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배준호(Jun Ho Bae),어동진(Dong Jin Euh),권태순(Tae Soon Kwon) 대한기계학회 2011 대한기계학회 춘추학술대회 Vol.2011 No.5
본 논문은 원자력 열수력 실험장치의 설계에 있어 CFD의 적용 예에 대해서 기술한다. 특히, 다음 주제에 관한 CFD 활용에 대해서 다룬다. 1) 노심 모의기의 유동 및 압력장 분포, 2) 원자로 강수부에서 압력파 교란 This paper describes the applicabi1ity of CFD for designing of nuclear thennal hydraulics test facility. Especially, CFD analysis will be discussed for the following subjects. 1) Flow and pressure distribution of core simulator, 2) Pressure Perturbation in Downcomer
강경호(Kyoung-Ho Kang),윤병조(Byung-Jo Yun),어동진(Dong-Jun Euh),백원필(Won-Pil Baek),유선봉(Sun-Bong Yu) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.6
An advanced flow meter applicable to large diameter piping system was developed using the average BDFT(Bidirectional Flow Tube). This flow meter can be used to measure the flow rate of discharged gas having fine floating particles in the stack of the chemical reactor and the large-sized boiler. Also it can be applied to the large-sized industrial piping system having flow of oil without structural instability. As a first step of commercialization, we designed and manufactured the flow meters which are applicable to piping system having diameter of 200㎜ and 500㎜. The calibration test results indicated that this flow meter has linaerity within 0.5% in the Re number range of above 10,000 where is meaningful in terms of application.