INVESTIGATION OF CRITICAL HEAT FLUX ON ABRADED INCONEL 625 TUBE

Authors

  • Ladislav Suk Brno University of Technology, Czech Republic
  • Kamil Števanka Brno University of Technology, Czech Republic
  • Taron Petrosyan Brno University of Technology, Czech Republic
  • Daniel Vlček Czech Technical University in Prague, Czech Republic

DOI:

https://doi.org/10.14311/APP.2020.28.0015

Keywords:

annulus, critical heat flux, flow boiling, Inconel 625

Abstract

Aim of this work was to study flow boiling in an annular channel at low pressure and low flow on a tube with modified surface roughness. The tube with the outer diameter of 9.14 mm and the heated length of 380 mm was made of Inconel 625 and was manually modified using 150 grit sandpaper. The tube was placed in a glass tube with an inner diameter of 14.8 mm. Outlet pressure was set to 120, 200 and 300 kPa with varying mass flow from 400 to 600 kg/(m2.s). A high speed camera was used to record several experiments to fully understand ongoing phenomena. Surface roughness was analysed using a confocal laser microscope and the effects of different mass flux and pressure on the CHF value were observed. Above all, the optimization of the flow parameters was done from the collected data and from the observed behaviour of the experimental loop.

Author Biographies

Ladislav Suk, Brno University of Technology, Czech Republic

Brno University of Technology, Faculty of Electrical Engineering and Communication, Department of Electrical Power Engineering, Technická 3058/10, 616 00 Brno, Czech Republic

Kamil Števanka, Brno University of Technology, Czech Republic

Brno University of Technology, Faculty of Electrical Engineering and Communication, Department of Electrical Power Engineering, Technická 3058/10, 616 00 Brno, Czech Republic

Taron Petrosyan, Brno University of Technology, Czech Republic

Brno University of Technology, Faculty of Electrical Engineering and Communication, Department of Electrical Power Engineering, Technická 3058/10, 616 00 Brno, Czech Republic

Daniel Vlček, Czech Technical University in Prague, Czech Republic

Czech Technical University in Prague, Faculty of Nuclear Sciences and Physical Engineering, Department of
Nuclear Reactors, Brehová 78/7, 115 19 Prague, Czech republic

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Published

2020-12-01