Published 2008 | Version v1
Miscellaneous

Study on flow-induced-vibration evaluation of large-diameter pipings in a sodium-cooled fast reactor. (2) A large-eddy simulation of turbulent flow in a short-elbow pipe

  • 1. Central Research Inst. of Electric Power Industry, Civil Engineering Research Laboratory, Abiko, Chiba (Japan)
  • 2. Japan Atomic Energy Agency, Advanced Nuclear System Research and Development Directorate, Oarai, Ibaraki (Japan)

Description

A turbulent flow in a short-elbow pipe was computed with a FEM-based large-eddy simulation code to examine the fundamental features of the flow, especially, pressure fluctuation to cause unsteady fluid force on the short-elbow pipe. The results at Re=3.2x105 and 1.2x106 show that two separation regions exist on the interior side of the elbow around 45-degree (middle of elbow) and 90-degree (end of elbow) positions. The statistical quantities of pressure fluctuation such as deviation, skewness and flatness were computed and analyzed. It is found that high pressure-fluctuation is located in the downstream of the second separation region, and near the twin vortex (or Dean vortices). This indicates that the pressure fluctuation is probably caused by both the shear layer instability at the separation and the twin vortex oscillation. Fluid force exerted on the pipe wall was also computed via surface integration of pressure, showing dominant fluctuations in vertical and out-of-plane (normal to the plane of pipe center line) directions at Strouhal number of about 0.6. (author)

Part of:
NTHAS6: Proceedings of the 6th Japan-Korea symposium on nuclear thermal hydraulics and safety

Additional details

Publishing Information

Imprint Title
NTHAS6: Proceedings of the 6th Japan-Korea symposium on nuclear thermal hydraulics and safety
Imprint Pagination
818 p.
Journal Page Range
[8 p.]

Conference

Title
6. Japan-Korea symposium on nuclear thermal hydraulics and safety
Acronym
NTHAS6
Dates
24-27 Nov 2008
Place
Nago, Okinawa (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
43045132
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; FINITE ELEMENT METHOD; FLUCTUATIONS; MECHANICAL VIBRATIONS; PIPES; REYNOLDS NUMBER; THERMAL HYDRAULICS; TURBULENCE; TURBULENT FLOW; UNSTEADY FLOW; VORTICES
Descriptors DEC
CALCULATION METHODS; DIMENSIONLESS NUMBERS; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MATHEMATICAL SOLUTIONS; MECHANICS; NUMERICAL SOLUTION; SIMULATION; TUBES; VARIATIONS

Optional Information

Notes
This USB flash memory can be used for WINDOWS 2000/XP, MACINTOSH 9.x/10.x; Acrobat Reader is included; Data in PDF format, Folder Name: FullPaper, Paper ID: N6P1003.pdf; 18 refs., 13 figs., 1 tab.