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Prof. Dr. Borut Mavko

Scientific Councilor

Jožef Stefan
Jamova cesta 39
SI-1000 Ljubljana

Phone: +386 1 5885 450
Fax: +386 1 5885 377




Research Interests

Nuclear safety Transient and accident analysis Probabilistic safety analysis Thermalhydraulics


Research Projects

Slovenian Ministry of Higher Education, Science and Technology:

  • Research program: Nuclear Engineering, Group leader: B. Mavko, Duration: till 2008.

Cooperation in International Research Projects:

  • ENEN II - Consolidation of European Nuclear Education, Training and Knowledge Management, vodja projekta: B. Mavko, Duration: till 2008.
  • SNF-TP, Sustainable Nuclear Fission Technology Platform, vodja projekta: B. Mavko, Duratione: till 2008.
  • Network of Excellence SARNET (Network of Excellence for a Sustainable Integration of European Research on Severe Accident Phenomenology), Sixth Framework Programme of the EC, Coordinator: IRSN, France, IJS Project leader: M. Leskovar, Vice-Chairman of Governing Board: B. Mavko, Duration: till 2008
  • Code Assessment Maintenance Program (CAMP), International Project, Coordination: US NRC, National Counterpart: "J.Stefan" Institute, Duration: till 2012.


  • Dipl. Ing. EE, University of Ljubljana, Slovenia, 1967
  • MS EE, University of Ljubljana, Slovenia, 1971
  • MS NE, Georgia Institute of Technology, Atlanta, USA, 1972
  • Ph. D., University of Maribor, Slovenia, 1979

Committee and Board Memberships

  • NPP Krsko Safety Committee, Krsko, since 1984
  • Administration for Nuclear Safety of Slovenia, Board for NPP Operator Licensing, Ljubljana, since 1980
  • J.Stefan Insitute, Scientific Council, since 1992
  • EU 6.FP SARNET, Vice-Chairman of Governing Board, since 2004

Professional Experience

  • Since 1967 employed by Jozef Stefan Institute
    • Scientific Councilor, Reactor Engineering Department, Jozef Stefan Institute, Ljubljana (full time)
    • Professor, University of Ljubljana, Faculty for Mathematics and Physics, Graduate Programme of Nuclear Engineering (part time)

Professional Societys

Selected Publications

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

  • KONČAR, Boštjan, KLJENAK, Ivo, MAVKO, Borut. Modelling of local two-phase flow parameters in upward subcooled flow boiling at low pressure. Int. j. heat mass transfer. [Print ed.], 2004, vol. 47, str. 1499-1513.
  • TISELJ, Iztok, HETSRONI, Gad, MAVKO, Borut, MOSYAK, Albert, POGREBNYAK, Elena, SEGAL, Z. Effect of axial conduction on the heat transfer in micro-channels. Int. j. heat mass transfer. [Print ed.], 2004, vol. 47, str. 2551-2565.
  • PROŠEK, Andrej, KVIZDA, Boris, MAVKO, Borut, KLIMENT, Tomáš. Quantitative assessment of MCP trip transient in a VVER. Nucl. Eng. Des.. [Print ed.], 2004, vol. 227, str. 85-96.
  • TISELJ, Iztok, HORVAT, Andrej, MAVKO, Borut, POGREBNYAK, Elena, MOSYAK, Albert, HETSRONI, Gad. Wall properties and heat transfer in near-wall turbulent flow. Numer. heat transf., A Appl.. [Print ed.], 2004, vol. 46, str. 717-729.
  • HORVAT, Andrej, MAVKO, Borut. Calculation of conjugate heat transfer problem with volumetric heat gerenation using the Galerkin method. Appl. math. model.. [Print ed.], 2005, vol. 29, str. 477-495.
  • HORVAT, Andrej, MAVKO, Borut. Hierarchic modeling of heat transfer processes in heat exchangers. Int. j. heat mass transfer. [Print ed.], 2005, vol. 48, str. 361-371.
  • MOONS, Frans, SAFIEH, Joseph, GIOT, Michel, MAVKO, Borut, SEHGAL, Bal Raj, SCHÄFER, Anselm, VAN GOETHEM, Georges, D'HAESELEER, William Denis. European master of science in nuclear engineering. Nucl. Eng. Des.. [Print ed.], 2005, vol. 235, str. 165-172.
  • KLJENAK, Ivo, MAVKO, Borut. Simulation of void fraction profile evolution in subcooled nucleate boiling flow in a vertical annulus using a bubble-tracking approach. Heat mass transf., 2006, vol. 42, str. 552-561.
  • HORVAT, Andrej, LESKOVAR, Matjaž, MAVKO, Borut. Comparison of heat transfer conditions in tube bundle cross-flow for different tube shapes. Int. j. heat mass transfer. [Print ed.], 2006, vol. 49, no. 5-6, str. 1027-1038.
  • HORVAT, Andrej, MAVKO, Borut. Drag coefficient and Stanton number behavior in fluid flow across a bundle of wing-shaped tubes. J. heat transfer, 2006, vol. 128, no. 9, str. 969-973.
  • ČEPIN, Marko, CIZELJ, Leon, LESKOVAR, Matjaž, MAVKO, Borut. Vulnerability analysis of a nuclear power plant considering detonations of explosive devices. J. Nucl. Sci. Technol., 2006, vol. 43, no. 10, str. 1258-1269.
  • KLJENAK, Ivo, BABIĆ, Miroslav, MAVKO, Borut, BAJSIČ, Ivan. Modeling of containment atmosphere mixing and stratification experiment using a CFD approach. Nucl. Eng. Des.. [Print ed.], 2006, vol. 236, no. 14-16, str. 1682-1692.
  • PROŠEK, Andrej, D'AURIA, Francesco, RICHARDS, David J., MAVKO, Borut. Quantitative assessment of thermal-hydraulic codes used for heavy water reactor calculations. Nucl. Eng. Des.. [Print ed.], 2006, vol. 236, str. 295-308.
  • HORVAT, Andrej, MAVKO, Borut. Heat transfer conditions in flow across a bundle of cylindrical and ellipsoidal tubes. Numer. heat transf., A Appl.. [Print ed.], 2006, vol. 49, no. 7, str. 699-715.
  • BABIĆ, Miroslav, KLJENAK, Ivo, MAVKO, Borut. Prediction of light gas distribution in experimental containment facilities using the CFX4 code. Nucl. Eng. Des.. [Print ed.], 2008, vol. 238, no. 3, str. 538-550.
  • PETELIN, Stojan, MAVKO, Borut, KONČAR, Boštjan, HASSAN, Yassin A. Scaling of small-scale thermal-hydraulic transient to the real nuclear power plant. Nucl. technol., 2007, vol. 158, no. 1, str. 56-68.
  • PROŠEK, Andrej, MAVKO, Borut. The state-of-the-art theory and applications of best-estimate plus uncertainty methods. Nucl. technol., 2007, vol. 158, no. 1, str. 69-79.
  • VOLKANOVSKI, Andrija, MAVKO, Borut, BOŠEVSKI, Tome, ČAUSEVSKI, Anton, ČEPIN, Marko. Genetic algorithm optimisation of the maintenance scheduling of generating units in a power system. Reliab. eng. syst. saf.. [Print ed.], 2008, vol. 93, no. 3, str. 779-789.


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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