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]
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]
Some observations concerning "laminarization" in heated vertical tubes. International journal of heat and mass transfer, (163)December:120101, Elsevier, 2020. [PUMA: mult ubs_10004 ubs_10006 ubs_10021 ubs_20004 ubs_20010 ubs_20019 ubs_30046 ubs_30098 ubs_30165 ubs_40072 unibibliografie wos]
Relaminarized and recovered turbulence under nonuniform body forces. Physical review fluids, (5)10:104604, American Physical Society, 2020. [PUMA: mult ubs_10004 ubs_10006 ubs_10021 ubs_20004 ubs_20010 ubs_20019 ubs_30046 ubs_30098 ubs_30165 ubs_40072 ubs_40153 unibibliografie wos]
Analysis of thermal mixing characteristics in different T-junction configurations. International Journal of Heat and Mass Transfer, (158):120019, Elsevier, 2020. [PUMA: mult ubs_10004 ubs_10021 ubs_20004 ubs_20019 ubs_30046 ubs_30165 ubs_40072 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]
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]
Investigation of leakage rates in pressure retaining piping. In Lambros Kaiktsis, Victor Janzen, and Christina Giannopapa (Eds.), Proceedings of the ASME Pressure Vessels and Piping Conference - 2017, (4 : Fluid-structure interaction):65360; 1-8, The American Society of Mechanical Engineers, New York, NY, 2017. [PUMA: liste mult ubs_10004 ubs_10014 ubs_20004 ubs_30046 ubs_30047 ubs_40071 ubs_40072 ubs_40074 unibibliografie]