• Title/Summary/Keyword: Beryllium-10

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2-Wavelength Organic Light-Emitting Diodes Using Bebq2 Selectively Doped with (pq)2Ir(acac) (Bebq2에 (pq)2Ir(acac)가 선택 도핑된 2-파장 유기발광다이오드)

  • Kim, Min-Young;Ji, Hyun-Jin;Jang, Ji-Geun
    • Korean Journal of Materials Research
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    • v.21 no.4
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    • pp.212-215
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    • 2011
  • New organic light-emitting diodes with structure of indium-tin-oxide[ITO]/N,N'-diphenyl-N, N'-bis-[4-(phenyl-m-tolvlamino)-phenyl]-biphenyl-4,4'-diamine[DNTPD]/1,1-bis-(di-4-poly-aminophenyl) cyclohexane[TAPC]/bis(10-hydroxy-benzo(h)quinolinato)beryllium[Bebq2]/Bebq2:iridium(III)bis(2-phenylquinoline-N,C2')acetylacetonate[(pq)2Ir(acac)]/ET-137[electron transport material from SFC Co]/LiF/Al using the selective doping of 5%-(pq)2Ir(acac) in a single Bebq2 host in the two wavelength (green, orange) emitter formation were proposed and characterized. In the experiments, with a 300${\AA}$-thick undoped emitter of Bebq2, two kinds of devices with the doped emitter thicknesses of 20${\AA}$ and 40${\AA}$ in the Bebq2:(pq)2Ir(acac) were fabricated. The device with a 20${\AA}$-thick doped emitter is referred to as "D-1" and the device with a 4${\AA}$-thick doped emitter is referred to as "D-2". Under an applied voltage of 9V, the luminance of D-1 and D-2 were 7780 $cd/m^2$ and 6620 $cd/m^2$, respectively. The electroluminescent spectrum of each fabricated device showed peak emissions at the same two wavelengths: 508 nm and 596 nm. However, the relative intensity of 596 nm to 508 nm at those wavelengths was higher in the D-2 than in the D-1. The D-1 and D-2 devices showed maximum current efficiencies of 5.2 cd/A and 6.0 cd/A, and color coordinates of (0.31, 0.50) and (0.37, 0.48) on the Commission Internationale de I'Eclairage[CIE] chart, respectively.

Fabrication and Characterization of Red OLED on the Plastic Substrate (플라스틱 기판상에 적색 OLED 제작과 특성 연구)

  • Jeong, Jin-Cheol;Kim, Hyeong-Seok;Kim, Won-Ki;Jang, Ji-Geun
    • Journal of the Semiconductor & Display Technology
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    • v.8 no.4
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    • pp.15-19
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    • 2009
  • A high efficient organic red light emitting device with structure of DNTPD/TAPC/$Bebq_2$ :[$(pq)_2Ir(acac)$, SFC-411]/SFC-137 was fabricated on the plastic substrate, which can be applied in the fields of flexible display and illumination. In the device structure, N,N'-diphenyl-N,N'-bis-[4-(phenyl-m-tolylamino)-phenyl]-biphenyl-4,4'-diamine[DNTPD] as a hole injection layer and 1,1-bis-(di-4-tolylaminophenyl) cyclohexane [TAPC] as a hole transport were used. Bis(10-hydroxybenzo[h]quinolinato) beryllium complex [$Bebq_2$] was used as a light emitting host material. The host material, $Bebq_2$ was doubly doped with volume ratio of 7% iridium(III)bis-(2-phenylquinoline)acetylacetonate[$(pq)_2$Ir(acac)] and 3% SFC-411[red phosphor dye coded by the proprietary company]. And then, SFC-137 was used as an electron transport layer. The luminous intensity and current efficiency of the fabricated device were $22,780\;cd/m^2$ at 9V and 17.3 cd/A under $10,000\;cd/m^2$, respectively. The maximum current efficiency of the device was 22.4cd/A under $580\;cd/m^2$.

