Boštjan Končar

Senior Research Associate

Jožef Stefan
Institute
Jamova cesta 39
SI-1000 Ljubljana
Slovenia

Phone: +386 1 5885 260
Fax: +386 1 5885 377
E-mail: mailto:bostjan.koncar@ijs.si

Research Interests

• Numerical simulations of two-phase flows.
• Modelling of convective boiling.
• Technology of fusion reactors.
• Thermal-hydraulic safety analyses.
• Simulations of turbulence and heat transfer in single-phase flows.

Education

• Ph.D. in Nuclear Engineering,  Faculty of mathematics and physics, University of Ljubljana, 2003
• Msc. in Nucl. Eng., Faculty of mathematics and physics, University of Ljubljana, 1999
• Bsc. in Mech. Eng., Faculty of Mechanical Engineering, University of Ljubljana, 1996

Teaching

• Nuclear Thermalhydraulics (Nuclear Engineering program, level II) on  Faculty of mathematics and physics, University of Ljubljana

Professional Experience

• Since 1996 employed by Jozef Stefan Institute
• Guest scientist in Forschungszentrum Rossendorf, Germany, Institute of Safety Research, Jun–July 2004, May-June 2005
• Guest scientist in Forschungszentrum Karlsruhe, Germany, Institute for Materials Research, July 2008

Management Experience

• Head of Slovenian Fusion Association (from 2014).
• Slovenian representative (expert) in the Fusion Programme Committee of the European Commission - Horizon 2020 (2014-2020).
• President Nuclear Society of Slovenia (2006-2010).
• Governing Board member ARAO (2006-2010)
• Member of the Council of the National Energy Agency JARSE (2009-2014).
• Organizer of international scientific conferences.
• Principal researcher of several international and national research projects.

Professional Societies

• Nuclear Society of Slovenia (President 2006-2010)
• European Nuclear Society

Selected (recent) Publications (on-line list of all publications)

The full list of publications is maintained by COBISS. Links to publications use the Digital Object Identifier System DOI.

• DRAKSLER, Martin, NIÄŒENO, Bojan, KONÄŒAR, Boštjan, CIZELJ, Leon. Large eddy simulation of multiple impinging jets in hexagonal configuration - Mean flow characteristics. International journal of heat and fluid flow, [Print ed.], 2014, vol. 46, str. 147-157, doi: 10.1016/j.ijheatfluidflow.2014.01.005.

• KONÄŒAR, Boštjan, KOŠMRLJ, Samo, NORAJITRA, Prachai. On the accuracy of CFD modeling of cyclic high heat flux divertor experiment. Fusion eng. des.. [Print ed.], 2012, vol. 87, no. 9, str. 1621-1627, doi: 10.1016/j.fusengdes.2012.06.005.

• KONÄŒAR, Boštjan, MATKOVIÄŒ, Marko. Simulation of turbulent boiling flow in a vertical rectangular channel with one heated wall. Nucl. Eng. Des.. [Print ed.], 2012, vol. 245, no. 1, str. 131-139, doi: 10.1016/j.nucengdes.2012.01.013.

• MATKOVIÄŒ, Marko, KONÄŒAR, Boštjan. Bubble departure diameter prediction uncertainty. Sci. Technol. Nucl. Install. (Print), 2012, vol. 2012, str. 863190-1-863190-7, doi: :10.1155/2012/863190.

• KONÄŒAR, Boštjan, SIMONOVSKI, Igor, DRAKSLER, Martin. Influence of multiple jet cooling on the heat transfer and thermal stresses in DEMO divertor cooling finger = f. Fusion eng. des.. [Print ed.], 2011, vol. 25, no. 2, str. 537-548, doi: 10.1016/j.fusengdes.2010.10.006.

• KONÄŒAR, Boštjan, MOREL, C., MIMOUNI, S., VYSKOCIL, L., GALASSI, M. C. Computational fluid dynamics modeling of boiling bubbly flow for departure from nucleate boiling investigations. Multiph. sci. technol., 2011, vol. 23, no. 2/3, str. 165-222, doi: 10.1615/MultScienTechn.v23.i2-4.40.

• DRAKSLER, Martin, KONÄŒAR, Boštjan. Analysis of heat transfer and flow characteristics in turbulent impinging jet. Nucl. Eng. Des.. [Print ed.], 2011, vol. 241, no. 4, str. 1248-1254, doi: 10.1016/j.nucengdes.2010.03.037.

• KONÄŒAR, Boštjan, NORAJITRA, Prachai, OBLAK, Klemen. Effect of nozzle sizes on jet impingement heat transfer in He-cooled divertor. Appl. therm. eng.. [Print ed.], May 2010, issue 6-7, vol. 30, str. 697-705, doi: 10.1016/j.applthermaleng.2009.11.018.

• SIMONOVSKI, Igor, KONÄŒAR, Boštjan, CIZELJ, Leon. Thermo-mechanical analysis of a DEMO divertor cooling finger under the EFREMOV test conditions. Fusion eng. des.. [Print ed.], 2010, vol. 85, no. 1, str. 130-137, doi: 10.1016/j.fusengdes.2009.08.005.

• KONÄŒAR, Boštjan, TISELJ, Iztok. Influence of near-wall modelling on boiling flow simulation. Nucl. Eng. Des.. [Print ed.], 2010, vol. 240, no. 2, str. 275-283, doi: 10.1016/j.nucengdes.2008.07.019.

• KONÄŒAR, Boštjan, MAVKO, Borut. Wall function approach for boiling two-phase flows. Nucl. Eng. Des.. [Print ed.], 2010, vol. 240, no. 11, str. 3910-3918, doi: 10.1016/j.nucengdes.2010.08.004.

• KONÄŒAR, Boštjan, KREPPER, Eckhard. CFD simulation of convective flow boiling of refrigerant in a vertical annulus. Nucl. Eng. Des.. [Print ed.], 2008, vol. 238, no. 3, str. 693-706.

• KONÄŒAR, Boštjan, MAVKO, Borut. Simulation of boiling flow experiments close to CHF with the Neptune_CFD code. Sci. Technol. Nucl. Install. (Print), 2008, vol. 2008, str. 732158-1-732158-8.

• KREPPER, Eckhard, KONÄŒAR, Boštjan, EGOROV, Yury. CFD modelling of subcooled boiling - concept, validation and application to fuel assembly design. Nuclear Engineering and Design, ISSN 0029-5493. [Print ed.], 2007, vol. 237, no. 7, str. 716-731. 

• BESTION, D., KONÄŒAR, Boštjan. Review of available data for validation of NURESIM two-phase CFD software applied to CHF investigations. Sci. Technol. Nucl. Install. (Print), 2009, vol. 2009, str. 214512-1-214512-14.