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RISS 인기검색어
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- 저자 : 지성균(S. Q. Zee) (검색결과 2 건)
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일체형원자로에서 냉각재펌프의 전력측정을 이용한 실시간 유량산정 방법에 관한 연구
이준(J. Lee),윤주현(J.-H. Yoon),지성균(S.-Q. Zee) 한국유체기계학회 2003 유체기계 연구개발 발표회 논문집 Vol.- No.-
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 coolant pumps or steam generators. 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 coolant pump power has been introduced in this study. Up to now, we did not found out a precedent which the coolant pump power is used for the real-time flow-rate calculation at normal operation of the commercial nuclear power plants. The objective of the study is to embody the real-time flow-rate calculation method by the measurement of coolant 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 real-time flow-rate by the measurement of pump motor inputs. In addition, the compensation for a above new method. can be made by HBM being now used in the commercial nuclear power plants.
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SMART연구로의 보수적인 급수관 파단사고 해석방법론 개발
정영종(Y. J. Chung),김수형(S. H. Kim),김희경(H. K Kim),김희철(H. C. Kim),지성균(S. Q. Zee) 대한기계학회 2005 대한기계학회 춘추학술대회 Vol.2005 No.5
Various sizes and types of advanced small and medium sized nuclear reactors are currently nuder development worldwide. The SMART-P, which is an integral pressurized water reactor is one of those advanced types of small sized nuclear reactor. a Feedwater pipe break accident is one of the most important accidents in the safety of the SMART-P plant. Decreased feedwater flow rate to the steam generators causes a decrease in the heat extraction from the reactor coolant system, resulting in a increase of the primary coolant temperature and pressure Performed sensitivity analysis to find parameters affecting seriously in SMART-P's feedwater pipe break accident. According to these sensitivity analysis results, an initial pressurizer pressure, a moderator reactivity coefficient, a power level and a break size are major parameters for the maximum pressure of the reactor coolant system point of view. the pressure in the reactor coolant system and the secondary system for all the cases investigated, remains below 18.7㎫ which is a safety criteria for SMART-P.
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