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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.
원추형 오리피스의 유출계수와 캐비테이션에 관한 실험적 연구
김병찬,윤병옥,박복춘,조남오,지대성,정백순,박경암,Kim, Byeong-Chan,Yun, Byeong-Ok,Park, Bok-Chun,Jo, Nam-O,Ji, Dae-seong,Jeong, Baek-Sun,Park, Gyeong-Am 대한기계학회 1997 大韓機械學會論文集B Vol.21 No.10
The high pressure drop is frequently required in the by-pass line of the pump or of the heat exchanger in power plants. However, cavitation produced by a high pressure drop could damage the pipe and pump blades. Conical orifices are adopted to reduce cavitation due to high pressure drop. The discharge coefficients of conical orifice plates were measured by weighing method in the standard water flow system. The discharge coefficients were larger when the ratios of thickness of orifice edge to throat diameter were larger. The noise generated from a conical orifice due to cavitation was measured with a sound level meter and a hydrophone. With increasing the bore diameter of the orifice, the sound pressure level or the noise level due to cavitation became higher. The noise level was suddenly increased at the inception of cavitation.
웨스팅하우스형 원전에서 가압기 안전밸브 개방고착 확률 리스크 영향 평가
오해철 (H. C. Oh),하정헌 (J. H. Ha),서미로(M.R. SEO),정백순 (B. S. Chung),김명기 (M. K. Kim) 한국동력기계공학회 2008 한국동력기계공학회 학술대회 논문집 Vol.2008 No.11
In an effort to increase the quality of probabilistic safety assessments (PSAs), it is recommended that the component failure are included the impact of the accident progression phenomena, either in the accident sequence models or in the system models. During various accident sequences modeled in the PSA, the pressurizer safety valves (PSVs) of a pressurized water reactor (PSVs) may cycle numerous times. The PSVs will initially relieve steam. In some longer duration accident sequences, the steam relief will eventually become liquid relief. With each cycle of the PSV, there is a probability that the safety valve will fail to reseat. The PSV failure-to-reseat results in the need for additional mitigative systems to prevent core damage. This paper describes a quantitative assessment to identify risk impacts of the failure probability due to the repeated cycling operation of PSVs (pressurizer safety valves) in westinghouse type PSA.