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Low-Power Discrete-Event SoC for 3DTV Active Shutter Glasses (3DTV 엑티브 셔터 안경을 위한 저전력 이산-사건 SoC)

  • Park, Dae-Jin;Kwak, Sung-Ho;Kim, Chang-Min;Kim, Tag-Gon
    • Journal of the Institute of Electronics Engineers of Korea SP
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    • v.48 no.6
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    • pp.18-26
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    • 2011
  • Debates concerning the competitive edge of leading 3DTV technology of the shutter glasses (SG) 3D and the film-type patterned retarder (FPR) are flaring up. Although SG technology enables Full-HD 3D vision, it requires complex systems including the sync transmitter (emitter), the sync processor chip, and the LCD lens in the active shutter glasses. In addition, the transferred sync-signal is easily affected by the external noise and a 3DTV viewer may feel flicker-effect caused by cross-talk of the left and right image. The operating current of the sync processor in the 3DTV active shutter glasses is gradually increasing to compensate the sync reconstruction error. The proposed chip is a low-power hardware sync processor based discrete-event SoC(system on a chip) designed specifically for the 3DTV active shutter glasses. This processor implements the newly designed power-saving techniques targeted for low-power operation in a noisy environment between 3DTV and the active shutter glasses. This design includes a hardware pre-processor based on a universal edge tracer and provides a perfect sync reconstruction based on a floating-point timer to advance the prior commercial 3DTV shutter glasses in terms of their power consumption. These two techniques enable an accurate sync reconstruction in the slow clock frequency of the synchronization timer and reduce the power consumption to less than about a maximum of 20% compared with other major commercial processors. This article describes the system's architecture and the details of the proposed techniques, also identifying the key concepts and functions.

Review of the Gross Alpha for Characterization of Radioactive Waste (방사성폐기물 특성평가를 위한 전알파 분석법 고찰)

  • Kim, Hyuncheol;Lim, Jong-Myoung;Jang, Mee;Park, Ji-Young
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.18 no.2_spc
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    • pp.227-235
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    • 2020
  • In this study, we discussed the limitations of gross alpha measurements for the characterization of radioactive wastes produced in nuclear facilities through experimental tests and Monte Carlo N-particle transport simulations. The determination of gross alpha is essential for the disposal of radioactive waste produced in nuclear facilities in Korea. The measurements of gross alpha are easy to perform and yield rapid analytical results, but it cannot be used for quantitative analysis. The error of counting efficiency for gross alpha with various masses of the deposit on planchets using KCl and 241Am was determined. The relative deviation of the counting efficiency in samples having the same mass was 20%. Uranium was extracted from the soil through acid leaching and extraction chromatography, and the concentration of U determined by inductively coupled plasma-mass spectrometry (ICP-MS) was compared with the results for gross alpha. The gross alpha was underestimated by 50% compared to the U concentration by ICP-MS. The counting efficiency depended on the energy from the alpha emitters, which differed by up to three times in determination of the counting efficiency depending on the kinds of alpha radionuclides of interest. Therefore, the gross alpha is not compatible with the sum of radioactivity for each alpha emitter and is suitable as a screening method.

A Study of Low-Voltage Low-Power Bipolar Linear Transconductor and Its Application to OTA (저전압 저전력 바이폴라 선형 트랜스컨덕터와 이를 이용한 OTA에 관한 연구)

  • Shin, Hee-Jong;Chung, Won-Sup
    • Journal of the Institute of Electronics Engineers of Korea SC
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    • v.37 no.1
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    • pp.40-48
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    • 2000
  • 1A novel bipolar linear transconductor and its application to operational transconductance amplifier(OTA) for low-voltage low-power signal processing is proposed. The transconductor consists of a npn differential-pair with emitter degeneration resistor and a pnp differential-pair connected to the npn differential-pair in cascade. The bias current of the pnp differential-pair is used with the output current of the npn differential-pair for wide linearity and temperature stability. The OTA consists of the linear transconductor and a translinear current cell followed by three current mirrors. The proposed transconductor has superior linearity and low-voltage low-power characteristics when compared with the conventional transconductor. The experimental results show that the transconductor with transconductance of 50 ${\mu}S$ has a linearity error of less than ${\pm}$0.06% over an input voltage range from -2V to +2V at supply voltage ${\pm}$3V. Power dissipation of the transconductor was 2.44 mW. A prototype OTA with a transconductance of 25 ${\mu}S$ has been built with bipolar transistor array. The linearity of the OTA was same as the proposed transconductor. The OTA circuit also exhibits a transconductance that is linearly dependent on a bias current varying over four decades with a sensitivity of 0.5 S/A.

