• 한국분말재료학회지
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• 제30권5호
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• pp.402-408
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• 2023

This study focused on improving the phase stability and mechanical properties of yttria-stabilized zirconia (YSZ), commonly utilized in gas turbine engine thermal barrier coatings, by incorporating Gd₂O₃, Er₂O₃, and TiO₂. The addition of 3-valent rare earth elements to YSZ can reduce thermal conductivity and enhance phase stability while adding the 4-valent element TiO₂ can improve phase stability and mechanical properties. Sintered specimens were prepared with hot-press equipment. Phase analysis was conducted with X-ray diffraction (XRD), and mechanical properties were assessed with Vickers hardness equipment. The research results revealed that, except for Z10YGE10T, most compositions predominantly exhibited the t-phase. Increasing the content of 3-valent rare earth oxides resulted in a decrease in the monoclinic phase and an increase in the tetragonal phase. In addition, the t(400) angle decreased while the t(004) angle increased. The addition of 10 mol% of 3-valent rare-earth oxides discarded the t-phase and led to the complete development of the c-phase. Adding 10 mol% TiO₂ increased hardness than YSZ.

• Korean Chemical Engineering Research
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• 제47권2호
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• pp.150-156
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• 2009

플라즈마 디스플레이 패널(Plasma Display Panel; PDP)이 Liquid Crystal Display(LCD) 등 다른 대형 평면 디스플레이 분야와 경쟁하기 위해선 제품의 다양성과 발광 효율의 향상, 저가격화, 고화질화 등의 기술 발전이 요구된다. 본 논문에서는 우선 기존 PDP용 녹색 형광체의 특성과 문제점, 이를 해결하기 위한 방법에 대해 개괄적으로 논의한다. 또한, 제품의 다양성을 위해 개발 진행 중인 3D-PDP의 원리와 이의 실현을 위한 형광체의 요구 특성에 대해 기술한다. 대표적인 PDP용 녹색 형광체인 $Zn_2SiO_4:Mn$ 형광체가 가진 문제점은 표면의 높은 음전하와 상대적으로 긴 잔광 시간으로 요약된다. 표면의 높은 음전하와 플라즈마의 가혹한 환경에 노출로 인한 열화 현상은 금속 산화물의 코팅을 통해 해결할 수 있음을 알 수 있었으며, 특히 $Al_2O_3$가 코팅되었을 때 가장 큰 효과를 볼 수 있음을 알 수 있었다. 상대적으로 긴 잔광 시간은 Mn 농도를 늘린 $Zn_2SiO_4:Mn$ 형광체를 사용함으로 개선할 수 있고, 부족한 휘도는 $YBO_3:Tb$ 형광체를 혼합하여 사용함으로써 개선할 수 있었다. 아울러 본 연구에서는 $YBO_3:Tb$ 형광체 대신으로 115%의 휘도를 가지는 $(Y,\;Gd)Al_3(BO_3)_4:Tb$ 형광체의 사용이 가능함을 제안하였으며, 3D-PDP에 적용하기에 적합한 1 ms 내외의 잔광 시간을 가지는 $(Mg,\;Zn)Al_2O_4:Mn$ 형광체를 제안하였다.

• 한국재료학회:학술대회논문집
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• 한국재료학회 2012년도 춘계학술발표대회
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• pp.58.2-58.2
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• 2012

