• 한국재료학회지
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• 제20권7호
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• pp.370-373
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• 2010

In fabricating plasma display panels, the photolithographic process is used to form patterns of barrier ribs with high accuracy and high aspect ratio. It is important in the photolithographic process to control the refractive index of the photosensitive paste. The composition of this paste for photolithography is based on the $B_2O_3-SiO_2-Al_2O_3$ glass system, including additives of alkali oxides and rare earth oxides. In this work, we investigated the density, structure and refractive index of glasses based on the $B_2O_3-SiO_2-Al_2O_3$ system with the addition of $Li_2O$, $K_2O$, $Na_2O$, CaO, SrO, and MgO. The refractive index of the glasses containing K2O, Na2O and CaO was similar to that of the [BO3] fraction while that of the SrO, MgO and Li2O containing glasses were not correlated with the coordination fraction. The coordination number of the boron atoms was measured by MAS NMR. The refractive index increased with a decrease of molar volume due to the increase in the number of non-bridging oxygen atoms and the polarizability. The lowest refractive index (1.485) in this study was that of the $B_2O_3-SiO_2-Al_2O_3-K_2O$ glass system due to the larger ionic radius of $K^+$. Based on our results, it has been determined that the refractive index of the $B_2O_3-SiO_2-Al_2O_3$ system should be controlled by the addition of alkali oxides and alkali earth oxides for proper formation of the photosensitive paste.

• Progress in Superconductivity
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• 제11권2호
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• pp.87-91
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• 2010

We fabricated the polyacrylic acid (PAA)-doped $MgB_2$ bulks and characterized their lattice parameters, actual C substitutions, microstructures, and critical properties. The boron (B) powder was mixed with PAA using N,N-dimethylformamide as solvent and then the solution was dried out at $200^{\circ}C$ and crushed. The C treated B powder and magnesium powder were mixed and compacted by uniaxial pressing at 500 MPa, followed by sintering at $900^{\circ}C$ for 1 h in high purity Ar atmosphere. We observed that the PAA doping increased the MgO amount but decreased the grain size, a-axis lattice constant, and critical temperature ($T_c$), which is indicative of the C substitution for B sites in $MgB_2$. In addition, the critical current density ($J_c$) at high magnetic field was significantly improved with increasing PAA addition: at 5 K and 6.6 T, the $J_c$ of 7 wt% PAA-doped sample was $6.39\;{\times}\;10^3\;A/cm^2$ which was approximately 6-fold higher than that of the pure sample ($1.04\;{\times}\;10^3\;A/cm^2$). This improvement was probably due to the C substitution and the refinement of grain size by PAA doping, suggesting that PAA is an effective dopant in improving $J_c$(B) performance of $MgB_2$.

• 한국세라믹학회지
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• 제50권3호
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• pp.238-243
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• 2013

We investigated the effect of Pb-metal filler added to a hybrid paste(PbO-$Bi_2O_3-B_2O_3$-ZnO glass frit and Pb-powder), for joining flip-chip sat lower temperatures than normal. The glass transition temperature was detected at $250^{\circ}C$ and the softening point occurred at $330^{\circ}C$. As the temperature increased, the specific density decreased due to the volatility of the Pb-metal and boron component in the glass. When the glass was heat-treated at $350^{\circ}C$ for 5 min, XRD results revealed a crystalline $Pb_4Bi_3B_7O_{19}$ phase that had been initiated by the addition of Pb-filler in the hybrid paste. The addition of the Pb-metal filler caused are action between the Pb-metal and glass that accelerated the formation of the liquid phase. The liquid phase that formed, promoted bonding between the flip-chip substrate sat lower temperature.

• 한국추진공학회:학술대회논문집
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• 한국추진공학회 2017년도 제48회 춘계학술대회논문집
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• pp.513-516
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• 2017

화약 기반 소자 (PMD)에서 장기간 보관을 하게 되면 소자 안에 있는 화약이 노화되어 폭발력에 변화가 생기기 때문에, 일정 기간이 지나면 폐기 처분을 하게 된다. 그렇기 때문에 PMD 안에 사용하는 화약은 자발적 혹은 외부적 요인에 대하여 화학적 및 물리적으로 안정해야 한다. 기존에 사용되는 화약으로서 $BKNO_3$과 THPP를 대표적으로 이용하기 때문에, 이 화약들을 기반으로 하여 열역학적 및 속도론적 분석을 실시하였다. Differential scanning calorimeter (DSC)를 이용하여 발열량과 반응속도를 분석하였는데, 그 결과 THPP에서는 열량 차이 및 반응속도에 큰 변화가 보이지 않았다. 추가적으로, 노화에 직접적으로 연관되는 산화막 형성을 확인하기 위하여 XPS 및 TEM-EDS 분석하였는데, 열적 분석 결과와 상응하는 결과로서 산화막이 관측 되지 않았다. 이는 THPP가 장기 안정성 측면에서 가장 유명한 화약이라고 판단 할 수 있다.

