• 제목/요약/키워드: Ion generator

검색결과 97건 처리시간 0.024초

오존-음이온 발생장치를 이용한 카네이션 생산성 향상 사례 연구 (A case study of carnation productivity improvement using a ozone-negative ion generator)

  • 송현직;이상근;윤대희;박원주;이광식;최상태
    • 한국조명전기설비학회:학술대회논문집
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    • 한국조명전기설비학회 2005년도 학술대회 논문집
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    • pp.271-273
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    • 2005
  • In order to carnation productivity improvement, ozonizer and negative ionizer has been designed and manufactured. The ozone is generated by DC positive streamer discharge and the negative ion is generated by DC negative discharge. When the ozone and negative ion are supplied growth room and farm to carnation cultivation, the carnation productivity is improved.

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Performance evaluation of nitrate removal in high TDS wet scrubber wastewater by ion exchange resin with dissolved air flotation (DAF) process

  • Kim, Bongchul;Yeo, Inseol;Park, Chan-gyu
    • Membrane and Water Treatment
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    • 제13권1호
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    • pp.1-6
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    • 2022
  • The regulations of the International Maritime Organization (IMO) have been steadily strengthened in ship emissions. Accordingly, there is a growing need for development of related technologies for the removal of contaminants that may occur during the treatment of SOx and NOx using a wet scrubber. However, this system also leads to wastewater production when the exhaust gas is scrubbed. In this research, we evaluated the performance of an ion selective resin process in accordance with scrubber wastewater discharge regulations, specifically nitrate discharge, by the IMO. Accelerated real and synthetic wastewater of wet scrubbers, contained high amounts of TDS with high nitrate, is used as feed water in lab scale systems. Furthermore, a pilot scale dissolved air flotation (DAF) using microbubble generator with ion exchange resin process was combined and developed in order to apply for the treatment of wet scrubber wastewater. The results of the present study revealed that operating conditions, such as resin property, bed volume (BV), and inlet wastewater flow rate, significantly affect the removal performance. Finally, through a pilot test, DAF with ion exchange resin process showed a noticeable improvement of the nitrate removal rate compared to the single DAF process.

Development of RF Ion Source for Neutral Beam Injector in Fusion Devices

  • 장두희;박민;김선호;정승호
    • 한국진공학회:학술대회논문집
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    • 한국진공학회 2013년도 제44회 동계 정기학술대회 초록집
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    • pp.550-551
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    • 2013
  • Large-area RF-driven ion source is being developed at Germany for the heating and current drive of ITER plasmas. Negative hydrogen (deuterium) ion sources are major components of neutral beam injection systems in future large-scale fusion experiments such as ITER and DEMO. RF ion sources for the production of positive hydrogen ions have been successfully developed at IPP (Max-Planck- Institute for Plasma Physics, Garching) for ASDEX-U and W7-AS neutral beam injection (NBI) systems. In recent, the first NBI system (NBI-1) has been developed successfully for the KSTAR. The first and second long-pulse ion sources (LPIS-1 and LPIS-2) of NBI-1 system consist of a magnetic bucket plasma generator with multi-pole cusp fields, filament heating structure, and a set of tetrode accelerators with circular apertures. There is a development plan of large-area RF ion source at KAERI to extract the positive ions, which can be used for the second NBI (NBI-2) system of KSTAR, and to extract the negative ions for future fusion devices such as ITER and K-DEMO. The large-area RF ion source consists of a driver region, including a helical antenna (6-turn copper tube with an outer diameter of 6 mm) and a discharge chamber (ceramic and/or quartz tubes with an inner diameter of 200 mm, a height of 150 mm, and a thickness of 8 mm), and an expansion region (magnetic bucket of prototype LPIS in the KAERI). RF power can be transferred up to 10 kW with a fixed frequency of 2 MHz through a matching circuit (auto- and manual-matching apparatus). Argon gas is commonly injected to the initial ignition of RF plasma discharge, and then hydrogen gas instead of argon gas is finally injected for the RF plasma sustainment. The uniformities of plasma density and electron temperature at the lowest area of expansion region (a distance of 300 mm from the driver region) are measured by using two electrostatic probes in the directions of short- and long-dimension of expansion region.

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Tungsten-188/Rhenium-188 발생기의 정도관리 (Quality Control of Tungsten-188/Rhenium-188 Generator)

