the number of thermal neutrons. The amount of radioactive concrete waste was reduced by factor of two when considering whole concrete walls of the PET cyclotron vault.

• Journal of Radiation Protection and Research
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• 제39권4호
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• pp.199-205
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• 2014

중성자 검출분야에서$^3He$는 높은 중성자 검출효율 때문에 아주 많이 사용되고 있다. 하지만 2009년 초반부터 발생하고 있는 전세계적인 $^3He$의 품귀현상으로 인하여 가격이 급등하고 수급이 어려워졌기 때문에 대체 중성자 검출물질에 대한 필요성이 높아졌다. 그러므로 중성자 검출물질로 사용될 수는 있지만 $^3He$에 비해 반응효율이 낮아 중성자 검출용으로 주로 사용되지 않던 물질들을 사용하여 검출기를 제작하는 연구가 다시 활발하게 진행되고 있다. $BF_3$, $^6Li$, $^{10}B$, $Gd_2O_2S$ 등과 같은 $^3He$ 대체 물질들 중 하나인 $^{10}B$은 손쉬운 감마선 구별, 무독성, 낮은 가격 등과 같은 여러 장점으로 인하여 여러 연구그룹에서 연구되고 있다. $^{10}B$ 박막을 이용한 중성자 검출은 중성자와 반응하여 발생되는 2차 방사선을 측정하여 간접적으로 중성자를 측정하는 검출기법이다. 반응을 통해 생성된 알파입자의 비정은 고체 내에서 아주 짧기 때문에 $^{10}B$ 층은 박막 형태로 얇게 제작해야 한다. 그러므로 중성자와 박막의 반응을 통해 발생되는 알파입자의 검출효율을 증가시키기 위해서는 $^{10}B$ 박막의 두께를 얇게 제작하는 것이 중요하다. 하지만 박막의 두께를 얇게 제작하는 것은 중성자와 반응하여 생성되는 알파입자의 수집효율을 증가시키는 장점이 있지만 또한 중성자와 반응할 단면적을 감소시키는 단점이 있다. 본 논문에서는 리튬이온전지에 사용되는 초박막 극판 제조 기술을 이용하여 중성자 검출을 위한 대략 $60{\mu}m$ 두께의 얇은 $^{10}B$ 박막을 제작하였다. 그리고 전도성, 분포, 점착력, 유연성와 같은 간단한 물리적 실험을 통해 제작된 $^{10}B$ 박막의 물성을 확인하였다. 또한, 제작된 $^{10}B$ 박막을 사용하여 중성자 모니터링을 위한 비례계수기 제작하고 이를 이용하여 한국원자력연구원의 중성자 조사시설의 중성자 파고 스펙트럼을 측정하였다. 또한, 중성자 검출효율을 증가시킬 수 있는 방법 중 하나인 다층 박막을 이용한 중성자 측정 방법을 이용하여 박막 층수에 따른 중성자 검출효율의 변화를 몬테칼로 전산모사 기법을 이용하여 계산하였고 실험을 통해 박막층의 증가에 따른 신호변화를 측정하였다.