Heavy hydrocarbon reforming is a core technology for "Dirty energy smart". Heavy hydrocarbons are components of fossil fuels, biomass, coke oven gas and etc. Heavy hydrocarbon reforming converts the fuels into $H_2$-rich syngas. And then $H_2$-rich syngas is used for the production of electricity, synthetic fuels and petrochemicals. Energy can be used efficiently and obtained from various sources by using $H_2$-rich syngas from heavy hydrocarbon reforming. Especially, the key point of "Dirty energy smart" is using "dirty fuel" which is wasted in an inefficient way. New energy conversion laboratory of KAIST has been researched diesel reforming for solid oxide fuel cell (SOFC) as a part of "Dirty energy smart". Diesel is heavy hydrocarbon fuels which has higher carbon number than natural gas, kerosene and gasoline. Diesel reforming has difficulties due to the evaporation of fuels and coke formation. Nevertheless, diesel reforming technology is directly applied to "Dirty fuel" because diesel has the similar chemical properties with "Dirty fuel". On the other hand, SOFC has advantages on high efficiency and wasted heat recovery. Nippon oil Co. of Japan recently commercializes 700We class SOFC system using city gas. Considering the market situation, the development of diesel reformer has a great ripple effect. SOFC system can be applied to auxiliary power unit and distributed power generation. In addition, "Dirty energy smart" can be realized by applying diesel reforming technology to "Dirty fuel". As well as material developments, multidirectional approaches are required to reform heavy hydrocarbon fuels and use $H_2$-rich gas in SOFC. Gd doped ceria (CGO, $Ce_{1-x}Gd_xO_{2-y}$) has been researched for not only electrolyte materials but also catalysts supports. In addition, catalysts infiltrated electrode over porous $La_{0.8}Sr_{0.2}Ga_{0.8}Mg_{0.2}O_3-{\delta}$ and catalyst deposition at three phase boundary are being investigated to improve the performance of SOFC. On the other hand, nozzle for diesel atomization and post-reforming for light-hydrocarbons removal are examples of solving material problems in multidirectional approaches. Likewise, multidirectional approaches are necessary to realize "Dirty energy smart" like reforming "Dirty fuel" for SOFC.

• Bulletin of the Korean Chemical Society
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• 제34권10호
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• pp.2900-2904
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• 2013

We present the synthesis and characterization of DTPA-bis(histidylamide) (1a), DTPA-bis(aspartamide) (1b), and their gadolinium complexes of the type $[Gd(L)(H_2O)]$ (2a:L = 1a; 2b:L = 1b). Thermodynamic stabilities and $R_1$ relaxivities of 2a-b compare well with Omniscan$^{(R)}$, a well-known commercial, extracellular (ECF) MRI CA which adopts the DTPA-bis(amide) framework for the chelate: $R_1$ = 5.5 and 5.1 $mM^{-1}$ for 2a and 2b, respectively. Addition of the Cu(II) ion to a solution containing 2b triggers relaxivity enhancement to raise $R_1$ as high as 15.3 $mM^{-1}$, which corresponds to a 300% enhancement. Such an increase levels off at the concentration beyond two equiv. of Cu(II), suggesting the formation of a trimetallic ($Gd/Cu_2$) complex in situ. Such a relaxivity increase is almost negligible with Zn(II) and other endogenous ions such as Na(I), K(I), Mg(II), and Ca(II). In vivo MR images and the signal-to-noise ratio (SNR) obtained with an aqueous mixture of 2b and Cu(II) ion in an 1:2 ratio demonstrate the potentiality of 2 as a copper responsive MRI CA.

• Nuclear Engineering and Technology
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• 제8권2호
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• pp.81-88
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• 1976

Flash Method로서 열에 관련된 물리적인 성질(밀도, 정압비열 또는 열확산 계수등)을 측정할 수 있는데 이 방법을 이용하여 핵연료의 열화산 계수를 상온(300k)으로부터 고온(1400 K)까지 측정하였으며 정압비열은 시차열용량법 (Differential Scanning Calorimeter)에 의하여 상온에서부터 500k까지 측정하였고 열전도 계수는 열확산 계수, 정압비열 그리고 핵연료의 밀도로부터 계산하였다. 본 연구의 결과는 낮은 온도(500k 이하)에서는 불순물의 정도(Impurity Level)에 따라서 열전도 계수가 크게 달라지기 때문에 중요시되지만 높은 온도(1000k 이상)에서는 불순물의 정도에 따른 열전도 계수의 변화가 근소함으로 그의 존재유무가 비교적 중요시되지 않는 Dielectric Material의 보편적인 경향과 완전히 일치하였다. Gd$_2$O$_3$를 첨가한 다수의 $UO_2$ Sample들에 대한 열확산 계수를 상온에서 측정하여 비교함으로써 이것을 재확인하였다.

