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이선기,정백순,김창호,Lee, Sun-Ki,Chung, Bag-Soon,Kim, Chang-Ho 한국유체기계학회 1999 한국유체기계학회 논문집 Vol.2 No.2
Thermal output in a nuclear power plant is verified with calorimetric heat balance on the secondary plant. The calorimetry involves the precise measurement of the feedwater flow rate. However, the correct indication of feedwater flow rate obtained by a pressure-difference measurement across a venturi can be affected by instrument errors, fouling or a poorly developed velocity profile. This can result in an inaccurate mass flow rate and consequently an inaccurate estimate of power. The purpose of this study is to develop verification methods with accuracy better than $0.5\%$ for high precision flow measurement to be used for measuring feedwater flow rate. This chemical tracer method is a testing process that uses tracers which can be applied to quantify losses in electrical output due to the incorrect measurements of feedwater flow rate. And this system has good response to the variation of the flow rate. Accuracy of better than 0.5 percent can be expected for feedwater flow measurement, providing that the system can be stabilized during the test. This methodology is applicable to other flow systems well.
이선기,Lee, Sun-ki 한국유체기계학회 2000 한국유체기계학회 논문집 Vol.3 No.1
For the improvement of the pump characteristics in the partial capacity range, it must be verified that the influence of the impeller design factor on the internal flows and the influence of the impeller internal flows on the pump characteristics. In this paper, in order to understand the influence of outlet angles on flow conditions and characteristics of a mixed flow pump, experiments were carried out for four kinds of impeller, which have the same inlet angle distributions and meridional section shapes. Results shown that separation and stall in the partial capacity range were enlarged by the outlet angles. The relationship between the separation and the stall at the impeller and the discharge flow conditions were clarified.
이선기,Lee, Sun Ki 한국압력기기공학회 2016 한국압력기기공학회 논문집 Vol.12 No.2
The thermal stratification phenomenon in the nuclear power plant can cause abnormal deformation of the piping, contact with the support, damage to the support system. Repetition of the thermal stratification phenomenon or variation of the thermal boundary layer can cause thermal fatigue. Thermal stratification phenomenon in nuclear power plants is still an ongoing issue and active research has been carried out. In this paper, the current situation in Korean nuclear power plants is described, followed by the status of research and the future problems on the thermal stratification phenomenon in Korea.
이선기(Sun-Ki Lee) 한국동력기계공학회 2020 동력시스템공학회지 Vol.24 No.2
Nuclear power plants have a number of pumps, which are operating at a high temperature–high pressure and radiation environment conditions. However, the aging of the pumps by increasing of years of plant operation and the system transients due to the sudden load change are causing the failures of the reliability of the pumps. Nevertheless, it is important to maintain the reliability of the pumps to ensure safe operation of the nuclear power plant. In this paper, an acceleration test apparatus was developed to secure the reliability of centrifugal pumps. The performance change with the increase of operation time of the pump was experimentally evaluated by the acceleration test. As the operating time of the pump increased, it was confirmed that the pump efficiency and head decreased.
이선기(Sun-Ki Lee) 한국동력기계공학회 2015 동력시스템공학회지 Vol.19 No.5
Nuclear power plants has a number of valves, which are operating at a high temperature?high pressure and radiation environment conditions. Nevertheless, it is important to maintain the reliability of the valves to ensure safe operation of the nuclear power plant. However, the aging of the valves by increasing of years of plant operation and the system transients due to the sudden load change are working the failures of the reliability of the valve. In this paper, we evaluate experimentally the performance change according to the thermal aging of the valve. Results show that the valve stem and the actuator leakages were enlarged by the thermal aging.
이선기(Sun-Ki Lee),이상국(Sang-kook Lee),김태룡(Tae-Ryong Kim),송택호(Taek-Ho Song),권종주(Jong-Ju Kwon),정일석(Ill-Suk Jung),홍승열(Seung-Ryul Hong) 대한기계학회 2005 대한기계학회 춘추학술대회 Vol.2005 No.5
During the nuclear power plant periodical inspection, the crack was detected at the reduce pressure orifice down stream in the CVCS(Chemical& Volume Control System). This Paper examined the degradation mechanism of reduce pressure orifice of CVCS by the measuring vibration and frequency analysis, internal flow pattern analysis. Results show that the degradation of the reduce pressure orifice was caused cavitation, and suggest design improvement plan for damage prevention.
고온/고압용 집진장치 및 역세정 시스템 설계를 위한 전산 유동해석
이선기 ( Sun Ki Lee ),정석우 ( Seok Woo Chung ) 한국공업화학회 2010 응용화학 Vol.14 No.1
전산유체역학을 이용하여 집진 및 역세정 장치의 유동특성 해석을 진행하였는데, 해석에서는 고온/고압 시스템에 적용하기 위한 집진장치를 대상으로 하였으며, 이를 통해 집진시스템 전체의 유동 및 온도분포, 입자거동 등을 파악하였다. 해석결과에 의하면 집진장치 내부에 원통형 격벽을 설치함으로써 집진필터의 입자부하를 최소화 할 수 있는 것으로 나타났으며, 역세정 노즐 및 벤추리 부분은 기존의 방식과 본 연구의 설계안을 비교하여 장단점을 파악할 수 있었는데 분진이 누적되지 않은 상태에서는 기존의 벤추리 노즐 방식이 적은 양의 역세정 가스로 우수한 역세정 효과를 나타내지만, 일반적인 운전조건에서는 필터표면에 달라붙는 분진 부하에 의해 본연구의 설계안이 높은 효율을 가지는 것으로 확인되었다.