  • 장영수;정재민;이동수;정준기;이명철
    • 대한핵의학회지
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    • 제32권5호
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    • pp.425-432
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    • 1998
  • 목적: Re-188을 치료용 방사성핵종으로 사용하기 위하여 W-188/Re-188 발생기를 병원 내에서 사용할 때 발생기 정도관리에 관한 실험을 실시하였다. 대상 및 방법: 알루미나 컬럼을 사용한 W-188/Re-188 발생기를 대상으로 하여 약 300일간 정도관리 실험을 하였다. 생리식염수 20 ml을 사용하여 발생기로부터 Re-188을 용출한 후 Re-188 용출액의 방사화학적 순도를 보기 위하여 박층크로마토그라피를 실시하고 감마에너지 스펙트럼을 측정하였다. 발생기의 화학순도실험으로 알루미늄의 용출을 알루미늄 이온 확인 키트를 사용하여 확인하였다. Re-188 용출액에 불순물로 있을 수 있는 모핵종 W-188은 감마에너지 스펙트럼으로 확인하였다. Re-188 용출액의 pH를 측정하였으며 발열원 검사로 LAL 검사를 시행하였다. Re-188 용출액을 이온교환컬럼을 사용하여 농축하였다. 결과: 용출분획의 Re-188 방사능양을 전체 용출한 방사능 양에 대한 백분율로 계산하였을 때 $5{\sim}10 ml$ 사이의 용출액이 전체 방사능양의 약 76%를 차지하였다. W-188의 방사능에 대한 Re-188 용출액의 방사능비는 270일간 평균 $67.4{\pm}7.0%$였으며, 용출 간격을 3일 이상 두었을 때가 높았다. 용출한 Re-188의 방사화학적 순도는 거의 100%였으며, 감마에너지 스펙트럼상에서 정점은 $135{\sim}188 keV$ 사이에 나타났다. 알루미늄 유출은 없었으며, W-188의 유출 역시 없었다. Re-188 용출액의 pH는 3이었으며, 발열성물질은 검출되지 않았다. 이온교환컬럼을 사용하여 Re-188을 농축하였을 때 회수율은 87%였다. 결론: 이 연구에서 사용한 W-188/Re-188 발생기는 각종 임상연구에 사용하기에 충분한 수준의 정도관리 결과를 나타내었다.

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와동 발생기 높이 변화에 대한 경계층 내의 유동장과 온도장에 관한 실험적 연구 (The Experimental Study of the Interaction Between the Flow rind Temperature Field and a Boundary Layer Due to a Variety of tole Height of a Vortex Generator)

  • 권수인;양장식;이기백
    • 대한기계학회논문집B
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    • 제26권1호
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    • pp.82-93
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    • 2002
  • The effects of the interaction between the flow and temperature field and a boundary layer due to a variety of the height of a vortex generator are experimentally investigated. The test facility consists of a boundary-layer wind tunnel with the vortex generator protruding from the bottom surface. In order to control the strength of the longitudinal vortices, the angle of attack and the spacing distance of the vortex generator are 20 degree and 40 mm, respectively. The height of the vortex generator (H) is 15 mm, 20 mm and 30 mm and the cord length of it is 50 mm. Three-component mean velocity measurements are made using a 5-hole probe system and the surface temperature distribution is measured by the hue capturing method using thermochromatic liquid crystals. By using the method mentioned above, the following conclusions are obtained from the present experiment. The boundary layer is thinned in the downwash region where the strong downflow and the lateral outflow of the boundary layer fluid occur and thickened in the upwash re,3ion where the longitudinal vortex sweeps low momentum fluid away from the bottom surface. In case that the height of the vortex generator increases, the averaged circulation and the maximum vorticity of the vortex pair decrease. The contours of the non-dimensional temperature show the similar trends fur all the cases (H=15 mm, 20 mm and 30 mm). The peak augmentation of the distribution of the local non-dimensional temperature occurs in the downwash region near the point of minimum boundary-layer thickness.

고전압 임펄스에 의한 스케일 제어 (Control of scale formation using high voltage impulse)

  • 양선희;장인성
    • 한국산학기술학회논문지
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    • 제16권3호
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    • pp.2301-2307
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    • 2015
  • 본 연구에서는 산업용수의 처리 및 운용 과정에서 중요한 문제점으로 지목되고 있는 탄산칼슘에 의한 스케일 형성을 제어하기 위해 고전압 임펄스 (High Voltage Impulse, HVI) 기술의 활용 가능성을 평가하고자 하였다. 전원부, 고전압발생부, 축전기, 스위치 및 임펄스발생기로 구성된 HVI를 제작하여 17kV의 고전압 펄스를 생성시켰다. 반응조에 $Ca^{2+}$을 포함하고 있는 인공 시료를 투입한 후 HVI를 인가하였다. HVI 접촉시간 5분 후에는 $Ca^{2+}$ 초기값의 3.0% 가량만 감소하였으나, 접촉시간 60분 후에는 약 13.7% 가량 감소하였다. HVI 인가로 인해 용액의 온도와 pH는 증가하였고 전기전도도는 탄산칼슘 석출로 인해 감소하는 것을 확인하였다. 칼슘 이온의 감소가 충분하지는 않았지만 전계의 세기 및 접촉시간에 따른 제거율에 간한 구체적인 정보가 얻어진다면, HVI 기술을 적용하여 $Ca^{2+}$ 이온을 탄산칼슘으로 미리 석출시켜 제거하는 연수화 (softening) 공정이나 탈염 기술로 활용할 수 있는 가능성을 확인하였다.

