Boštjan Končar

Dr. Boštjan Končar

orcid

Research Focus & Metrics

Academic Career Length

19Years (2008-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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30 July 2024 in International Journal of Multiphase Flow
Verified
Journal Article
Open access
GBG. Bois
G. Bois
PFP. Fillion
P. Fillion
FFFabrice FRANCOIS
Fabrice FRANCOIS
ABAlan Burlot
Alan Burlot
AAA. Ben Hadj Ali
A. Ben Hadj Ali
VHV. Hovi
V. Hovi

24 December 2012 in Science and Technology of Nuclear Installations
Verified
Journal Article
Open access
PDF file
MMMarko Matkovič
Marko Matkovič
BKBoštjan Končar
Boštjan Končar
This paper presents quality assessment of a mechanistic modelling for bubble departure diameter prediction during pool boiling condition. In contrast to flow boiling process only buoyancy force with opposing surface tension force was considered as the responsible mechanisms for bubble departure. Indeed, inertia from the fluid flow around the bubble and the growth force, which describes momentum change due to the evaporation at the bubble base and condensation at the top of the bubble, were all neglected. Besides, shear lift force and quasi-steady drag force as the dominant inertia driven forces were also neglected in the assessment. Rather than trying to model bubble dynamics as precise as possible by properly addressing all the relevant mechanisms available, the work focuses on prediction accuracy of such approach. It has been shown that inlet boundary conditions with realistic experimental accuracy may lead to a significant uncertainty in the prediction of bubble departure diameter, which is intrinsically connected to the uncertainty of most heat partitioning and CHF models.

21 November 2022 in Flow Measurement and Instrumentation
Verified
Journal Article
Closed access
BKBoštjan Končar
Boštjan Končar
JSJ. Sotošek
J. Sotošek
IBI. Bajsić
I. Bajsić

19 February 2018 in Science and Technology of Nuclear Installations
Verified
Journal Article
Open access
PDF file
RKRok Krpan
Rok Krpan
BKBoštjan Končar
Boštjan Končar
The development of a turbulent mixing layer at mixing of two horizontal water streams with slightly different densities is studied by the means of numerical simulation. The mixing of such flows can be modelled as the flow of two components, where the concentration of one component in the mixing region is described as a passive scalar. The velocity field remains common over the entire computational domain, where the density and viscosity difference due to the concentration mainly affects the turbulent fluctuations in the mixing region. The numerical simulations are performed with the open source code OpenFOAM using two different approaches for turbulence modelling, Reynolds Averaged Navier Stokes equations (RANS) and Large Eddy Simulation (LES). The simulation results are discussed and compared with the benchmark experiment obtained within the frame of OECD/NEA benchmark test. A good agreement with experimental results is obtained in the case of the single liquid experiment. A high discrepancy between the simulated and the experimental velocity fluctuations in the case of mixing of the flows with the slightly different densities and viscosities triggered a systematic investigation of the modelling approaches that helped us to find out and interpret the main reasons for the disagreement.

27 October 2008 in Science and Technology of Nuclear Installations
Verified
Journal Article
Open access
PDF file
BKBoštjan Končar
Boštjan Končar
BMBorut Mavko
Borut Mavko
A three-dimensional two-fluid code Neptune_CFD has been validated against the Arizona State University (ASU) and DEBORA boiling flow experiments. Two-phase flow processes in the subcooled flow boiling regime have been studied on ASU experiments. Within this scope a new wall function has been implemented in the Neptune_CFD code aiming to improve the prediction of flow parameters in the near-wall region. The capability of the code to predict the boiling flow regime close to critical heat flux (CHF) conditions has been verified on selected DEBORA experiments. To predict the onset of CHF regime, a simplified model based on the near-wall values of gas volume fraction was used. The results have shown that the code is able to predict the wall temperature increase and the sharp void fraction peak near the heated wall, which are characteristic phenomena for CHF conditions.

1 February 2010 in Nuclear Engineering and Design
Verified
Journal Article
Closed access
BKBoštjan Končar
Boštjan Končar
ITIztok Tiselj
Iztok Tiselj