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RISS 인기검색어
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- 저자 : Jae-Kwang Seo(서재광) (검색결과 4 건)
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Jae-Kwang Seo(서재광),Han-Ok Kang(강한옥),Juhyeon Yoon(윤주현),Sung-Qunn Zee(지성균) 대한기계학회 2005 대한기계학회 춘추학술대회 Vol.2005 No.11
A once-through steam generator (OTSG) with a modular feedwater line (MFL) is located inside a reactor vessel. A sufficient heating of the feedwater in the MFL can cause an aperiodic instability especially at low flow and low pressure conditions. Aperiodic instability is an instability related to the change of a flow direction in individual steam generating U-shaped channels operating at given pressure difference. The nature of an aperiodic instability is close to a Ledinegg instability related to the presence of multiple flows at the full hydraulic curve of a U-shaped channel. In this paper, the conditions for a reverse flow at the OTSG with a tube-in-tube MFL are studied. From the results of the studies, it is revealed that the change of a flow direction in the MFL is due to the boiling of the feedwater in the downcomer branch of the U-shaped pipe and that multiple flows start in the area of the extreams corresponding to the minimum pressure difference of the hydraulic curves.
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Static Instability of a Once-Through Steam Generator with a Modular Feedwater Line
Jae-Kwang Seo(서재광),Han-Ok Kang(강한옥),Juhyeon Yoon(윤주현),Keung-Koo Kim(김긍구) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.11
Static flow instability of a once-through steam generator (OTSG) with a modular feedwater line is an instability related to the change of a flow direction in individual steam generating U-shaped channels operating at a given pressure difference. The nature of the static instability is close to a Ledinegg instability [1] related to the presence of multiple flows at the full hydraulic curve of a U-shaped channel. In this paper, the conditions for a reverse flow for the OTSG with a U-shaped modular feedwater line (MFL) are studied. From the results of the studies, it is revealed that the change of a flow direction in the MFL is due to a boiling of the feedwater in the downcomer branch of the U-shaped MFL and that multiple flows start in an area of the extremes corresponding to the minimum pressure difference of the hydraulic curves. Calculation models for predicting a threshold of a static instability for the OTSG of interest is proposed and the analysis results are compared with the experimental data.
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축류형 펌프에서 펌프전력을 이용한 유량산정 방범에 관한 연구
이준,서재광,박천태,김영인,윤주현,Lee, Jun,Seo, Jae-Kwang,Park, Chun-Tae,Kim, Young-In,Yoon, Ju-Hyun 한국산학기술학회 2004 한국산학기술학회논문지 Vol.5 No.3
It is the common features of the integral reactors that the main components of the RCS are installed within the reactor vessel, and so there are no any flow pipes connecting the steam generator or the pump whose type is the axial flow. Due to no any flow pipes, it is impossible to measure the differential pressure at the RCS of the integral reactors, and it also makes impossible measure the flow-rate of the reactor coolant. As a alternative method, the method by the measurement of the pump power of the axial flow pump has been introduced in this study. Up to now, we did not found out a precedent which the pump power is used for the flow-rate calculation at normal operation of the commercial nuclear power plants. The objective of the study is to embody the flow-rate calculation method by the measurement of the pump power in an integral reactor. As a result of the study, we could theoretically reason that the capacity-head curve and capacity-shaft power curve around the rated capacity with the high specific-speeded axial flow pumps have each diagonally steep incline but show the similar shape. Also, we could confirm the above theoretical reasoning from the measured result of the pump motor inputs. So, it has been concluded that it is possible to calculate the flow-rate by the measurement of the pump motor inputs.
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연구용 원자로의 원자로 구조물 집합체 스트레이너에서의 압력강하 평가
윤현기(Hyungi Yoon),김다용(Dayong Kim),서재광(Jae-kwang Seo) 대한기계학회 2018 대한기계학회 춘추학술대회 Vol.2018 No.12
Open pool type research reactor is widely designed in consideration of the reactor utilization and accessibility. A coolant flows into a reactor structure assembly and goes to fuel assemblies in the downward flow type reactor. Inlet and outlet pipes of the primary coolant system are directly connected to the reactor structure assembly. The primary coolant system circulates the coolant from the reactor core to the heat exchanger in order to remove the fission heat continuously. There are holes in the reactor structure assembly for the by-pass flow path and the reactor utilization. The strainer is installed on each hole to prevent to enter foreign materials from the reactor pool to fuel assemblies. When the loss of coolant accident occurs in the pipe of the primary coolant system, the coolant is flowed out from the reactor pool to the primary coolant system through strainers. The loss coefficient of the strainer is one factor to determine the flow rate. The flow field of the strainer is numerically simulated to calculate the loss coefficient based on the velocity and pressure. The loss coefficient of 8.0 ± 1.0 is obtained from the numerical and analytical methods.
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