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Assessment of a URANS CFD model for gravity driven flows: a comparison with OECD/PKL2 ROCOM experiments
Puragliesi, R. (2019). Assessment of a URANS CFD model for gravity driven flows: a comparison with OECD/PKL2 ROCOM experiments. Nuclear Engineering and Design. https://doi.org/10.1016/j.nucengdes.2019.110365
Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing
Puragliesi, R., Mukin, R., Clifford, I., Ferroukhi, H., & Seidl, M. (2019). Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS).
Unsteady single-phase natural-circulation flow mixing prediction using 3-D thermal-hydraulic system and CFD Codes
Bousbia Salah, A., Ceuca, S. C., Puragliesi, R., Mukin, R., Grahn, A., Kliem, S., … Austregesilo, H. (2018). Unsteady single-phase natural-circulation flow mixing prediction using 3-D thermal-hydraulic system and CFD Codes. Nuclear Technology, 203(3), 293-314. https://doi.org/10.1080/00295450.2018.1461517
On the characteristics of the flow and heat transfer in the core bypass region of a PWR
Clifford, I., Pecchia, M., Puragliesi, R., Vasiliev, A., & Ferroukhi, H. (2018). On the characteristics of the flow and heat transfer in the core bypass region of a PWR. Nuclear Engineering and Design, 330, 117-128. https://doi.org/10.1016/j.nucengdes.2018.01.039
Subchannel modeling of single rod bowing in a bundle geometry
Mukin, R., Puragliesi, R., Pecchia, M., & Seidl, M. (2018). Subchannel modeling of single rod bowing in a bundle geometry. Nuclear Engineering and Design, 340, 347-369. https://doi.org/10.1016/j.nucengdes.2018.09.032
Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study
Puragliesi, R., Mukin, R., Clifford, I., Ferroukhi, H., & Seidl, M. (2018). Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study. In Vol. 8. Proceedings of the 26th international conference on nuclear engineering (ICONE26). Computational fluid dynamics (CFD); nuclear education and public acceptance. https://doi.org/10.1115/ICONE26-81743
Thermal mixing assessment using 3-D thermal-hydraulic and CFD codes
Mukin, R., Puragliesi, R., Ceuca, S. C., Austregesilo, H., & Bousbia Salah, A. (2017). Thermal mixing assessment using 3-D thermal-hydraulic and CFD codes. Presented at the 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017). Xi'an, China.
Influence of URANS turbulence models on in-vessel flow mixing during cold leg accumulator injection
Puragliesi, R., Zerkak, O., & Pautz, A. (2016). Influence of URANS turbulence models on in-vessel flow mixing during cold leg accumulator injection. Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). Gyeongju, Korea.
Steady-state CFD simulations of an EPRTM reactor pressure vessel: a validation study based on the JULIETTE experiments
Puragliesi, R., Zhou, L., Zerkak, O., & Pautz, A. (2016). Steady-state CFD simulations of an EPRTM reactor pressure vessel: a validation study based on the JULIETTE experiments. Nuclear Engineering and Design, 300, 41-56. https://doi.org/10.1016/j.nucengdes.2015.12.025
Assessment of OpenFOAM CFD toolbox for gravity driven mixing flows in a Reactor Pressure Vessel
Puragliesi, R., Zerkak, O., Pautz, A., & Zhou, Q. (2015). Assessment of OpenFOAM CFD toolbox for gravity driven mixing flows in a Reactor Pressure Vessel. In 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society.
Assessment of CFD uRANS models for buoyancy driven mixing flows based on ROCOM experiments
Puragliesi, R., Zerkak, O., & Pautz, A. (2014). Assessment of CFD uRANS models for buoyancy driven mixing flows based on ROCOM experiments. Presented at the 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10). Okinawa, Japan.
Large eddy simulation of the differentially heated cubic cavity flow by the spectral element method
Bosshard, C., Dehbi, A., Deville, M., Leriche, E., Puragliesi, R., & Soldati, A. (2013). Large eddy simulation of the differentially heated cubic cavity flow by the spectral element method. Computers and Fluids, 86, 210-227. https://doi.org/10.1016/j.compfluid.2013.07.007
DNS of buoyancy-driven flows and Lagrangian particle tracking in a square cavity at high Rayleigh numbers
Puragliesi, R., Dehbi, A., Leriche, E., Soldati, A., & Deville, M. O. (2011). DNS of buoyancy-driven flows and Lagrangian particle tracking in a square cavity at high Rayleigh numbers. International Journal of Heat and Fluid Flow, 32(5), 915-931. https://doi.org/10.1016/j.ijheatfluidflow.2011.06.007