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Iztok Tiselj

Jožef Stefan
Jamova cesta 39
SI-1000 Ljubljana

Phone: +386 1 5885 333
Fax: +386 1 5885 377



Research Interests


ARRS project 2018-2021  Experimental and computational heat transfer studies (in Slovenian)

Development of WAHA code for simulations of 1D water hammer in two-phase systems. (WAHA manual)

Direct Numerical Simulation of turbulent heat transfer. (Lectures)

Numerical simulations of the two-phase flow. (Materials of the course on Two-phase flow modeling, Technical University of Catalonia, 2006)

RELAP5 computer code for thermal hydraulics of nuclear power plants.



Chair for Nuclear engineering, Faculty of Mathematics and Physics, University of Ljubljana


- Jedrska tehnika in energetika (Program Physics, I cycle)

- Reaktorska tehnika (Program Nuclear Engineering, II cycle)


Professional Experience

Selected Publications

The full list of publications is maintained by COBISS.

 TISELJ, Iztok, PETELIN, Stojan. Modelling of two-phase flow with second order accurate scheme. J. comput. phys., 1997, vol. 136, 503-521. 

TISELJ, Iztok, PETELIN, Stojan. First and second-order accurate schemes for two-fluid models. J. fluids eng., 1998, vol. 120, 363-368. 

TISELJ, Iztok, ČERNE, Gregor. Some comments on the behaviour of the RELAP5 numerical scheme at very small time steps. Nucl. sci. eng., 2000, vol. 134, 306-311.

 ČERNE, Gregor, PETELIN, Stojan, TISELJ, Iztok. Coupling of the interface tracking and the two-fluid models for the simulation of the incompressible two-phase flow. J. comput. phys., 2001, vol. 171, 776-804. 

TISELJ, Iztok, BERGANT, Robert, MAVKO, Borut, BAJSIČ, Ivan, HETSRONI, Gad. DNS of turbulent heat transfer in channel flow with heat conduction in the solid wall. J. heat transfer, 2001, vol. 123, št. 5, 849-857. 

TISELJ, Iztok, POGREBNYAK, Elena, LI, Changfeng, MOSYAK, Albert, HESTRONI, Gad. Effect of wall boundary condition on scalar transfer in a fully developed turbulent flume. Phys. fluids , 2001, vol. 13, 1028-1039. 

ČERNE, Gregor, PETELIN, Stojan, TISELJ, Iztok. Numerical errors of the volume-of-fluid interface tracking algorithm. Int. j. numer. methods fluids, 2002, vol. 38, 329-350. 

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, 2004, vol. 47, 2551-2565. 

BERGANT, Robert, TISELJ, Iztok. Near-wall passive scalar transport at high Prandtl numbers. Phys. fluids (1994), 2007, vol. 19, št. 6, str. 065105-1-065105-18. 

TISELJ, Iztok, GALE, Janez. Integration of unsteady friction models in pipe flow simulation J. Hydraul. Res., 2008, vol. 46, št. 4, str. 526-535. 

GALE, Janez, TISELJ, Iztok. Godunov's method for simulatinons of fluid-structure interaction in piping systems. J. press. vessel technol., 2008, vol. 130, št. 3, str. 031304-1-031304-12. 

ŠTRUBELJ, Luka, ÉZSÖL, György, TISELJ, Iztok. Direct contact condensation induced transition from stratified to slug flow. Nucl. Eng. Des., 2010, vol. 240, no. 2, str. 266-274. 

ŠTRUBELJ, Luka, TISELJ, Iztok. Two-fluid model with interface sharpening. Int. j. numer. methods eng., 2011, vol. 85, no. 5, str. 575-590, doi: 10.1002/nme.2978.

TISELJ, Iztok, ODER, Jure, CIZELJ, Leon. Double-sided cooling of heated slab : conjugate heat transfer DNS. International journal of heat and mass transfer, nov. 2013, vol. 66, str. 781-790.

TISELJ, Iztok. Tracking of large-scale structures in turbulent channel with direct numerical simulation of low Prandtl number passive scalar. Physics of fluids, 2014, vol. 26, no. 12, str. 125111-1-125111-17.

MIKUŽ, Blaž, TISELJ, Iztok. URANS prediction of flow fluctuations in rod bundle with split-type spacer grid. International journal of heat and fluid flow, ISSN 0142-727X. [Print ed.], 2017, vol. 64, str. 10-22.

HENRY, Romain, TISELJ, Iztok, SNOJ, Luka. CFD/Monte-Carlo neutron transport coupling scheme, application to TRIGA reactor. Annals of Nuclear Energy, ISSN 0306-4549. [Print ed.], 2017, vol. 110, str. 36-47.

ODER, Jure, SHAMS, Afaque, CIZELJ, Leon, TISELJ, Iztok. Direct numerical simulation of low-Prandtl fluid flow over a confined backward facing step. International journal of heat and mass transfer, ISSN 0017-9310. [Print ed.], 2019, vol. 142, str. 118436-1-118436-20.

FLAGEUL, Cedric, TISELJ, Iztok, BENHAMADOUCHE, Sofiane, FERRAND, Martin. A correlation for the discontinuity of the temperature variance dissipation rate at the fluid-solid interface in turbulent channel flows. Flow, turbulence and combustion, ISSN 1386-6184, 2019, vol. 103, no. 1, str. 175-201.


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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