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Study on an open fuel cycle of IVG.1M research reactor operating with LEU-fuel

  • Ruslan А. Irkimbekov ;Artur S. Surayev ;Galina А. Vityuk ;Olzhas M. Zhanbolatov ;Zamanbek B. Kozhabaev;Sergey V. Bedenko ;Nima Ghal-Eh ;Alexander D. Vurim
    • Nuclear Engineering and Technology
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    • v.55 no.4
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    • pp.1439-1447
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    • 2023
  • The fuel cycle characteristics of the IVG.1M reactor were studied within the framework of the research reactor conversion program to modernize the IVG.1M reactor. Optimum use of the nuclear fuel and reactor was achieved through routine methods which included partial fuel reloading combined with scheduled maintenance operations. Since, the additional problem in planning the fuel cycle of the IVG.1M reactor was the poisoning of the beryllium parts of the core, reflector, and control system. An assessment of the residual power and composition of spent fuel is necessary for the selection and justification of the technology for its subsequent management. Computational studies were performed using the MCNP6.1 program and the neutronics model of the IVG.1M reactor. The proposed scheme of annual partial fuel reloading allows for maintaining a high reactor reactivity margin, stabilizing it within 2-4 βeff for 20 years, and achieving a burnup of 9.9-10.8 MW × day/kg U in the steady state mode of fuel reloading. Spent fuel immediately after unloading from the reactor can be placed in a transport packaging cask for shipping or safely stored in dry storage at the research reactor site.

절연절단 방식의 프로브 빔 제작

  • Hong, Pyo-Hwan;Gong, Dae-Yeong;Pyo, Dae-Seung;Lee, Jong-Hyeon;Lee, Dong-In;Kim, Bong-Hwan;Jo, Chan-Seop
    • Proceedings of the Korean Vacuum Society Conference
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    • 2013.02a
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    • pp.449-449
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    • 2013
  • 최근 반도체 소자의 집적회로는 점점 복잡해지고 있는 반면, 소자의 크기는 작아지고 있으며 그로 인해 패드의 크기가 작아지고 패드사이의 간격 또한 협소해지고 있다. 따라서 웨이퍼 단계에서 제조된 집적회로의 불량여부를 판단하기위한 검사 장비인 프로브카드(Probe Card)의 높은 집적도가 요구되고 있다. 하지만 기존의 MEMS 공법으로 제작되는 프로브 빔은 복잡한 제조 공정과 높은 생산비용, 낮은 집적도의 문제점을 가지고 있다. 본 연구에서는 이러한 문제점을 해결하기 위하여 간단한 제조 공정과 낮은 생산비용, 높은 집적도를 가지는 프로브 빔을 개발하기 위하여 절연절단 방식으로 BeCu (Beryllium-Copper) 프로브 빔을 제작하였다. 낮은 소비 전력으로 우수한 프로브 빔 어레이를 제작하기 위해서 가장 고려해야할 대상은 프로브 빔의 재료와 구조(형상)이다. 절연전단 방식으로 프로브 빔을 형성할 때 요구되는 Fusing current는 프로브 빔의 구조(형상)에 크게 영향을 받는다. 낮은 Fusing current는 소비 전력을 줄여주고, 절연절단으로 형성되는 프로브 빔의 단면(끝)을 날카롭게 하여 프로브 빔과 집적회로의 패드 간의 접촉 저항을 감소시킨다. 프로브 빔의 제작은 BeCu 박판을 빔 형태로 식각하여 제작하였으며, 실리콘 비아 홀(Via hole) 구조의 기판위에 정렬하여 soldering 공정을 통해 실리콘 기판과 BeCu 박판을 접합시켰다. 접합된 프로브 빔의 끝부분을 들어 올린 상태로 전류를 인가하여 stress free 상태로 만들어 내부 응력을 제거하였으며, BeCu 박판에 fusing current를 인가하여 BeCu 박판 프레임으로부터 제거를 하였다. 제작된 프로브 빔의 길이는 1.7 mm, 폭은 $50{\mu}m$, 두께는 $15{\mu}m$, 절단부의 단면적은 1$50{\mu}m^2$로 제작되었다. 그리고 프로브 빔의 절단부의 길이는 $50{\mu}m$ 부터 $90{\mu}m$까지 $10{\mu}m$ 증가시켜 제작되었다. 이후에 절연절단 공정에 요구되는 Fusing current를 측정하였고, 절연절단 후의 절단면의 형상을 SEM (Scanning Electron Microscope)장비를 통하여 확인하였다. 절단부의 길이가 $50{\mu}m$일 때 5.98A의 fusing current를 얻었으며, 절연절단 후 절단부 상태 또한 가장 우수했다. 본 연구에서 제안된 프로브 빔 제작 방법은 프로브카드 및 테스트 소켓(Test socket) 생산에 응용이 가능하리라 기대한다.

