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장석규(Seok-Kyu Chang),주인철(In-Cheol Chu),송철화(Chul-Hwa Song) 대한기계학회 2010 대한기계학회 춘추학술대회 Vol.2010 No.11
For the development of the constitutive relations in the interfacial area transport equations, adiabatic air-water two-phase flow experiments were conducted on a 4x4 rod bundle array. A squared center subchannel was chosen for the measurement of a total 1,321 points in a full subchannel, and the axial location of measured section was placed at 44D<SUB>H</SUB> from the inlet of the bundle array. Bundle array was consisted of 16 rods with a diameter of 25.4 ㎜, a rod to rod pitch of 33.7 ㎜ and the subchannel hydraulic diameter, D<SUB>H</SUB> of 31.5 ㎜. A double-sensor optical probe with the automatic controlled traverse system was used for the measurement of flow parameters such as local void fraction, interfacial velocity, Sauter mean diameter and interfacial area concentration in a subchannel. Three data sets were acquired consisting of void fractions, about 0.05, 0.10 and 0.20 at a superficial liquid velocity, 1.60 ㎧. The detailed profiles of two-phase flow parameters in a subchannel were obtained and the phase distribution patterns according to the bubble conditions were discussed.
혼합날개가 장착된 봉다발부수로에서의 횡류유동의 광학측정 비교
장석규(Seok Kyu Chang),추연준(Yeon Jun Choo),김복득(Bok Deuk Kim),송철화(Chul Hwa Song) 대한기계학회 2008 대한기계학회 춘추학술대회 Vol.2008 No.5
The lateral crossflow on subchannels in a rod bundle array was investigated to understand the flow characteristics related to the mixing vane types on a spacer grid by using the PIV technique. For more measurement resolutions, a 5×5 rod bundle was fabricated a 2.6 times larger than the real rod bundle size in a pressurized water reactor. A rod-embedded optic array was specially designed and used for the illumination of the inner subchannels. The crossflow field in a subchannel was characterized by the type and the arrangement of the mixing vanes. At a near downstream location from the spacer grid (z/D<SUB>h</SUB>, = 1) in the case of the split type, a couple of small vortices were generated diagonally in a subchannel. On the other hand, in the case of the swirl type, there was a large elliptic vortex generated in the center of a subchannel. The measurement results were compared with the experimental results which had been performed with the LDV technique at the same test facility. The magnitudes of the flow velocity and the vorticity in PIY results were less than those in LDV measurement results. It was shown that the instantaneous flow fields in a subchannel frequently have quite different shapes from the averaged one.
추연준(Yeon-Jun Choo),장석규(Seok-Kyu Chang),김복득(Bok-Deok Kim),문상기(Sang-Ki Moon),송철화(Chul-Hwa Song) 대한기계학회 2007 대한기계학회 춘추학술대회 Vol.2007 No.5
The mixing vanes attached to the spacer grid of rod bundles are used to improve the heat transfer in heat exchanger devices by controlling the characteristics of the flow structures and turbulence. In this study, velocity patterns induced by two types of mixing vane(split and swirl vane) are measured by the PIV technique to better understand how to effect on the cross and secondary vortex flow patterns in 5×5 rod bundle simulating the fuel assembly of the nuclear reactor. A successful measurement of the lateral velocity patterns was conducted using a specially designed beam sheet generator and experimental loop at KAERI. As the result, we found that for the cross flow between subchannels, the split vane is more effective than the swirl vane, while for the secondary vortex flow in each subchannel, the swirl vane's one is larger and longer than split vane's one.
와이어 메쉬 센서를 이용한 소듐냉각고속로 37봉다발 부수로 유동 혼합의 실험적 측정
김형모(Hyungmo Kim),김석(Seok Kim),배황(Hwang Bae),고영주(Yung Joo Ko),최해섭(Hae Seob Choi),장석규(Seok-Kyu Chang),어동진(Dong-Jin Euh),이형연(Hyeong-Yeon Lee),정지영(Ji-Young Jeong) 대한기계학회 2015 대한기계학회 춘추학술대회 Vol.2015 No.11
Flow mixing measurements inside a wire-wrapped 37-rods bundle were conducted using a wire-mesh sensor with a customized design for a sodium-cooled fast reactor (SFR). To verify the flow mixing behaviors inside an SFR fuel bundle, a hexagonally arrayed 37 wire-wrapped-rods bundle has been fabricated. The experimental data obtained will be used for validating the capability of subchannel analysis codes for the SFR core thermal hydraulic design. A wiremesh sensing system was successfully developed including a tracing liquid injection system, and a post-processing method was also developed for our experiments. Experimental tests have been performed under the flow condition corresponding to 100 % flow of the prototype reactor nominal flow based on the Reynolds number. The results were compared with other experimental results by an LIF (Laser Induced Fluorescence) method, which show good agreements with each other. The uncertainty analysis including the error propagation based on the flow rates and temperatures has been evaluated to validate the experimental results.