Start-up, operation and thermal-hydraulic analysis of a self-propelling supercritical CO2 heat removal system coupled to a pressurized water reactor. EPJ Nuclear Sciences & Technologies, (8):34, EDP Sciences, 2022. [PUMA: oa ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie wos]
Strategic Agenda For EU Wide Nuclear Education, Training And Knowledge Management. In Leon Cizelj, and Matej Tekavčič (Eds.), 30th International Conference Nuclear Energy for New Europe (NENE 2021), 1101, Nuclear Society of Slovenia, Ljubljana, 2021. [PUMA: ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie wos] URL
Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection. Journal of nuclear engineering and radiation science, (8)4:041702, American Society of Mechanical Engineers, 2022. [PUMA: ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie wos]
Experimental investigations on heat transfer of CO2 under supercritical pressure in heated horizontal pipes. Energy, (254)A:124171, Elsevier, 2022. [PUMA: mult oa ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie wos]
Large-eddy simulation on thermal-mixing experiment at horizontal T-junction with varied flow temperature. Nuclear engineering and design, (388):111644, Elsevier, 2022. [PUMA: mult ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie wos]
Heat transfer deterioration in vertical sCO2 cooling in 3 mm tube. Energy, (254)B:124240, Elsevier, 2022. [PUMA: mult oa ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie wos]
Simulation, analysis and control of a self-propelling heat removal system using supercritical CO2 under varying boundary conditions. Energy, (247):123500, Elsevier, 2022. [PUMA: oa ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie wos]
High resolution measurements with miniature neutron scintillators in the SUR-100 zero power reactor. In A. Lyoussi, M. Carette, R. Hodák, I. Jenčič, P. Le Dû, S. Pospíšil, C. Reynard-Carette, L. Snoj, I. Stekl, and L. Vermeeren (Eds.), EPJ Web of Conferences, 253:04029, EDP Sciences, 2021. [PUMA: oa ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie wos]
A systematic approach to evaluating environmental-economic benefits of high-gravity technology for flue gas purification and municipal solid waste incineration fly ash utilization. Journal of environmental chemical engineering, (9)6:106438, Elsevier, 2021. [PUMA: ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie wos]
Experimental investigation and modelling of steam-heated supercritical CO2 compact cross-flow heat exchangers. Applied thermal engineering, (190):116352, Elsevier, 2021. [PUMA: oa ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie wos]
Heat transfer correlation for sCO2 cooling in a 2 mm tube. The journal of supercritical fluids, (173)July:105221, Elsevier, 2021. [PUMA: mult oa ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie wos]
Leak rate testing in the range of leak detection systems. Nuclear engineering and design, (372)February:111000, Elsevier, 2021. [PUMA: mult ubs_10004 ubs_10014 ubs_20004 ubs_30046 ubs_40071 unibibliografie wos]
Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products. Journal of nuclear engineering and radiation science, (6)4:041110, ASME, 2020. [PUMA: ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie wos]
Safety assessments and severe accidents, impact of external events on nuclear power plants and on mitigation strategies. EPJ Nuclear Sci. Technol., (6):39, EDP Sciences, 2020. [PUMA: oa ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie wos]
Large-Eddy Simulation of Turbulent Thermal Flow Mixing in a Vertical T-Junction Configuration. International Journal of Thermal Sciences, (150):106231, Elsevier, 2020. [PUMA: mult ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie wos]
ATHLET Erweiterungen für die Simulation von Kreisläufen mit superkritischem Kohlenstoffdioxid als Arbeitsmedium. Kerntechnik, (84)5:390-396, Carl Hanser Verlag, 2020. [PUMA: ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie wos]
Investigations on subcooled leakage flows at a through-wall crack. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), 4291-4303, Curran, Red Hook, NY, 2017. [PUMA: liste mult ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie]
3D simulation of melt/water premixing and steam explosion: evaluation of realistic loads from FCI in reactor scenarios. 2018. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie]
Raising nuclear reactor safety to a higher level - The supercritical CO2 Heat Removal System - "sCO2-HeRo". In Leon Cizelj, and Tadej Holler (Eds.), NENE 2017, 405; 1-8, Nuclear Society of Slovenia, Ljubljana, 2017. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40071 unibibliografie]
Investigation on temperature fluctuations near a geometric weld-seam model downstream of a 90° T-junction in a thermal mixing process. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), 248-262, Curran, Red Hook, NY, 2017. [PUMA: liste ubs_10004 ubs_20004 ubs_30046 ubs_40071 ubs_40072 unibibliografie]