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김양석(Y.S. Kim),이도환(D.H. Lee),김대웅(D.W. Kim),박성근(S.K. Park),홍승열(S.Y. Hong) 대한기계학회 2003 대한기계학회 춘추학술대회 Vol.2003 No.11
In spite of its simple design, structure and operating mechanism, swing check valves are one of the<br/> critical components which adversely affect the safety of the nuclear power plants if they fail to<br/> function properly. Therefore, it is important to evaluate the performance condition of the swing check<br/> valves in safety-related systems. The performance characteristics of swing check valves include opening<br/> characteristics, the minimum required flow velocity, the pressure drop at design flow, the disc stability,<br/> and the effect of the upstream disturbances. Among factors to identify the performance of a swing<br/> check valve, a method to evaluate the opening characteristics and the minimum required flow velocity,<br/> which guarantees to fully open the disc and hold the disc without motion, are presented to determine<br/> the operating region of the swing check valve, such as stable, tapping, or oscillation. Based on the<br/> determined operating region and opening characteristics, the simple methods of wear and fatigue<br/> analyses of the specific parts of the valve are also described.
〈학술논문〉 초임계압수 냉각로 노심열수력 특성 예비평가
변충섭(C. S. Byun),최훈(H. Choi),이광호(K. H. Lee),배성만(S.M. Bae),김용배(Y. B. Kim),홍승열(S. Y. Hong) 대한기계학회 2008 대한기계학회 춘추학술대회 Vol.2008 No.5
Supercritical water-cooled reactors (SCWR) are among the most promising advanced nuclear systems because of their high thermal efficiency (about 45%) with superior thermodynamic conditions and considerable plant simplification compared to light water reactor. Because of dramatic change of thermal properties of supercritical water, the core thermal-hydraulic analysis is important to evaluate the feasibility of the SCWR. This study contributes to setup the software tool for sub-channel analysis and to validate it. The VIPRE code was adapted for the analysis of reactor cores with supercritical water and the calculation module for thermal properties of super critical water was added in it, and new heat transfer correlation that are considered adequate for SCWR analysis were implemented in the code. For validating, 1/4 core model for SCWR concept using for the feasibility study in Idaho National Laboratory was developed. The preliminary evaluation shows the revised software code to be working well and the characteristics of supercritical water in the core channel to be predicted well.
정일석(I.S. Jeong),김상재(S.J. Kim),이용성(Y.S. Lee),송택호(T.H. Song),홍승열(S.Y. Hong) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.11
For developing fatigue design curve of cast stainless steels that would be used in piping material of domestic nuclear power plants, a low-cycle fatigue test rig was built. It is capable of performing tests in pressurized high temperature water environment of PWR. Cylindrical specimens of CF8M were used for the strain-controlled environmental fatigue tests. Fatigue life was measured in terms of the number of cycles with the variation of strain amplitude at 0.04%/s strain rates. The disparity between target length and measured length of specimens was corrected by using finite element method. The corrected test results showed similar fatigue life trend with another previous results.
고차압에서 운전되는 모터구동게이트밸브의 부하율 향상 방안
김대웅(D.-W. Kim),박성근(S.-G. Park),홍승열(S.-Y. Hong),유성연(S.-Y.Yooh) 한국유체기계학회 2003 유체기계 연구개발 발표회 논문집 Vol.- No.-
This paper presents the method of Rate of Loading(ROL) improvement for the Motor Operated Gate Valve operating in high differential pressure condition. The character of ROL and Stem Factor is analyzed. Static test and dynamic test were performed and acquired the diagnosis signal for the valve closing stroke. The result of this study is the modification of stem factor is very important factor for the ROL improvement. In order to obtain the same value of dynamic test thread friction coefficient, stem and stem nut should be combined appropriately.