• Nuclear Engineering and Technology
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• 제52권11호
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• pp.2572-2580
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• 2020

Emerging gamma ray detection applications that utilize neutron-based interrogation result in the prompt emission of high-energy (>2 MeV) gamma-rays. Rapid imaging is enabled by scintillators that possess high density, high atomic number, and excellent energy resolution. In this paper, we evaluate the bright (50,000 photons/MeV) oxide scintillator, cerium-doped Gd₂Al₂Ga₃O₁₂ (GAGG(Ce)). A silicon photomultiplier (SiPM) array is coupled to a GAGG(Ce) scintillator array (12 × 12 pixels) and integrated into a coded-aperture based gamma-ray imaging system. A resistor-based symmetric charge division circuit was used reduce the multiplicity of the analog outputs from 144 to 4. The developed system exhibits 9.1%, 8.3%, and 8.0% FWHM energy resolutions at 511 keV, 662 keV, and 1173.2 keV, respectively. In addition, a pixel-identification resolution of 602 ㎛ FWHM was obtained from the GAGG(Ce) scintillator array.

• Nuclear Engineering and Technology
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• 제55권7호
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• pp.2578-2590
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• 2023

In this work, a 24-month two-batch fuel management strategy for the APR1400 using LEU + has been investigated, where enrichments of 5.9 and 5.2 w/o are utilized in lieu of the conventional 4-5 w/o UO₂ fuel. In addition, an Accident Tolerant Fuel (ATF) clad based on the swaging technology is applied to APR1400 fuel assemblies. In this special ATF clad design, both outer and inner SS316 layers protect the conventional zircaloy clad. Erbia (Er₂O₃) is introduced as a burnable absorber with two-fold goals to lower the critical boron concentration in the long-cycle LEU + loaded core as well as to handle the LEU + fuel in the existing front-end fuel facilities without renewing the license. Two types of fuel assemblies with different loading of gadolinia (Gd₂O₃) are considered to control both the reactivity and the core radial power distribution. The erbia burnable absorber is uniformly admixed with UO₂ in all fuel pins except for the gadolinia-bearing ones. In this study, two core designs were devised with different erbia loading, and core performance and safety parameters were evaluated for each case in comparison with a core design without any burnable absorbers. The core analysis was done using the two-step method. First, cross-sections are generated by the SERPENT 2 Monte Carlo code, and the 3-D neutronic analysis is performed with an in-house multi-physics nodal code KANT.

• Journal of Radiation Protection and Research
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• 제47권4호
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• pp.214-225
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• 2022

Background: The conventional cerium-doped Gd₂Al₂Ga₃O₁₂ (GAGG(Ce)) scintillator-based gamma-ray imager has a bulky detector, which can lead to incorrect positioning of the gammaray source if the shielding against background radiation is not appropriately designed. In addition, portability is important in complex environments such as inside nuclear power plants, yet existing gamma-ray imager based on a tungsten mask tends to be weighty and therefore difficult to handle. Motivated by the need to develop a system that is not sensitive to background radiation and is portable, we changed the material of the scintillator and the coded aperture. Materials and Methods: The existing GAGG(Ce) was replaced with Bi₄Ge₃O₁₂ (BGO), a scintillator with high gamma-ray detection efficiency but low energy resolution, and replaced the tungsten (W) used in the existing coded aperture with lead (Pb). Each BGO scintillator is pixelated with 144 elements (12 × 12), and each pixel has an area of 4 mm × 4 mm and the scintillator thickness ranges from 5 to 20 mm (5, 10, and 20 mm). A coded aperture consisting of Pb with a thickness of 20 mm was applied to the BGO scintillators of all thicknesses. Results and Discussion: Spectroscopic characterization, imaging performance, and image quality evaluation revealed the 10 mm-thick BGO scintillators enabled the portable gamma-ray imager to deliver optimal performance. Although its performance is slightly inferior to that of existing GAGG(Ce)-based gamma-ray imager, the results confirmed that the manufacturing cost and the system's overall weight can be reduced. Conclusion: Despite the spectral characteristics, imaging system performance, and image quality is slightly lower than that of GAGG(Ce), the results show that BGO scintillators are preferable for gamma-ray imaging systems in terms of cost and ease of deployment, and the proposed design is well worth applying to systems intended for use in areas that do not require high precision.

• 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.