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한국 표준형 원전의 POSRV 하부 배관 유동해석
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  • 한국 표준형 원전의 POSRV 하부 배관 유동해석
저자명
권순범,김인구,안형준,이동은,백승철,이병은,Kwon. Soon-Bum,Kim. In-Goo,Ahn. Hyung-Joon,Lee. Dong-Eum,Baek. Seung-Cheol,Lee. Byeong-Eun
간행물명
大韓機械學會論文集. Transactions of the Korean society of mechanical engineers. B. B
권/호정보
2003년|27권 10호|pp.1464-1471 (8 pages)
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이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
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기타언어초록

In order to investigate the flows with shock wave in branch, 108$^{circ}$ elbow and T-junction of the IRWST system of standard Korean nuclear reactor, detail time dependent behaviors of unsteady flow with shock wave, vortex and so on are obtained by numerical method using compressible three-dimensional Navier-Stokes equations. At first, the complex flow including the incident and reflected shock waves, vortex and expansion waves which are generated at the corner of T-junction is calculated by the commercial code of FLUENT6 and is compared with the experimental result to obtain the validation of numerical method. Then the flow fields in above mentioned units are analyzed by numerical method of [mite volume method. In numerical analysis, the distributions of flow properties with the moving of shock wave and the forces acting on the wall of each unit which can be used to calculate the size of supporting structure in future are calculated specially. It is found that the initial shock wave of normal type is re-established its type from an oblique one having the same strength of the initial shock wave at the 4 times hydraulic diameters of downstream from the branch point of each unit. Finally, it is turned out that the maximum force acting on the pipe wall becomes in order of the T-junction, 108$^{circ}$ elbow and branch in magnitude, respectively.