Thermal fatigue in stagnant branch lines

Project description

experimental apparatus for the investigation of thermal-fatigue
experimental apparatus for the investigation of thermal-fatigue

We have built an experimental apparatus for the investigation of thermal-fatigue occurring in stagnant branch-lines departing from main coolant lines of nuclear power plants.

Particle Image Velocimetry (PIV) and other high-resolution instrumentation is used to gather high-fidelity data.

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T-junction / branch-line region #3
1) cavity flow forming a vertical vortex, 2) disturbed flow heading various directions, 3) mainly spiral flow upward about the axis, 4) fluctuating boundary
1) cavity flow forming a vertical vortex, 2) disturbed flow heading various directions, 3) mainly spiral flow upward about the axis, 4) fluctuating boundary
A complex flow structure appears in the stagnant branch line as a consequence of the main pipe flow.
A complex flow structure appears in the stagnant branch line as a consequence of the main pipe flow.

Experimental results

Tjunction region 3 measurements
Tjunction region 3 measurements
Particle Image Velocimetry (PIV) and Laser Doppler Velocimetry (LDV)
figure 1

Particle Image Velocimetry (PIV) and Laser Doppler Velocimetry (LDV) is used to perform high-resolution measurements of the flow field in the isolated branch line. As expected, increasing penetration depth with increasing main line flow-rate is observed. A cork-screw flow structure upstream of the penetration boundary is also seen. see figure 1.

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