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Influence of Blankholding Force and Blank Diameter on the Drawability and Quality of Very Small Cylindrical Cups (극소형 원통컵의 드로잉성과 품질에 미치는 블랭크 홀딩력과 블랭크 직경의 영향)

  • Lee, K.S.;Kim, J.B.;Jung, W.J.;Kim, J.H.
    • Transactions of Materials Processing
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    • v.23 no.8
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    • pp.489-494
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    • 2014
  • Micro forming is an appropriate process to manufacture very small metal parts which can be employed in the field of electronic devices or electrically controlled mechanical systems. The purpose of the current study was to investigate the influences of both blankholding force and blank diameter for the deep drawing of very small cups. It is essential to control the blankholding force because improper force can result in defects such as wrinkles in the flange or cracks in the corner of the drawn cups. In the current study blankholding force was controlled by springs connected to the blankholder of a press die. Exchangeable bushing dies with various die-corner radii were also used. To obtain the limit drawing ratio for each working condition several sizes of circular specimens were prepared using blanking tools. Beryllium copper(C1720) alloy sheet of $50{\mu}m$ thickness was chosen for the experiments. The maximum limit drawing ratio of 2.1 was achieved experimentally for the conditions of the blankholder force(BHF)=5.3kgf and Rd=0.3mm. Both thickness and hardness along the central section of drawn cups were measured and compared for different drawing conditions. It was found that the deviation of measured data in the thickness and hardness distribution increases with increasing blankholder force and blank diameter.

Exposure Characteristics of Chemical Hazards in Metalworking Operations using an Employee Exposure Assessment Database (작업환경측정 자료를 이용한 CNC공정의 유해물질 노출 특성)

  • Lee, Jaehwan;Park, Donguk;Ha, Kwonchul
    • Journal of Korean Society of Occupational and Environmental Hygiene
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    • v.28 no.2
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    • pp.230-239
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    • 2018
  • Objective: The purpose of this study is to identify the kinds and exposure levels of health hazards in the metalworking process in relation to acute poisoning accidents caused by methanol in 2016. Methods: The number of industries, workplaces, exposed workers, regional distribution, and exposure level of health hazards in metalworking process were investigated based on employee exposure assessment database provided by KOSHA (the Korea Occupational Safety and Health Agency), which was collected from workplace hazard evaluation programs in Korea. Exposure metrics for methanol were assessed by RCR (risk characterization ratio). Results: The numbers of processes, workplaces, and exposed workers of metalworking, which include CNC (computer numerical control) were 25, 14,405, and 169,102 respectively. The numbers of samples of chemical hazards including methanol were 91,325, and it was found that workers in metalworking were exposed to 249 kinds of chemical hazards. There were 16 kinds of special controlled substances including beryllium. It is estimated that the number of workplaces involving CNC process was 2,537, and the number of exposed workers was 27,976. In CNC process, the total number of workplaces handling methanol was 36, and 298 workers were estimated to be exposed. There was no exceeded that surpassed the OEL and 49% of samples were below the limit of detection. Methanol exposure concentrations in Gyeonggido Province were statistically significantly higher than in other areas (p <0.0001). Conclusions: In the metalworking process including CNC, there is exposure to a wide variety of health hazards. There was no sample exceeding the OEL for methanol. Therefore, it is necessary to recognize the limits of the employee exposure assessment system and urgently improve measures to prevent the occurrence of events like methanol poisoning.

Radiation-induced transformation of Hafnium composition

  • Ulybkin, Alexander;Rybka, Alexander;Kovtun, Konstantin;Kutny, Vladimir;Voyevodin, Victor;Pudov, Alexey;Azhazha, Roman
    • Nuclear Engineering and Technology
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    • v.51 no.8
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    • pp.1964-1969
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    • 2019
  • The safety and efficiency of nuclear reactors largely depend on the monitoring and control of nuclear radiation. Due to the unique nuclear-physical characteristics, Hf is one of the most promising materials for the manufacturing of the control rods and the emitters of neutron detectors. It is proposed to use the Compton neutron detector with the emitter made of Hf in the In-core Instrumentation System (ICIS) for monitoring the neutron field. The main advantages of such a detector in comparison the conventional β-emission sensors are the possibility of reaching of a higher cumulative radiation dose and the absence of signal delays. The response time of the detection is extremely important when a nuclear reactor is operating near its critical operational parameters. Taking Hf as an example, the general principles for calculating the chains of materials transformation under neutron irradiation are reported. The influence of 179m1Hf on the Hf composition changing dynamics and the process of transmutants' (Ta, W) generation were determined. The effect of these processes on the absorbing properties of Hf, which inevitably predetermine the lifetime of the detector and its ability to generate a signal, is estimated.