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Assessment of GHG Emission Reduction Potential in Extension of Nuclear and Renewable Energy Electricity Generation (원자력과 신재생에너지 발전설비 확대에 따른 온실가스 저감 잠재량에 관한 연구)

  • Jun, Soo-Young;Park, Sang-Won;Song, Ho-Jun;Park, Jin-Won
    • Journal of Energy Engineering
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    • v.18 no.3
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    • pp.191-202
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    • 2009
  • South Korea, ranks 10th largest emitter of carbon dioxide in the world, will probably be under the obligation to reduce GHG emission from 2013. It is very important to reduce the electrical energy consumption since 30% of GHG emission in South Korea is made during electricity generation. In this study, based on "the 1st national energy master plan", the GHG emission reduction potential and the feasibility of the scenario in the electricity generation have been analyzed using LEAP(Long-range Energy Alternative Planning system). The scenario of the mater plan contains the 41% expansion of nuclear power plant facilities and the 11% diffusion of renewable energy until 2030. In result, total $CO_2$ emission reduction rate is 28.8% in 2030. Also $CO_2$ emission of unit electricity generation of bituminous coal power plant is $0.85kgCO_2/kWh$ and its LNG power plant is $0.51kgCO_2/kWh$ in BAU scenario. Therefore when existing facilities is exchanged for nuclear or renewable energy power plant, substitute of bituminous power plant is more effective than LNG power.

Acute Toxicity of DW-166HC (Hlolmium-165-chitosan) in Mice (마우스에서의 DW-166HC (Ho1mium-165-chitosan)에 대한 급성독성)

  • Lee, Won-Yong;Lee, Jin;Moon, Eun-Yi;Nam, Soon-Chul;Lee, Dug-Keun;Yoon, Sung-June
    • Biomolecules & Therapeutics
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    • v.5 no.1
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    • pp.100-105
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    • 1997
  • DW-166HC ($^{166}$Holmium-chitosan) is a complex of $^{166}$Ho, $\beta$- and $\gamma$-ray emitter, and chitosan, a polymer of glucosamine, with radiotherapeutic potential. The current study was performed to determine the acute toxicities of $^{165}$Ho-chitosan in mice by two different routes of administration. The both sex mice were given a single intravenous bolus injection of $^{165}$Ho-chitosan complex at doses of 12, 10, 6, 5 and 4 mg/kg or subcutaneous administration at doses of 600, 500, 400 and 300 mg/kg. Chitosan was dosed to control animals as 16 and 800 mg/kg, intravenously and subcutaneously, respectively. The doses of $_{165}$Ho-chitosan complex were expressed as $_{165}$holmium nitrate pentahydrate and the ratio of $^{165}$Ho$(NO_3)_3$).$5H_2O$ to chitosan was 3/4 Severe convulsion and respiratory failure were followed by death within 10 min after intravenous dosing. Transient unilateral hindlimb hypokinesias were found in two mice of 5 mg/kg dosing group during the study period. No abnormalities were observed during the necropsy of survived animals in intravenous dosing group. Only one male animal was found dead in 500 mg/kg subcutaneously dosed group. Alopecia with or without cutaneous ulcer were found in most mice including control animals. During necropsy, omental adhesion was observed in all dose ranges and enlarged spleen was found in several animals including control group. It is suggested that the acute intravenous >).$LD_{50}s$ for male and female mice were 4.90 and 6.03 mg/kg, respectively. The lowest lethal dose in male was 500 mg/kg by subcutaneous administration.

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Study on the Preparations of New $^{166}Ho$-Chitosan Complex and Its Macroaggregates for a Potential Use of Internal Radiotherapy (새로운 내부 방사선 치료용 $^{166}Ho$-Chitosan 착물 및 그 응집입자의 제조에 관한 연구)

