• 제목/요약/키워드: 김상백

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비지도학습 기반 자동 특허문서 분류 시스템 (Unsupervised learning-based automated patent document classification system)

  • 김상백;김지호;이홍철
    • 한국컴퓨터정보학회:학술대회논문집
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    • 한국컴퓨터정보학회 2021년도 제64차 하계학술대회논문집 29권2호
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    • pp.421-422
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    • 2021
  • 국내·외 기업들의 기술을 보호하고자 매년 100만개의 특허가 출원되고 있다. 등록된 특허 수가 증가될수록 전문가의 판단만으로 원하는 기술 분야의 유효한 특허문서를 선별하는 것은 효율적이지 않으며 객관적인 결과를 기대하기 어려워진다. 본 연구에서는 유효 특허문서 분류 정확성과 전문가의 업무 효율성을 제고하고자 비지도학습 모델인 잠재 디리클레 할당 알고리즘(Latent Dirichlet Allocation, LDA)과 딥러닝을 활용하여 자동 특허문서 분류 시스템을 제안하고자 한다.

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공기와 물의 이상 자연순환 유동의 1 차원 해석 (One-Dimensional Analysis of Air-Water Two Phase Natural Circulation Flow)

  • 박래준;하광순;김재철;홍성완;김상백
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2007년도 춘계학술대회B
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    • pp.2626-2631
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    • 2007
  • Air-water two phase natural circulation flow in the T-HERMES (Thermo-Hydraulic Evaluation of Reactor cooling Mechanism by External Self-induced flow)-1D experiment has been evaluated to verify and evaluate the experimental results by using the RELAP5/MOD3 computer code. The RELAP5 results have shown that an increase in the coolant inlet area leads to an increase in the water circulation mass flow rate. However, the water outlet area does not effective on the water circulation mass flow rate. As the coolant outlet moves to a lower position, the water circulation mass flow rate decreases. The water level is not effective on the water circulation mass flow rate. As the height increases in the air injection part, the void fraction increases. However, the void fraction in the upper part of the air injector maintains a constant value. An increase in the air injection mass flow rate leads to an increase in the local void fraction, but it is not effective on the local pressure.

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사각 단면 채널에서의 자연순환 유동에 관한 연구 (Natural Circulation Flow Investigation in a Rectangular Channel)

  • 하광순;김재철;박래준;김상백;홍성완
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2007년도 춘계학술대회B
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    • pp.3086-3091
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    • 2007
  • When a molten corium is relocated in a lower head of a reactor vessel, the ERVC (External Reactor Vessel Cooling) system is actuated as coolant is supplied into a reactor cavity to remove a decay heat from the molten corium during a severe accident. To achieve this severe accident mitigation strategy, the two-phase natural circulation flow in the annular gap between the external reactor vessel and the insulation should be formed sufficiently by designing the coolant inlet/outlet area and gap size adequately on the insulation device. For this reason, one-dimensional natural circulation flow tests were conducted to estimate the natural circulation flow under the ERVC condition of APR1400. The experimental facility is one-dimensional and scaled-down as the half height and 1/238 rectangular channel area of the APR1400 reactor vessel. As the water inlet area increased, the natural circulation mass flow rate asymptotically increased, that is, it converged at a specific value. And the circulation mass flow rate also increased as the outlet area, injected air flow rate, and outlet height increased. But the circulation mass flow rate was not changed along with the external water level variation if the water level was higher than the outlet height.

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중대사고 조건에서 회로 모델링 모의시험을 통한 새로운 신호분기의 설계 (Design for a New Signals Analyzer through the Circuit Modeling Simulation under Severe Accident Conditions)

  • 구길모;김상백;김희동;강희영;강해용
    • 대한전자공학회:학술대회논문집
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    • 대한전자공학회 2005년도 추계종합학술대회
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    • pp.171-174
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    • 2005
  • The circuit simulation analysis and diagnosis methods are used to instruments in detail when they give apparently abnormal readings. In this paper, a new simulator through an analysis of the important circuits modeling under severe accident conditions has been designed, the realization for a body work instead of the two sorts of the Labview & Pspice as an one order command in the Labview program. The program can be shown the output graph form the circuit modeling as an order commend. The procedure for the simulator design was divided into two design steps, of which the first step was the diagnosis methods, the second step was the circuit simulator for the signal processing tool. It has three main functions which are a signal processing tool, an accident management tool, and an additional guide from the initial screen.

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PMD용 금속화약(ZPP) 제조 및 특성분석 (The Characteristics Analysis and Manufacture of Metal Explosive(ZPP) on PMD)

  • 심정섭;김상백;안길환;김준형
    • 한국추진공학회지
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    • 제20권3호
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    • pp.25-31
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    • 2016
  • 본 연구에서는 항공우주, 유도탄, 자동화 산업에 널리 적용되는 금속복합화약 ZPP(Zirconium Potassium Perchlorate)의 제조공정 과 특성평가를 고찰하였다. 기본적으로 PMD에 사용되는 고체 점화제는 금속연료와 산화제 그리고 유기 고분자물질(결합재)로 구성되며, 이들 원료들을 균질하게 혼합하기 위하여 precipitation process를 사용하였다. 원료 물질의 특성 및 열적 반응 해석을 통한 최적 조성비를 설계하였으며, 이들의 입도, 형상, 열량 분석 등의 특성 평가를 수행하여 결과를 비교하였다.

