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단층진단법을 이용한 축대칭 부분예혼합 화염의 자발광 스펙트럼 해석에 관한 연구
하광순,최상민,Ha, Kwang-Soon,Choi, Sang-Min 대한기계학회 2000 大韓機械學會論文集B Vol.24 No.6
Visible spectral characteristics of cross-sectional emissions from a partially premixed methane/air and propane/air flames have been investigated. An optical train with a two-axis scanning mirror system was used to record line-of-sight emission spectra from 354nm to 618nm, and inversion technique was adapted to obtain cross-sectional emission spectra. By analyzing the reconstructed emission spectra, cross-sectional intensities of CH and $C_2$ radicals were separated from the background emissions. The blue flame edge and yellow flame edge were also obtained by image processing technique for edge detection with color photograph of flame. These edges were compared with radial distributions of CH, $C_2$ radicals and background emissions. The CH radicals were observed at blue flame edge. The background emissions were generated by soot precursor at upstream of flame and by soot at downstream of flame. The $C_2$ radicals in propane/air flame were observed more than those in methane/air flame.
벽면의 가열조건에 따른 반구형 소형 간극 내에서의 냉각과정에 관한 실험적 연구
하광순(Kwang-Soon Ha),박래준(Rae-Joon Park),김상백(Sang-Baik Kim) 대한기계학회 2002 대한기계학회 춘추학술대회 Vol.2002 No.5
Quenching phenomena of hemispherical surfaces with narrow gaps with respect to the wall heating<br/> conditions have been investigated experimentally. Experiments employed test sections having 1 and 2 mm in<br/> gap thickness and 1atm in system pressure. From interpretations of the temperature and heat flux history, it<br/> was found that the quenching process was changed by wall heating conditions. If external wall was not heated,<br/> then the coolant was penetrated along the cooled external wall. However, if both internal and external wall<br/> were heated, then the quenching phenomena were more complicated as the gap thickness decreased. All<br/> quenching processes were propagated from lower to upper regions of the both internal and external walls. The<br/> quenching scenario of the hemispherical downward facing surface with narrow gap has been suggested.
하광순(Kwang Soon Ha),김종태(Jongtae Kim),구홍두(Hong Doo Koo) 대한기계학회 2009 대한기계학회 춘추학술대회 Vol.2009 No.5
An auto-door hinge, which is one of the automatic door-closing apparatuses, has been widely used to prevent fire propagations in living or commercial buildings. The auto-door hinge consists of a spring to accumulate power for closing a door and an oil damper to control door-closing velocity. To predict and optimize the temporal door behavior during the door-closing period, the auto-door closing system was modeled as a second order-damping system. And a damping coefficient of the oil damper was also theoretically modeled by analyzing Newtonian, incompressible, viscous flow through an oil passage between a oil control rod and a oil piston body. The temporal door behaviors during the door-closing period were predicted with respect to the gap distance of the oil passage, oil viscosity, and pre-compressing of the spring.
소형 비가열 실험을 이용한 원자로용기 외벽냉각시 용기와 단열재 사이의 자연순환 이상유동에 관한 연구
하광순(Kwang-Soon Ha),박래준(Rae-Joon Park),조영로(Young-Rho Cho),김상백(Sang-Baik Kim),김희동(Hee-Dong Kim) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.4
A 1/21.6 scaled non-heating experimental facility was prepared utilizing the results of a scaling analysis to simulate the APR1400 reactor and insulation system. The behaviors of the air bubble-induced two-phase natural circulation flow in the insulation gap were observed, and the liquid mass flow rates driven by natural circulation loop were measured by varying the injected air flow rate and distribution. As the injected air flow rates increased, the natural circulation flow rates also increased. Both the longitudinal and the latitudinal distributions of the injected air affected the natural circulation flow rates, especially, the longitudinal effect is more larger.
원자로용기 외벽냉각시 용기와 단열재 사이의 자연순환 이상유동에 관한 실험적 연구
하광순(Kwang-Soon Ha),박래준(Rae-Joon Park),김환열(Hwan-Yeol Kim),김상백(Sang-Baik Kim),김희동(Hee-Dong Kim) 대한기계학회 2003 대한기계학회 춘추학술대회 Vol.2003 No.4
An 1/21.6 scaled experimental facility was prepared utilizing the results of a scaling analysis to simulate the APR1400 reactor and insulation system. The behaviors of the boiling-induced two-phase natural circulation flow in the insulation gap were observed, and the liquid mass flow rates driven by natural circulation loop were measured by varying the wall heat flux, upper exit slot area and configuration. And non-heating experiments have also been performed and discussed to certify the hydraulic similarity of the heating experiments by injecting air equivalent to the steam generated in the heating experimental condition
하광순(Kwang-Soon Ha),김재철(Jae-Cheol Kim),박래준(Rae-Joon Park),김상백(Sang-Baik Kim),홍성완(Seong-Wan Hong) 대한기계학회 2007 대한기계학회 춘추학술대회 Vol.2007 No.5
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.