  • Park, K.B.;Kim, Y.M.;Shin, B.C.;Kim, J.R.
    • The Korean Journal of Nuclear Medicine
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    • v.30 no.3
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    • pp.351-360
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    • 1996
  • Chitosan is a polysaccharide of natural orgin obtained by full or partial deacetylation of chitin, a very abudant natural polymer, which has the properties of biocompatibilities, bioaffinities, and biodegradabilities. The free amino group of chitosan should be participated in forming chelate with holmium (${\beta}$-emitter). $^{166}Ho(NO_3)_3\;5H_2O$ of high radionuclidic purity of upto 99.9% was made by neutron irradiation of naturally occuring $^{166}Ho(NO_3)_3\;5H_2O$, and then reacted with the prepared chitosan solution. The effect of pH, reaction time, the concentration and viscosity of chitosan and the amount of $^{166}Ho$ on forming $^{166}Ho$-chitosan complex ($^{166}Ho$-CHICO) were investigated. $^{166}Ho$-chitosan macroaggregate($^{166}Ho$-CHIMA) was made from $^{166}Ho$-CHICO. Their physical properties such as radionuclidic purity, particle size distribution, stability in vitro and vivo were examined. Their high in vitro and vivo stability makes them attractive agents for internal radiotherapy by local administeration.

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Laser-based THz Time-Domain Spectroscopy and Imaging Technology (레이저 기반 테라헤르츠 시간영역 분광 및 영상 기술)

  • Kang, Kwang-Yong;Kwon, Bong-Joon;Paek, Mun Cheol;Kang, Kyeong Kon;Cho, Suyoung;Kim, Jangsun;Lee, Senung-Churl;Lee, Dae-sung
    • Journal of Sensor Science and Technology
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    • v.27 no.5
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    • pp.317-327
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    • 2018
  • Terahertz (THz) time-domain spectroscopy(TDS), imaging techniques, and related systems have become mature technologies, widely used in many universities and research laboratories. However, the development of creative technologies still requires improved THz application systems. A few key points are discussed, including the innovative advances of mode-locking energy-emitting semiconductor lasers and better photoconductive semiconductor quantum structures. To realize a compact, low cost, and high performance THz system, it is essential that THz spectroscopy and imaging technologies are better characterized by semiconductor and nano-devices, both static and time-resolved. We introduce the THz spectroscopy and imaging systems, the OSCAT(Optical Sampling by laser CAvity Tuning) system and the ASOPS(ASynchronous Optical Sampling) system, are constructed by our research team. We report on the THz images obtained from their use.

CVD를 이용한 수직으로 정렬된 탄소나노튜브의 합성과 성장한계에 관한 메커니즘

  • Park, Sang-Eun;Song, U-Seok;Kim, Yu-Seok;Song, In-Gyeong;Lee, Su-Il;Park, Jong-Yun
    • Proceedings of the Korean Vacuum Society Conference
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    • 2013.02a
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    • pp.615-615
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    • 2013
  • 탄소나노튜브(carbon nanotubes; CNT)는 강철보다 10~100배 견고할 뿐만 아니라 영률과 탄성률 은 각각 1.8 TPa, 1.3 TPa에 달하는 매우 우수한 기계적 강도를 지니고 있으며, 구리보다 좋은 전기 전도도와 다이아몬드의 2배에 이르는 열전도도를 지닌 물질이다. 이러한 탄소나노튜브의 우수한 특성을 이용하여 나노섬유, 고분자-탄소나노튜브의 고기능 복합체, 나노소자, 전계방출원(field emitter), 가스센서 등 다양한 분야로의 활용을 위한 연구가 진행되고 있다. 특히, 수백 ${\mu}m$ 이상의 길이로 수직 성장된 탄소나노튜브(VA-CNTs)의 합성은 길이 대 직경의 비(aspect ratio)가 비약적으로 증가하여 앞서 언급한 분야로의 활용이 더욱 유리하며, 그 중에서도 대량 생산, 나노섬유 및 나노복합체로서의 활용에 극히 유용하다. 최근에는 열 화학기상증착(thermal chemical vapor deposition; TCVD)법을 이용하여 탄소나노튜브의 구조를 제어하는 연구들이 많이 보고되고 있다. 열 화학기상증착을 이용한 수직 정렬된 탄소나노튜브의 합성에서 합성조건의 변화는 탄소나노튜브의 길이, 벽의 수, 직경, 결정성 등 구조에 큰 영향을 미친다. 탄소나노튜브는 이러한 구조에 따 라 물리적 특성이 달라지기 때문에 다양한 분야로의 응용을 위해서는 합성에 대한 근본적인 이해 가 절실히 요구된다. 본 연구에서는 열 화학기상증착법을 이용한 합성에서 성장압력의 변화에 따른 탄소나노튜브의 구조적 특성을 조사하였다. 성장압력의 변화는 탄소나노튜브의 밀도, 길이, 결정성에 큰 영향을 미치는 것을 주사전자현미경과 라만분광법을 이용하여 확인하였다. 이러한 결과 는 탄소나노튜브 박막(CNT forest)의 가장자리(edge)에 비정질 탄소(amorphous carbon)의 흡착으로 인한 나노튜브사이의 간격(intertube distance)이 좁아짐에 따른 가스공급 차단 효과로 설명이 가능 하다. 또한, 마이크로웨이브 플라즈마 화학기상증착법을 이용하여 탄소나노튜브를 합성하였다. 합성과정 중 산소(O2)를 주입 하였을 경우, 그렇지 않은 경우에 비하여 성장 속도가 증가하여 3시간 합성 시 2 mm가 넘는 수직 정렬된 탄소나노튜브를 합성 할 수 있었다. 이러한 결과는 과잉 공급 되어 탄소나노튜브로 합성되지 못하고 촉매금속의 표면과 탄소나노튜브의 벽에 비정질의 형태로 붙어있는 탄소 원자들을 추가 주입해 준 산소에 의하여 CO 또는 CO2 형태로 제거해 줌으로써 활성화된 촉매금속의 반응 시간을 향상 시켜주어 탄소공급이 원활하게 이루어졌기 때문이라 생각된다.

