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차재은(Jae-Eun Cha),김희령(Hee-Reyoung Kim),김종만(Jong-Man Kim),남호윤(Ho-Yoon Nam),김성오(Sung-O Kim),김병호(Byung-Ho Kim) 대한기계학회 2007 대한기계학회 춘추학술대회 Vol.2007 No.5
The magnetohydrodynamic(MHD) pressure drop along a liquid sodium flow was measured in a rectangular duct under a transverse magnetic field. The test section was made of a 3 ㎜ thick stainless steel SUS304 with a 74×5 ㎟ rectangular flow channel. The range of experimental parameters was roughly B = 0~0.18T and U=0~0.9㎧ at around 200℃. The differential pressure was measured by a diaphragm seal-type pressure transmitter filled with a high temperature silicon oil within 0.1㎫. The experimental results show a similar pressure drop with the theoretical estimation according to a change of the flow velocity and the magnetic field.
차재은(Jae-Eun Cha),김태준(Tae-Joon Kim),김종만(Jong-Man Kim),김성오(Sung-O Kim),김병호(Byung-Ho Kim) 대한기계학회 2007 대한기계학회 춘추학술대회 Vol.2007 No.10
The flow-field information is very important for the safety analysis of a liquid-metal fast reactor. Local velocity measurements are still challenging in a liquid sodium flow since the widely used methods such as LDV or Hot-wire are not applicable owing to an opaqueness and an endurance of high temperature. The local velocity probe has been continuously developed to apply it to the measurement of a liquid sodium flow for the study of the reactor thermal phenomena. Local velocity probes were newly designed and fabricated to investigate several problems for a local flow measurement. The preliminary performance test of the probe was conducted in a sodium facility. The measured emf shows the same order as the calculated value with an estimated sensitivity in the range of a mean velocity from 0 to 1.7m/s at around 160℃.
소듐냉각고속로 KALIMER-600의 물모의 가시화 실험
차재은(Jae-Eun Cha),이상혁(Sang-Hyuk Lee),김성오(Seong-O Kim) 대한기계학회 2009 대한기계학회 춘추학술대회 Vol.2009 No.11
KAERI has been developing a KALIMER-600 which is a pool-type sodium-cooled fast reactor with a 600MWe electric generation capacity. For a SFR development, one of the main topics is an enhancement of the reactor system safety. Therefore, we are designing the large sodium experimental facility to evaluate the reactor safety and component performance. Before a large sodium test, we are going to conduct a scaled water model test due to several benefits. In this study, we intend to investigate the thermal hydraulic behavior with a 1/10 scaled reactor vessel model for the KALIMER-600 reactor. For the flow field measurement, the PIV and UVP methods will be used in a transparent Plexiglas reactor vessel model at around 30℃ water condition. In this paper, we shortly described the scaling analysis status and experiment plan.
초임계 이산화탄소 Brayton 에너지 전환계통 예비설계
차재은(Jae-Eun Cha),어재혁(Jae-Hyuk Eoh),이태호(Tae-Ho Lee),성승환(Sung-Hwan Sung),김성오(Seong-O Kim),김태우(Tae-Woo Kim),김동억(Dong-Eok Kim),김무환(Moo-Hwan Kim) 대한기계학회 2008 대한기계학회 춘추학술대회 Vol.2008 No.11
The supercritical CO₂ Brayton cycle energy conversion system is presented as a promising alternative to the present Rankine cycle. The principal advantage of the S-CO₂ gas is a good efficiency at a modest temperature and a compact size of its components. The S-CO₂ Brayton cycle coupled to a SFR also excludes the possibilities of a SWR (Sodium-Water Reaction) which is a major safety-related event, so that the safety of a SFR can be improved. KAERI is conducting a feasibility study for the supercritical carbon dioxide (S-CO₂) Brayton cycle power conversion system coupled to KALIMER(Korea Advanced LIquid MEtal Reactor). The purpose of this research is to develop S-CO₂ Brayton cycle energy conversion systems and evaluate their performance when they are coupled to advanced nuclear reactor concepts of the type under investigation in the Generation Ⅳ Nuclear Energy Systems. This paper contains the research overview of the S-CO₂ Brayton cycle coupled to KALIMER-600 as an alternative energy conversion system.