원자력발전소 핵분열생성물 거동 해석을 위한 에어로졸 관성 침착 모델의 개발과 검증
윤철(Churl Yoon),하광순(Kwang Soon Ha),임홍식(Hong Sik Lim) 대한기계학회 2013 대한기계학회 춘추학술대회 Vol.2013 No.12
Prediction and estimation of the radioactive fission product release from a NPP (Nuclear Power Plant) to the environment is one of the major concerns in the field of severe accidents. Because a relatively small amount of radioactive fission products(FP) could be released into the environment during the postulated accident conditions, behavior analyses of the fission products circulating in the primary coolant loop and in the containment are major consideration factors for safety evaluation. The multi-component and multi-sectional analysis module of aerosol fission products has been developed based on the MAEROS model(F. Gelbard, 1988), and the aerosol transport model has been developed and verified. Due to the existence of carrier gas flows, aerosol fission products would deposited to the surrounding walls more when the flow goes through a bend. To evaluate this phenomena, an inertial deposition model has been developed based on the VICTORIA 2.0 code. The implemented inertial deposition model was successfully validated against the TRANSAT separated effect tests performed at the Cadarache laboratories in France.
원자로용기 외벽냉각시 원자로공동에서 이상유동 자연순환 해석
박래준(Rae-Joon Park),하광순(Kwang-Soon Ha),김상백(Sang-Baik Kim),김희동(Hee-Dong Kim) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.4
As part of study on thermal hydraulic behavior in the reactor cavity under external vessel cooling in the APR (Advanced Power Reactor) 1400, one dimensional two phase flow of steady state in the reactor cavity have been analyzed to investigate a coolant circulation mass flow rate in the annulus region between the reactor vessel and the insulation material using the RELAP5/MOD3 computer code. The RELAP5/MOD3 results have shown that a two phase natural circulation flow of 300 ? 600 kg/s is generated in the annulus region between the reactor vessel and the insulation material when the external vessel cooling has been applied in the APR 1400. An increase in the heat flux of the inner vessel leads to an increase of the coolant mass flow rate. An increase in the coolant outlet area leads to an increase in the coolant circulation mass flow rate, but the coolant inlet area does not effective on the coolant circulation mass flow rate. The change of the lower coolant outlet to a lower position affects the coolant circulation mass flow rate, but the variation trend is not consistent.
공간 주파수 응답의 기저 합성에 의한 원전 주요재료 내부 결함의 초음파 영상신호 개선
구길모(Kil-Mo Koo),하광순(Kwang-Soon Ha),조영로(Young-Ro Cho),김상백(Sang-Baik Kim),강희영(Hee-Young Kang) 대한기계학회 2002 대한기계학회 춘추학술대회 Vol.2002 No.5
In this paper, we have studied the images which have been reconstructed by using combination of images<br/> acquired by the variation of operating frequency. When inner images have been reconstructed, they have been<br/> superposed by the surface state effect. In this case, the images of the phase object can be enhanced by the<br/> contrast of inner images. In this experiment, there are two kinds of specimens, one is a reference block having<br/> 1/4T, 1/2T, 3/4T side drilled holes as main run piping material of the steam generator in NPPs and the another<br/> is a part of a hemisphere type specimen having about 1-2 ㎜ distance gap. It has been shown that the two<br/> results of defect shapes have better than before in this processing and phase contrast grow about twice. And<br/> we have constructed the acoustic microscope by using a quadrature detector that enables to acquire the<br/> amplitude and phase of the reflected signal simultaneously. Further more we have studied the reconstruction<br/> method of the amplitude and phase images and the enhancement method of the defect images' contrast.
원자로용기 외벽냉각시 형성되는 자연순환 이상유동의 1차원 해석 연구
김재철(Jae-Cheol Kim),하광순(Kwang-Soon Ha),박래준(Rae-Joon Park),김상백(Sang-Baik Kim),김신(Sin Kim) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.6
During a severe accident in a nuclear power plant, the decay heat from a molten corium in a reactor vessel should be removed to maintain the integrity of the reactor vessel. For this purpose, the external reactor vessel cooling(ERVC) strategy has been suggested. HERMES-HALF experiments have been conducted in KAERI to evaluate two-phase natural circulation flow occurred in the annular gap between the reactor vessel and the insulation. The facility was scaled down as a half size of the APR1400 reactor vessel, and the air-water flow was used in a working fluid. In this study, the 1-D loop analysis of the HERMES-HALF experiments was carried out using the one-dimensional drift flux model. With varying some parameters, which were inlet/outlet areas, shape factors, and gas injection rates, the calculated circulation mass flow rates were compared with experimental data.