• Proceedings of the Korean Vacuum Society Conference
• /
• 2011.02a
• /
• pp.392-392
• /
• 2011

현재의 태양전지에 사용되는 wafer는 원가저감을 위해 점점 얇아지고 있는 추세이다. 하지만 wafer가 얇아질수록 장파장 영역의 광자는 충분히 활용할 수 없게 된다. 대부분의 광자는 50um 지점에 도달하였을 때 그 역할을 다하고 소멸하게 되며, 특히 800nm 이상의 장파장에 대한 generation rate는 wafer 두께에 따라 급격한 차이를 보이게 된다. 따라서 장파장 영역의 광자를 효율적으로 사용할 뿐만 아니라 원가 저감을 위해 더욱 얇아지고 있는 추세의 wafer의 장파장 이용을 보상하기 위해서 TCO를 이용한 back-reflector의 역할은 가장 좋은 해결책이 될 것이다. 본 연구에서는 Macleod를 이용하여 ZnO, Al-doped ZnO, TiN, TiO2와 같은 다양한 TCO 물질에 대한 다양한 simulation을 실시 하여 reflectance 특성을 알아보았다. 상기 simulation결과로써 Al-doped ZnO가 가장 reflectance 특성이 좋게 나타났었으며 이를 이종접합 태양전지에 적용하여 광학적 및 전기적 특성 변화에 대해서 분석하였다.

• Journal of the Korean Vacuum Society
• /
• v.17 no.3
• /
• pp.211-214
• /
• 2008

GaN-based light-emitting diodes (LEDs) of a 405 nm wavelength have been fabricated on a sapphire substrate by metal organic chemical vapor deposition (MOCVD). In order to reflect the photons, which are generated in the InGaN active region and emitted to the backside, to the front surface, a reflection layer was deposited onto the back of the substrate. Aluminum was used as the reflection layer and Al was deposited on the sample followed by Ti evaporation for firm adhesion of the reflection layer to the substrate. The light extraction efficiency was enhanced 52 % by adoption of the Ti-Al reflection layer.

• Journal of the Korean Ceramic Society
• /
• v.38 no.12
• /
• pp.1137-1143
• /
• 2001

In this study, glass-ceramics containing cordierite(2MgO$.$2Al$_2$O$_3$5SiO$_2$) as a major crystalline phase was prepared from MAS (MgO-Al$_2$O$_3$-SiO$_2$) glass system for the application to reflector. Glasses prepared with addition of TiO$_2$as a nucleating agent were crystallized by two-step heat treatment of nucleation and crystal growth. Then nucleation and crystal growth behavior were investigated and the influence of heat treatment schedule on the nature of crystal phases and the diffuse reflectance spectrum was investigated. As a result, cordierite and rutile were precipitated as a major crystalline phases for the glass-ceramics with the nucleation at 750$^{\circ}C$ for 3 hours and then crystallization at 1100$^{\circ}C$ for 5 hours, and this glass-ceramics showed the reflectance over 90% in 570∼2500nm specturm region.

• Proceedings of the Korean Vacuum Society Conference
• /
• 2015.08a
• /
• pp.243.1-243.1
• /
• 2015

To replace the based on silicon solar cells, the third generation solar cells, Dye-sensitized solar cells (DSSCs), is low fabrication than silicon solar cells, environmentally friendly and can be applied to various field. For this reason, the DSSCs have been continuously researched. But DSSCs have one drawback that is the low power conversion efficiency (PCE) than silicon solar cells. To solve the problem, we used the backr-eflector the Al foil that can be easily obtained from the surrounding in order to improve the efficiency of the DSSCs. Easily detachable Al foil back-reflector increases the photocurrent by enhancing the harvesting light because the discarded light is reused. It also leads to enhance the power conversion efficiency (PCE). In addition, we compared with the efficiency of the DSSCs that is applied and does not be applied with back-reflector according to the thickness of the TiO2 photoelectrode. When the back-reflector is applied to DSSCs, the photocurrent is increased. It leads to affect the efficiency. We used to solar simulator and Electrochemical Impedance Spectroscopy (EIS) to confirm the PCE and resistance. The DSSCs were also measured by External Quantum effect (EQE). At the same time, FE-SEM and XRD were used to confirm the thickness of layer and crystal structural of photoelectrode.

• Progress in Medical Physics
• /
• v.29 no.4
• /
• pp.101-105
• /
• 2018

In this paper, a neutron moderation system for boron neutron capture therapy (BNCT) based on a $^{252}Cf$ neutron source is proposed. Different materials have been studied in order to produce a high percentage of epithermal neutrons. A moderator with a construction mixture of $AlF_3$ and Al, three reflectors of $Al_2O_3$, BeO, graphite, and seven filters (Bi, Cu, Fe, Pb, Ti, a two-layer filter of Ti+Bi, and a two-layer filter of Ti+Pb) is considered. The MCNPX simulation code has been used to calculate the neutron and gamma flux at the output window of the neutronic system. The results show that the epithermal neutron flux is relatively high for four filters: Ti+Pb, Ti+Bi, Bi, and Ti. However, a layer of Ti cannot reduce the contribution of ${\gamma}$-rays at the output window. Although the neutron spectra filtered by the Ti+Bi and Ti+Pb overlap, a large fraction of neutrons (74.95%) has epithermal energy when the Ti+Pb is used as a filter. However, the percentages of the fast and thermal neutrons are 25% and 0.5%, respectively. The Bi layer provides a relatively low epithermal neutron flux. Moreover, an assembly configuration of 30% $AlF_3+70%$ Al moderator/$Al_2O_3$ reflector/a two-layer filter of Ti+Pb reduces the fast neutron flux at the output port much more than other assembly combinations. In comparison with a recent model suggested by Ghassoun et al., the proposed neutron moderation system provides a higher epithermal flux with a relatively low contamination of gamma rays.

• Nuclear Engineering and Technology
• /
• v.55 no.11
• /
• pp.4246-4251
• /
• 2023

The optimized design of a Neutron Activation Analysis (NAA) system, including Delayed Gamma NAA (DGNAA) and Prompt Gamma NAA (PGNAA), has been proposed in this research based on Mevex Linac with 5 MeV electron energy and 50 kW power as a neutron source. Based on the MCNPX 2.6 simulation, the optimized configuration contains; tungsten as an electron-photon converter, BeO as a photoneutron target, BeD₂ and plexiglass as moderators, and graphite as a reflector and collimator, as well as lead as a gamma shield. The obtained thermal neutron flux at the beam port is equal to 2.06 × 10⁹ (# /cm².s). In addition, using the optimized neutron beam, the detection limit has been calculated for some elements such as H-1, B-10, Na-23, Al-27, and Ti-48. The HPGe Coaxial detector has been used to measure gamma rays emitted by nuclides in the sample. By the results, the proposed system can be an appropriate solution to measure the concentration and toxicity of elements in different samples such as food, soil, and plant samples.