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Boštjan Končar

Senior Research Associate

Jožef Stefan
Jamova cesta 39
SI-1000 Ljubljana

Phone: +386 1 5885 260
Fax: +386 1 5885 377






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.



Professional Experience

Management Experience

Professional Societies

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.


Joint European Torus (JET) device released a record 59 MJ of sustained fusion energy
Researchers from the EUROfusion consortium, including JSI researchers, used the Joint European Torus (JET) device to release a record 59 MJ of sustained fusion energy. The breakt...
Turbulent Flow over Confined Backward-Facing Step: PIV vs. DN
Boštjan Zajec, Marko Matkovič, Nejc Kosanič, Jure Oder, Blaž Mikuž, Jan Kren and Iztok Tiselj from the Reactor Engineering Division at Jožef Stefan Institute published the article “Turbul...
Prof. dr. Leon Cizelj elected as the president of the European Nuclear Society (ENS)
Prof. dr. Leon Cizelj was elected as the president of the European Nuclear Society (ENS; for 2022 and 2023 at the proposal of the Nuclear Society of Slo...
New experimental campaign - Investigation of Temperature Fluctuations in a Fully Developed Channel Flow
New experimental campaign - Investigation of Temperature Fluctuations in a Fully Developed Channel Flow Dr. Mohit Sharma and colleagues have performed turbulent heat transfer experiments with the heated thin fo...
The 8th Young Generation Nuclear Conference has been successfully held online
On 19 May 2021, the Young Generation Network of the Nuclear Society of Slovenia (YGN NSS), in cooperation with the Reactor Engineering Division of the Jožef Stefan Institute, organized the 8th Young Generation Nuclear Conference YGNC. Due to the coron...
A single grain boundary parameter to characterize normal stress fluctuations in materials with elastic cubic grains
Dr. Samir El Shawish and dr. Timon Mede from the Reactor Engineering Division at Jožef Stefan Institute, in collaboration with dr. Jeremy Hure from Université Paris-Saclay, CEA (France) published the article &l...
Modelling of premixed layer formation in stratified fuel–coolant configuration
Janez Kokalj, dr. Mitja Uršič and dr. Matjaž Leskovar from the Reactor Engineering Division at Jožef Stefan Institute published the article »...
Validation of a morphology adaptive multi-field two-fluid model considering counter-current stratified flow with interfacial turbulence damping
Dr. Matej Tekavčič from the Reactor Engineering Division at Jožef Stefan Institute in collaboration with researchers from the Institute of Fluid Dynamics, Helmholtz-Zentrum Dresden-Rossendorf (Germany) published the article »...
Symposium and seminar nuclear human development in TokyoTec
The international symposium and seminar on global nuclear human resource development for safety, security and safeguards (IS3S) is a yearly activity coordinated by the Academy for Global Nuclear Safety and Security Agent of the Tokyo Institute of Techn...
NESTet 2020 program board meeting, Bruselj, 7.-10.1.2020
The NESTet conference is dedicated to education and training in nuclear technology. After several years of silence (the last NESTet was organized by the ...
15th Steering Committee Meeting of the TSO Forum (TSOF), Vienn, Austria, 17.-18. 2. 2020
In 2010, the International Atomic Energy Agency (IAEA) set up a comitee of Certified Nuclear and Radiation Safety Experts (TSOs) to promote cooperation and exchange of information. The basis for the ...
WPSAE Progress Meeting & PMU meeting, Garching, Germany, 27.1.-29.1. 2020
Within the framework of Horizon 2020, European fusion research combines the targeted 7-year (2014-2020) EUROfusion fusion program under the auspices of the EURATOM Treaty. Within EUROfusion, a large part of the activities is devoted to the development ...
ENEN+ Communication workshop, Brussels, Belgium, 13.-14.10.2019
Part of the ENEN + (Attract, Retain and Develop New Nuclear Talents Beyond Academic Curricula) project is the development and implementation of a communication strategy to fam...
18th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-18), Portland, USA, 18. 8. – 22. 8. 2019
NURETH is the most important conference related to the nuclear reactor thermal-hydraulics. At the NURETH-18 internetional conference, 545 papers were presented as well as 3 pannel discussions and 17 technical keynote addresses. Main topics were: ...
EUROfusion PPPT Project Management Meeting in DEMO Project Board Meeting, IPP, Garching, Germany, 11.-12. 7. 2019
As a part of Horizon 2020, european fusion research brings together a targeted 5-year (2014-2018) EUROfusion program under the auspices of the EURATOM Treaty. Due to the 7-year horizon of Horizon 202...
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