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공학적 접근을 통한 해체비용 산정 프레임워크에 대한 고찰
이선기,Lee, Sun Kee 한국시스템엔지니어링학회 2012 시스템엔지니어링학술지 Vol.8 No.2
It is the sensitivity and confidentiality of nuclear power plant decommissioning cost that prevent detailed cost information to be released to the public, which causes some limitation to analyze and reuse the costs. This limitation to access cost information means that the lessons learned from preceding cost estimating may not systematically feed back into following cost estimates. As an alternative, decommissioning cost estimation framework is indispensable to reflecting available experience and knowledge for decommission costs. This study provides the cost estimation framework including data flow and structuralization based on engineering and bottom up approach to enhance decommissioning cost estimation.
이선기,박정하,Lee, Seon-Gi,Park, Jeong-Ha 한국시스템엔지니어링협회 2003 시스템엔지니어링워크숍 Vol.1 No.-
Construction industry recognizes the necessity to manage is business from viewpoint of processes, and consider developing, evaluating and improving standard processes as important managerial target. SW-CMM provides basic framework for this process management. However, appropriate tailoring and adjustment are essential for SW-CMM concept to be applied to construction business. SW-CMM makes construction manager understand the capability of business process, based on which the priority of process improvement is judged. The capability is prescribed by common features. This paper introduces the basic frame for diagnosing construction business processes with SW-CMM, and presents the case study of analysing processes focusing on communication management.
사류 임펠러의 입구각 변화가 내부유동 및 펌프특성에 미치는 영향
이선기,Lee, Seon-Gi 대한기계학회 1997 大韓機械學會論文集B Vol.21 No.8
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 inlet angles on flow conditions and characteristics of a mixed flow pump, experiments were carried out for three kinds of impeller, which have the same outlet angle distributions and meridional section shapes. Results show that separation and stall in the partial capacity range can be controlled by the inlet angles. The relationship between the separation - stall at the impeller leading edge and the discharge flow conditions is clarified.
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,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 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.