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한국 표준형 원전의 POSRV 하부 배관 유동해석

Flow Analysis of POSRV Subsystem of Standard Korean Nuclear Reactor

  • 권순범 (경북대학교 기계공학부) ;
  • 김인구 (한국 원자력 안전기술원) ;
  • 안형준 (한국 원자력 안전기술원) ;
  • 이동은 (경북대학교 대학원 기계공학과) ;
  • 백승철 (경북대학교 대학원 기계공학과) ;
  • 이병은 (한국항공기능대학)
  • 발행 : 2003.10.01

초록

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.

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참고문헌

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