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PIV Measurement of Velocity Profile in the 1/8 Scale CANDU6 Moderator Circulation Test
김형태,서한,차재은,방인철,Kim, Hyoung Tae,Seo, Han,Chan, Jae Eun,Bang, In Cheol The Korean Society of Visualization 2014 한국가시화정보학회지 Vol.12 No.1
The Korea Atomic Energy Research Institute (KAERI) has a scaled-down moderator test program to simulate the CANDU6 moderator circulation phenomena during steady state operation and accident conditions. In the present work a preliminary experiment using a 1/8 scaled-down moderator tank has been performed to identify the potential problems of the flow visualization and measurement in the scaled-down moderator test facility. With a transparent moderator tank model, a velocity field is measured with a Particle Image Velocimetry (PIV) technique under an isothermal state. The flow patterns from the inlet nozzles to the top region of the tank are investigated using PIV for a 1/8 scale moderator tank.
나노유체 : 유체 내 전기선폭발법으로 제조된 금속 기반 나노유체를 이용한 핵비등 열전달 증진
박은주 ( Eunju Park ),방인철 ( In Cheol Bang ),박형욱 ( Hyung Wook Park ) 한국액체미립화학회 2012 한국액체미립화학회 학술강연회 논문집 Vol.2012 No.-
Nanofluids are functional suspensions containing nano-sized particles. Nanofluids have been drawing the attention as heat transfer fluid for enhancement of the critical heat flux. The enhancement of CHF contributes to increase the safety margin of the thermal system. The CHF enhancement is explained by changing the morphology of the heated surface during pool boiling. It is dependent on various factors as follows: materials, particle concentration and size, and dispersibility. In this study, the water-based Ag, CuO, and Al2O3 nanofluids were produced by the electrical explosion of wire in liquids. We have performed pool boiling experiments to characterize the CHF enhancement of the produced Ag, CuO, and Al2O3 nanofluids.
원자력발전소 피동 노내 냉각계통 적용을 위한 유압 제어봉 구동시스템 설계
김인국(In Guk Kim),방인철(In Cheol Bang) 대한기계학회 2018 대한기계학회 춘추학술대회 Vol.2018 No.12
To enhance the safety of the nuclear power plants, a passive in-core cooling system (PINCs) is currently being studied for the various reactor types such as PWR, SMR, Gen. IV reactors in UNIST. A PINCs consists of hybrid control rod assemblies, a hydraulic control rod drive mechanism, and a natural circulation loop to remove the decay heat from the nuclear fuels. In PINCs, one of the key elements is the hydraulically driven rod control system that is being studied for their various benefits, including a) ability to be in-vessel control, b) short length of the control rods, and c) safe reactor shutdown. In this paper, a novel hydraulic rod control system was designed and tested. The tests of the hydraulic rod control system with 4-hybrid control rod were conducted with the different weight and geometry. The theoretical models of the steady flow and transient behavior were driven by the force-induced patterned geometry of the cylinder. The experimental results showed that the position of the hydraulic system with control rod was well predicted by the theoretical model within ±8.6%. Finally, this study shows the unique feature of the hydraulically driven system and its behavioral characteristics.
나노유체 : 나노유체를 활용한 APR 1400 부수로 벤치마크 해석
이민호 ( Min Ho Lee ),방인철 ( In Cheol Bang ) 한국액체미립화학회 2015 한국액체미립화학회 학술강연회 논문집 Vol.2015 No.-
In case of pressurized water reactor, thermal conductivity of coolant is crucial factor for improvement of performance and safety of nuclear power plants. In this report, to enhance thermal conductivity of coolant, nanofluid was used. nanofluid is fluid having particles which have scale of nanometer, called nanoparticles. Silicon carbide, aluminum oxide, and graphene oxide have higher thermal conductivity than pure water. Moreover, they have not too big cross-section with neutron, especially thermal. Over 0.1 % of volume fraction of nanoparticle can make conspicuous difference with pure water. In the present study, three nanoparticles, such as SiC, aluminum oxide, and grapheme oxide, were used as nanofluid to show the effect of thermal conductivity. The volume fraction of nanoparticle was 0.2 % 0.5 %, 1.0 %, and 2.0 %. Thermal conductivity and viscosity of nanofluids were measured by KD2PRO and SV-10 respectively. The measurement data of thermal conductivity and viscosity was applied in the MATRA and CFD APR 1400 analysis. As anticipated, relative to pure water, thermal conductivity of nanofluid was increased and viscosity of nanofluid was also increased. But it was not effective as expectation. Due to lowered specific heat of nanofluid, overall coolant bulk temperature was increased and DNBR was decreased and these tendency was deepened with volume fraction of nanoparticle. CFD and MATRA show similar result