중대사고 시 차세대 원전 관통부의 건전성에 대한 원자로 용기 외벽 냉각의 영향 평가 실험 연구 (An Experimental Study on Effect of External Vessel Cooling for the Penetration Integrity in the KNGR during a Severe Accident)

  • 강경호;박래준;김종태;김상백;이기영;박종균
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 춘계학술대회논문집D
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    • pp.127-132
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    • 2001
  • An experimental study on penetration integrity of the reactor vessel has been performed under external vessel cooling during a core melt accident. In this study a series of experiments are performed for the verification of the effects of coolant in the annulus between the ICI(In-Core Instrumentation) nozzle and the thimble tube and also the effects of external vessel cooling on the integrity of the penetration using the test section including only one penetration and $Al_{2}O_{3}$ melt as a corium simulant. The experimental results have shown that penetration is more damaged in the case of no external vessel cooling compared with the case of external vessel cooling. It is preliminarily concluded that the external vessel cooling is very effective measure for the improvement of the penetration integrity. Also it is confirmed from the experimental results that the coolant in the annulus reduces the melt penetration distance through the annulus and enhance the integrity of the reactor vessel penetration in the end.

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상온에서 $1100^{\circ}C$까지 온도변화에 따른 콘크리트의 열물성 측정치 (Measured data of thermophysical properties of concrete for a temperature range of $20^{\circ}C$ to $1100^{\circ}C$)

  • 신기열;정모;김상백;김종철
    • 대한기계학회논문집B
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    • 제22권5호
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    • pp.596-606
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    • 1998
  • Thermophysical properties and the compressive strength of concrete used in nuclear power plants in Korea were measured. The chemical composition of the concrete was also analyzed. The measured thermophysical properties include the density, the thermal conductivity, the thermal diffusivity and the specific heat for a wide temperature range of 20.deg. C to 1100.deg. C. The chemical composition of Korean concrete is similar to that of US basaltic concrete and the thermophysical properties are strongly temperature dependent. The density, the conductivity and the diffusivity decrease with an increase in temperature, and particularly the conductivity and the diffusivity are a 50-perdent decrease at 900.deg. C as compared with these values at room temperature. The specific heat increases until 500.deg. C, decreases from 700.deg. C to 900 .deg. C, and then increases again when temperature is above 900.deg. C. The measurement beyond 1100.deg. C is not acceptably accurate because the concrete decomposes to a liquid phase from a solid phase at that temperature. The results of this study can be applied, for example, to an analysis of the molten core-concrete interaction (MCCI) phenomenon of concrete structures at high temperature will also require those property data, especially for high temperature ranges.

원자로 가상사고시(노심) 용융물 고압 분출 모의 실험 연구 (Simulated Experiments on High Pressure Melt Ejection in the Reactor Cavity During Severe Accident)

  • 정한원;김도형;이규정;김상백;박래준;김희동
    • 대한기계학회논문집B
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    • 제24권11호
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    • pp.1447-1456
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    • 2000
  • Simulated experiments of high pressure melt ejection(HPME) are performed to measure the released fraction of corium simulant from the French type PWR cavity. The experiments are carried out on a 1/20th linear scaled model of the Ulchin 1&2 cavity. Water or woods metal and nitrogen is used as simulant of molten corium and steam, respectively. Experimental parameters are water mass, annulus area and breach size. It is shown that only breach size effects is very important while the mass and the annulus area do not affect the released fraction. It is found that the liquid film transport is much more dominant mechanism than the entrainment droplet transport, especially in linear scale down simulated HPME experiment.

Sludge를 이용한 자기 연마재 개발 (Development of the Magnetic Abrasive Using Sludge)

  • 김희남;윤여권;김상백;최희성;안효종
    • 한국안전학회지
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    • 제19권2호
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    • pp.6-10
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    • 2004
  • The magnetic polishing is the useful method to finish using magnetic power of magnet. This method is one of precision polishing techniques and has an aim of the clean technology using for the pure of gas and inside of the clean pipe for transportation. The magnetic abrasive polishing method is not so common for machine that it tis not spreaded widely. There are rarely researcher in this field because of non-effectiveness of magnetic abrasive. Therefore, in ths paper deals with development of the magnetic abrasive using sludge. In this development, abrasive grain WA and GC used to resin bond fabricated low temperature. And magnetic material was fabricated from the sludge which were crused into 200 mesh and average diameter ${\o}$1.2mm ball type. The XRD analysis result show that only WA and GC abrasive and sludge crystal peaks detected which explains resin bond was not any more chemical reaction. From SEM analysis it tis found that WA and GC abrasive and sludge were stron bonding with each other by bond.