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Design of Dual-Polarization Antenna with High Cross-Polarization Discrimination (높은 교차편파 분리도를 가지는 이중편파 안테나 설계)

  • Lee, Sang-Ho;Oh, Taeck-Keun;Ha, Jung-Je;Lee, Yong-Shik
    • The Journal of Korea Institute of Information, Electronics, and Communication Technology
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    • v.10 no.3
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    • pp.199-205
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    • 2017
  • In a small cell base station used in densely populated areas, a dual polarized multiple antenna(MIMO) is mainly used to increase the cell capacity. This paper demonstrates a dual-polarization antenna with high cross-polarization discrimination(XPD) that can improve the capacity of a small cell using a dual polarization multiple antenna (MIMO). By using the symmetric structure and differential feeding, high XPD in all directions is achieved. In addition, a very similar radiation pattern is observed between each polarization. Because of high XPD and similar radiation pattern in all directions, proposed antenna is well adopted for small-cell multiple-input multiple-output(MIMO) system. Experimental results shows that the proposed antenna has a bandwidth of 180 MHz (2.51~2.7 GHz), a maximum gain of 4.5 dBi (3.5~4.5 dBi), and a half-power beam width of 85 degrees. In addition, average XPD of 26.4 dB in all directions, more than 13.8 dB increase than previous dual-polarization antennas which use single emitter by using different feeding or selectively use polarization through switching.

Residual Radioactivity Investigation & Radiological Assessment for Self-disposal of Concrete Waste in Nuclear Fuel Processing Facility (콘크리트 폐기물의 자체처분을 위한 잔류방사능 조사 및 피폭선량평가)

  • Seol, Jeung-Gun;Ryu, Jae-Bong;Cho, Suk-Ju;Yoo, Sung-Hyun;Song, Jung-Ho;Baek, Hoon;Kim, Seong-Hwan;Shin, Jin-Seong;Park, Hyun-Kyoun
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.5 no.2
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    • pp.91-101
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    • 2007
  • In this study, domestic regulatory requirement was investigated for self-disposal of concrete waste from nuclear fuel processing facility. And after self-disposal as landfill or recycling/reuse, the exposure dose was evaluated by RESRAD Ver. 6.3 and RESRAD BUILD Ver.3.3 computing code for radiological assessments of the general public. Derived clearance level by the result of assessments for the exposure dose of the general public is 0.1071Bq/g (3.5% enriched uranium) for landfill and $0.05515Bq/cm^2$ (5% enriched uranium) for recycling/reuse respectively. Also, residual radioactivity of concrete waste after decontamination was investigated in this study. The result of surface activity is $0.01Bq/cm^2\;for\;{\alpha}-emitter$ and the result of radionuclide analysis for taken concrete samples from surface of concrete waste is 0.0297Bq/g for concentration of $^{238}U$, below 2w/o for enrichment of $^{235}U$ and 0.0089Bq/g for artificial contamination of $^{238}U$ respectively. Therefore, radiological hazard of concrete waste by self-disposal as landfill and recycling/reuse is below clearance level to comply with clearance criterion provided for Notice No.2001-30 of the MOST and Korea Atomic Energy Act.

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