Published November 2011 | Version v1
Journal article

A finite element LES for high-Re flow in a short-elbow pipe with undisturbed inlet velocity

  • 1. Central Research Institute of Electric Power Industry, Abiko 1646, Abiko-shi, Chiba-ken 270-1194 (Japan)
  • 2. Japan Atomic Energy Agency, 4002 Narita-cho, O-arai-machi, Ibaraki-ken 311-1393 (Japan)

Description

Research highlights: ► We simulate a high-Reynolds-number flow in a short-elbow pipe with LES. ► We examine the effects of SGS model and inlet velocity profile without fluctuation. ► We find the thicker the boundary layer at inlet, the weaker the flow separation. ► We find the WALE model induce unphysical SGS viscosity for rigidly rotating flow. ► Unsteady force can be explained by Dean vortices destabilized by flow separation. - Abstract: The paper is concerned with a large-eddy simulation (LES) for a high-Reynolds-number flow in a short-elbow pipe, which can potentially be employed in the primary piping system of the Japan Sodium-cooled Fast Reactor (JSFR). The basic performance of the LES is studied for an elbow pipe flow without turbulence at inlet boundary at Re = 1.2 × 106 by comparison with a flow observed in a 1/3-scale water experiment, where the flow disturbance at the pipe inlet is small. In setting up the computational conditions, special care was taken to ensure that the mesh subdivision was suitable for the simulation of the pipe flow through a theoretical consideration. We discuss the effects of the turbulence model (Smagorinsky model, WALE model) and the inlet velocity profile on the results. The mechanism of the pressure fluctuation and the origin of the fluid force are also discussed with the aid of spectral analysis and the visualization of essential hydraulic quantities.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2010.09.038

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2010.09.038;
PII
S0029-5493(11)00086-0;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
241
Journal Issue
11
Journal Page Range
p. 4368-4378
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
13. international topical meeting on nuclear reactor thermal hydraulics
Acronym
NURETH-13
Dates
27 Sep - 2 Oct 2009
Place
Kanazawa (Japan)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
43073997
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BOUNDARY LAYERS; DISTURBANCES; FINITE ELEMENT METHOD; LARGE-EDDY SIMULATION; REYNOLDS NUMBER; SODIUM COOLED REACTORS; TURBULENCE; VELOCITY; VISCOSITY; VORTICES; WATER
Descriptors DEC
CALCULATION METHODS; COMPUTERIZED SIMULATION; DIMENSIONLESS NUMBERS; HYDROGEN COMPOUNDS; LAYERS; LIQUID METAL COOLED REACTORS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; REACTORS; SIMULATION

Optional Information

Copyright
Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.