Pulmonary Foreign Body Granulomatosis in Dental Technician

  • Chung, Sung Jun;Koo, Gun Woo;Park, Dong Won;Kwak, Hyun Jung;Yhi, Ji Young;Moon, Ji-Yong;Kim, Sang-Heon;Sohn, Jang Won;Yoon, Ho Joo;Shin, Dong Ho;Park, Sung Soo;Pyo, Ju Yeon;Oh, Young-Ha;Kim, Tae-Hyung
    • Tuberculosis and Respiratory Diseases
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    • v.78 no.4
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    • pp.445-449
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    • 2015
  • Occupational lung diseases are caused by several toxic substances including heavy metals; however, the exact pathologic mechanisms remain unknown. In the workplace, dental technicians are often exposed to heavy metals such as cobalt, nickel, or beryllium and occasionally develop occupational lung diseases. We described a case of occupational lung disease in a patient who was employed as a dental technician for over a decade. A 31-year-old, non-smoking woman presented with productive cough and shortness of breath of several weeks duration. Chest computed tomography revealed a large number of scattered, bilateral small pulmonary nodules throughout the lung field, and multiple mediastinal lymph nodes enlargement. Percutaneous needle biopsy showed multifocal small granulomas with foreign body type giant cells suggestive of heavy metals inhalation. The patient's condition improved on simple avoidance strategy for several months. This case highlighted the importance of proper workplace safety.

Bragg-curve simulation of carbon-ion beams for particle-therapy applications: A study with the GEANT4 toolkit

  • Hamad, Morad Kh.
    • Nuclear Engineering and Technology
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    • v.53 no.8
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    • pp.2767-2773
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    • 2021
  • We used the GEANT4 Monte Carlo MC Toolkit to simulate carbon ion beams incident on water, tissue, and bone, taking into account nuclear fragmentation reactions. Upon increasing the energy of the primary beam, the position of the Bragg-Peak transfers to a location deeper inside the phantom. For different materials, the peak is located at a shallower depth along the beam direction and becomes sharper with increasing electron density NZ. Subsequently, the generated depth dose of the Bragg curve is then benchmarked with experimental data from GSI in Germany. The results exhibit a reasonable correlation with GSI experimental data with an accuracy of between 0.02 and 0.08 cm, thus establishing the basis to adopt MC in heavy-ion treatment planning. The Kolmogorov-Smirnov K-S test further ascertained from a statistical point of view that the simulation data matched the experimentally measured data very well. The two-dimensional isodose contours at the entrance were compared to those around the peak position and in the tail region beyond the peak, showing that bone produces more dose, in comparison to both water and tissue, due to secondary doses. In the water, the results show that the maximum energy deposited per fragment is mainly attributed to secondary carbon ions, followed by secondary boron and beryllium. Furthermore, the number of protons produced is the highest, thus making the maximum contribution to the total dose deposition in the tail region. Finally, the associated spectra of neutrons and photons were analyzed. The mean neutron energy value was found to be 16.29 MeV, and 1.03 MeV for the secondary gamma. However, the neutron dose was found to be negligible as compared to the total dose due to their longer range.

Evaluating Activation for 50 MeV Cyclotron Irradiation Service using Monte Carlo Method and Inventory Code (50 MeV 사이클로트론 조사 서비스로 인한 방사화 평가)

  • Kim, Sangrok;Kim, Gi-sub;Heo, Jaeseung;Ahn, Yunjin
    • Journal of the Korean Society of Radiology
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    • v.15 no.4
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    • pp.415-427
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    • 2021
  • Korea Institute of Radiological and Medical Sciences has provided various beam irradiation services to researchers using a 50 MeV cyclotron beam line. In particular, since the neutron beam service uses the nuclear reaction between protons and beryllium, the possibility of activation of the irradiated sample increases by using a high current. In this study, MCNP 6.2 and FISPACT-II 4.0 were used to evaluate the possible activation during the 35 MeV 20 ㎂ neutron beam service, which is preferred by the researchers. As a result of the calculation, if the iron, copper, and tungsten samples were irradiated for more than 1 hour, long-lived radioisotopes were produced and their radioactivity exceeded the standard level for self-disposal. Under the conditions of 2 hours of daily irradiation, no activation occurred in the building materials, and the internal exposure of workers due to air activation inside the irradiation room was very insignificant. And when this air was discharged to environment, the radioactivity including this air was also satisfied the emission standard.