• 한국재료학회지
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• 제6권8호
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• pp.841-851
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• 1996

최근의 연구에 의하면 직접 소입강에서 미량의 베이나이트상의 생성이 확인되었다. 마르텐사이트 변태전에 생성된 베이나이트상은 마르텐사이트의 패킷을 미세화시키고 입도 미세화로 기계적 성질을 향상시킨다고 한다. 본 연구에서는 미량 합금 원소로 Mo, B 등을 첨가한 강을 $1200^{\circ}C$에서 단조하여 물에 직접 소입한 후, 베이나이트상의 분율을 조절하기 위해 베이나이트 변태 온도에서 일정시간 유지하는 열처리 과정을 거쳐 생성된 베이나이트상의 분율과 기계적 성질간의 관계를 고찰하였다. 이로써 마르텐사이트와 베이나이트 혼합 조직의 강도와 인성을 증가시키는 효과적인 베이나이트 분율을 조사한 후에, 직접 소입시에 이와 같은 분율의 베이나이트 함량으로 조절할 수 있는 방법을 제시하여 고강도 고인성형 직접 소입강의 개발에 활용하고자 한다.

• 대한화학회지
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• 제12권2호
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• pp.65-80
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• 1968

9種의 選擇된 탈리움硼硅酸유리와 21種의 同類組成을 變化시킨 유리에 對하여 物理化學的 性質을 檢討하였다. 이들 組成에 依한 性質의 變化曲線은 여러 點에서 酸化리티움, 소다 및 酸化鉛들을 包含하는 다른 硼硅酸유리와 類似하였다. 탈리움 硼硅酸유리의 組成에 따른 成質의 變化曲線에 極少點이 나타났는데, 이는 $Na_2O-B_2O_3-SiO_2$유리에서 關察된 바와 같이 硼素結合의 變化에 基因되는 것 같다. 탈리움 이온이 硼硅酸유리에 미치는 主 影響을 綜合해 보면 다음과 같다. 1) 탈리움 이온을 添加함으로써 密度, 屈折率, 물에 對한 溶解度, 熱線膨脹係數, 誘電恒數 等이 增加되었다. 2) 탈리움 濃度을 增加시킴으로써 유리의 軟化點이 降下되었고, 紫外線 照射에 依하여 螢光이 생겼으며, 赤外線 $15{\mu}$까지의 吸收端이 不明確해 졌다. $Tl_2O-B_2O_3-SiO_2$ 系에서 廣範한 液體不混合性이 電子顯微鏡에 依해 밝혀졌다. 不混合性은 $B_2O_3-SiO_2$ 二成分系에 對하여 約 $Tl_2O$ 55wt.%의 組成範圍內에서 나타났다. 不混合性유리는 多硅酸과 多硅素相으로 分離 構成되어 있음이 酸處理에 依하여 밝혀졌다.

• 한국토양비료학회지
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• 제38권1호
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• pp.45-51
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• 2005

유효규산을 다량 함유하고 있는 알카리성 석탄회를 농업적으로 활용하고자 산성의 인산석고와 50:50으로 혼합하여 토양 개량제를 제조하였다. 혼합제재의 적정 시용량과 토양의 이화학적 특성에 미치는 영향을 조사하기 위해 평택통의 논토양에 혼합제재를 0, 20, 40, $60Mg\;ha^{-1}$의 4 수준으로 처리하여 벼 재배시험을 실시하였다. 혼합제재 시용량이 증가함에 따라 벼의 수량성은 증가하여 약 $30Mg\;ha^{-1}$ 처리시 최고수량(Yield Index 109)을 획득할 수 있었다. 혼합제재 시용에 따른 백미와 토양내 중금속 함량의 증가는 발생되지 않았으며, 토양의 pH 향상, 그리고 유효 규산 및 인산함량 및 치환성 칼슘함량을 증가시켜 토양 비옥도 개선에 효과가 있었다. 벼 재배과정 중 혼합제재를 최고 $60Mg\;ha^{-1}$ 처리시 토양내 유효붕소 함량은 최고 $1.42mg\;B\;kg^{-1}$ 까지 증가하였으나, 생육기간 중 붕소독성은 발생되지 않았다. 이상의 결과로부터 석탄회와 인산석고의 50:50 혼합제재는 토양개량제로서 활용성이 대단히 높은 것으로 평가된다.

• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1120-1130
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• 2020

The CREOLE experiment performed In the EOLE critical facility located In the Nuclear Center of CADARACHE - CEA have allowed us to get interesting and complete experimental information on the temperature effects in the light water reactor lattices. To analyze these experiments with accuracy an elaborate calculation scheme using the Monte Carlo method implemented in the MCNP6.1 code and the ENDF/B-VII.1 cross section library has been developed. We have used the ENDF/B-VII.1 data provided with the MCNP6.1.1 version in ACE format and the Makxsf utility to handle the data in the specific temperatures not available in the MCNP6.1.1 original library. The main purpose of this analysis is the qualification of the ENDF/B-VII.1 nuclear data for the prediction of the Reactivity Temperature Coefficient while ensuring the ability of the MCNP6.1 system to model such a complex experiment as CREOLE. We have analyzed the case of UO₂ lattice with 1166 ppm of boron in ordinary water moderator in specified temperatures. A detailed comparison of the calculated effective multiplication factors with the reference ones [1] in room temperature presented in this work shows a good agreement demonstrating the validation of our 3D calculation model. The discrepancies between calculations and the differential measurements of the Reactivity Temperature Coefficient for the analyzed configuration are relatively small: the maximum discrepancy doesn't exceed 1,1 pcm/℃. In addition to the analysis of direct differential measurements of the reactivity temperature coefficient performed in the poisoned UO₂ lattice configuration, we have also analyzed integral measurements in UO₂ clean lattice configuration using equivalency of the integral temperature reactivity worth with the driver core fuel reactivity worth and soluble boron reactivity worth. In this case both of the ENDF/B-VII.1 and JENDL.4 libraries were used in our analysis and the obtained results are very similar.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2002년도 Proceedings
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• pp.161-163
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• 2002

The BNCT(Boron Neutron Capture Therapy) facility has been developed in Hanaro(High-flux Advanced Neutron Application Reactor), a research reactor of Korea Atomic Energy Research Institute. A typical tangenial beam port is utilized with this BNCT facility. Thermal neutrons can be penetrated within the limits of the possible maximum instead of being filtered fast neutrons and gamma rays as much as possible using the silicon and bismuth single crystals. In addition to, the liquid nitrogen (LN$_2$) is used to cool down the silicon and bismuth single crystals for the increase of the penetrated thermal neutron flux. Neutron beams for BNCT are shielded using the water shutter. The water shutter was designed and manufactured not to interfere with any other subsystem of Hanaro when the BNCT facility is operated. Also, it is replaced with conventional beam port plug in order to cut off helium gas leakage in the beam port. A circular collimator, composed of $\^$6/Li$_2$CO$_3$ and polyethylene compounds, is installed at the irradiation position. The measured neutron flux with 24 MW reactor power using the Au-198 activation analysis method is 8.3${\times}$10$\^$8/ n/cm$^2$ s at the collimator, exit point of neutron beams. Flatness of neutron beams is proven to ${\pm}$ 6.8% at 97 mm collimator. According to the result of acceptance tests of the water shutter, the filling time of water is about 190 seconds and drainage time of it is about 270 seconds. The radiation leakages in the irradiation room are analyzed to near the background level for neutron and 12 mSv/hr in the maximum for gamma by using BF$_3$ proportional counter and GM counter respectively. Therefore, it is verified that the neutron beams from BNCT facility in Hanaro will be enough to utilize for the purpose of clinical and pre-clinical experiment.

• Nuclear Engineering and Technology
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• 제56권8호
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• pp.3307-3314
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• 2024

For traditional spent fuel shielding materials, due to physical and chemical defects and cost constraints, they have been unable to meet the needs. Therefore, this paper carries out the first discussion on the application and performance of bismuth in neutron shielding by establishing Monte Carlo simulation on the neutron flux model of shielded spent fuel. Firstly, functional fillers such as bismuth oxide, lead oxide, boron oxide, gadolinium oxide and tungsten oxide are added to the matrices to compare the shielding rates of aluminum alloy matrix and silicone rubber matrix. The shielding rate of silicone rubber mixture is higher than aluminum alloy mixture, reaching more than 56%. The optimal addition proportion of bismuth oxide and lead oxide is 30%, and the neutron radiation protection efficiency reaches 60%. Then, the mass attenuation coefficients of bismuth oxide, lead oxide, boron oxide, gadolinium oxide and tungsten oxide in silicone rubber matrix are simulated with the change of functional fillers proportion and neutron energy. This simulation result shows that the mixture with functional fillers has good shielding performance for low energy neutrons, but poor shielding effect for high energy neutrons. Finally, in order to further evaluate the possibility of replacing lead oxide with bismuth oxide as shielding material, the half-value layers and various properties of bismuth oxide and lead oxide are compared. The results show that the shielding properties of bismuth oxide and lead oxide are basically the same, and the mechanical properties, heat resistance, radiation resistance and environmental protection of bismuth oxide are better than that of lead oxide. Therefore, in the case of neutron source strengths in the range of 0.01-6 MeV and secondary gamma rays produced below 2.5 MeV, bismuth can replace lead in neutron shielding applications.