Preliminary study for the development of radiation safety evaluation methodology for industrial kV-rated radiation generator facilities

  • Hye Sung Park ;Na Hye Kwon ;Sang Rok Kim ;Hwidong Yoo;Jin Sung Kim ;Sang Hyoun Choi;Dong Wook Kim
    • Nuclear Engineering and Technology
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    • 제55권10호
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    • pp.3854-3859
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    • 2023
  • Background: This study aims to develop an evaluator that can quickly and accurately evaluate the shielding of low-energy industrial radiation generators. Methods: We used PyQt to develop a graphical user interface (GUI)-based program and employed the calculation methodology reported in the National Council on Radiation Protection and Measurements (NCRP)-49 for shielding calculations. We gathered the necessary factors for shielding evaluation using two libraries designed for Python, pandas and NumPy, and processed them into a database. We verified the effectiveness of the proposed program by comparing the results with those from safety reports of six domestic facilities. Results: After verifying the effectiveness of the program using the NCRP-49 example, we obtained an average error rate of 1.73%. When comparing the facility safety report and results obtained using the program, we found that the error rate was between 1.09% and 6.51%. However, facilities that did not use a defined shielding methodology were underestimated by 31.82% compared with the program (the final barrier thickness satisfied the shielding standard). Conclusion: The developed program provides a fast and accurate shielding evaluation that can assist personnel that work in radiation generator facilities and government officials in reviewing safety.

Development of Large-Area RF Ion Source for Neutral Beam Injector in Fusion Devices

  • Chang, Doo-Hee;Jeong, Seung Ho;Kim, Tae-Seong;Park, Min;Lee, Kwang Won;In, Sang Ryul
    • 한국진공학회:학술대회논문집
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    • 한국진공학회 2013년도 제45회 하계 정기학술대회 초록집
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    • pp.179.2-179.2
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    • 2013
  • A large-area RF-driven ion source is being developed at Germany for the heating and current drive of ITER device. Negative hydrogen ion sources are major components of neutral beam injection (NBI) systems in future large-scale fusion experiments such as ITER and DEMO. The RF sources for the production of positive hydrogen ions have been successfully developed at IPP (Max-Planck-Institute for Plasma Physics), Garching, for the ASDEX-U and W7-AS neutral beam heating systems. Ion sources of the first NBI system (NBI-1) for the KSTAR tokamak have been developed successfully with a bucket plasma generator based on the filament arc discharge, which have contributed to achieve a good plasma performance such as 15 sec H-mode operation with an injection of 3.5 MW NB power. There is a development plan of RF ion source at the KAERI to extract the positive ions, which can be used for the second NBI system (NBI-2) of the KSTAR and to extract the negative ions for future fusion devices such as Fusion Neutron Source and Korea-DEMO. The development progresses of RF ion source at the KAERI are described in this presentation.

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차세대 군용전원용 500W급 마이크로 터빈 발전기 시스템 설계 (Design of a 500W Class Micro Turbine Generator System as a Next Generation Military Power Source)

  • 최상규;최범석;한용식;우병철;송인혁;민성기;임진식
    • 한국군사과학기술학회지
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    • 제14권6호
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    • pp.1192-1197
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    • 2011
  • Recent developments of small-size unmanned or manned mobile systems such as autonomous robots, exoskeleton or armored suits, micro air vehicles, and unmanned armored vehicles require long-lasting independent power sources of high energy and power density to support the systems' operation for up to 72 hours in the fields. Chemical batteries such as Ni-MH, Li-Ion, the current primary power sources for mobile devices, however, are not capable of providing enough power and energy density for the next generation high power mobile machines. For this reason, KIMM along with KERI and KIMS has been carrying out a 500W MTG development project under the DAPA's "Next generation military power source R&D program" since 2009. In this paper, a design process for a 500W MTG system currently being developed at KIMM is briefly described and the technical issues related to its development are addressed.

Preliminary Study on Separation of Germanium and Gallium for Development of a 68Ge/68Ga Generator

  • Lee, Heung Nae;Kim, Sang Wook;Park, Jeong Hoon;Kim, Injong;Yang, Seung Dae;Hur, Min Goo
    • 방사선산업학회지
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    • 제5권2호
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    • pp.101-106
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    • 2011
  • The separation of germanium and gallium ion with metal oxide was introduced into the development of $^{68}Ge/^{68}Ga$ generator. Germanium and gallium within mixed solution were respectively separated by using a liquid-liquid extraction and a column chromatographic method. The separation of Ge within high concentrated hydrochloric and sulfuric acid was conducted by the extraction to $CCl_4$ and the back-extraction to 0.05 M HCl. An optimum condition of the extraction by $CCl_4$ was in 5~7 M HCl and efficiency was around 80%. The gallium was selectively separated by using $Al_2O_3$ among metal oxides as sorbents from the mixed solution in 0.04~0.10 M HCl condition.