Status of computational fluid dynamics for in-vessel retention: Challenges and achievements A Shams, D Dovizio, K Zwijsen, C Le Guennic, L Saas, R Le Tellier, ... Annals of Nuclear Energy 135, 107004, 2020 | 19 | 2020 |
On the treatment of plane fusion front in lumped parameter thermal models with convection R Le Tellier, E Skrzypek, L Saas Applied Thermal Engineering 120, 314-326, 2017 | 15 | 2017 |
Total loss of AC power analysis for EPR reactor P Darnowski, E Skrzypek, P Mazgaj, K Świrski, P Gandrille Nuclear Engineering and Design 289, 8-18, 2015 | 15 | 2015 |
Analysis of in-vessel corium pool behaviour using CFD tools C Le Guennic, E Skrzypek, L Vyskocil, M Skrzypek, A Shams, L Saas Proceedings of ERMSAR-2017 conference, Warsaw (Poland), 2017 | 10 | 2017 |
Pre-conceptual design of the research high-temperature gas-cooled reactor TeResa for non-electrical applications E Skrzypek, D Muszyński, M Skrzypek, P Darnowski, J Malesa, ... Energies 15 (6), 2084, 2022 | 8 | 2022 |
Rayleigh-Bénard and Bénard-Marangoni convection in a thin metallic layer on top of corium pool L Saas, R Le Tellier, E Skrzypek The 8th European Review Meeting on Severe Accident Research-ERMSAR-2017 …, 2017 | 5 | 2017 |
Study on the DLOFC Accident of the GEMINI+ Conceptual Design of HTGR Reactor with MELCOR and SPECTRA M Skrzypek, E Skrzypek, M Stempniewicz, J Malesa Journal of Physics: Conference Series 2048 (1), 012043, 2021 | 4 | 2021 |
Computer codes in the safety analysis for nuclear power plants. Computational capabilities of thermal-hydraulic tools, using the example of the RELAP5 code E Skrzypek, M Skrzypek Journal of Power Technologies 94 (5), 41-50, 2016 | 4 | 2016 |
Study of a thin metallic layer: Comparison of cfd and integral codes C Le Guennic, E Skrzypek, M Skrzypek, N Bakouta ERMSAR-2019 Prague, Czech Republic, 2019 | 3 | 2019 |
In vessel corium propagation sensitivity study of reactor pressure vessel rupture time with PROCOR platform. E Skrzypek, M Skrzypek, L Saas, R LeTellier Journal of Power Technologies 97 (2), 2017 | 3 | 2017 |
Advancing production of hydrogen using nuclear cycles–integration of high temperature gas-cooled reactors (HTGR) with solid oxide electrolyzers (SOE) J Kupecki, J Hercog, K Motyliński, J Malesa, D Muszyński, E Skrzypek, ... International Journal of Hydrogen Energy 53, 40-48, 2024 | 2 | 2024 |
Advancing production of hydrogen using nuclear cycles-integration of high temperature gas-cooled reactors with thermochemical water splitting cycles J Hercog, J Kupecki, B Świątkowski, P Kowalik, A Boettcher, J Malesa, ... International Journal of Hydrogen Energy 52, 1070-1083, 2024 | 2 | 2024 |
MELCOR Simulations of the SBO in Gen III PWR with EVMR P Darnowski, P Mazgaj, E Skrzypek Proceedings of the 28th International Conference Nuclear Energy for New …, 2019 | 2 | 2019 |
Analysis of air ingress scenario in GEMINI+ plant MM Stempniewicz, EAR de Geus, F Roelofs, M Skrzypek, E Skrzypek, ... Nuclear Engineering and Design 399, 112030, 2022 | 1 | 2022 |
Simulations of Large Break Loss of Coolant Accident without Safety Injection for EPR Reactor using MELCOR Computer Code P Darnowski, E Skrzypek, P Mazgaj, M Gatkowski Proceedings of the European Review Meeting on Severe Accident Research …, 2015 | 1 | 2015 |
Concept of the polish high temperature gas-cooled reactor HTGR-POLA MP Da̧browski, A Boettcher, W Brudek, J Malesa, D Muszyński, ... Nuclear Engineering and Design 424, 113197, 2024 | | 2024 |
Thermo-hydraulic Modeling of a Steel Metal Layer on Top of Corium Pool in a PWR Under Severe Accident Conditions E Skrzypek | | 2023 |
Thin metallic layer thermal-hydraulics modelling-selected aspects of the issue E Skrzypek | | 2016 |
Simulation of large break LOCA without safety injection for EPR reactor using MELCOR computer code P Darnowski, E Skrzypek, P Mazgaj, M Gatkowski, IV Session | | |
Thin Metallic Layer on the Top of the Molten Corium Pool Study, Under Severe Accident Conditions with its Impact on the Core Support Plate-CFD Software Application E Skrzypek, M Skrzypek, A Siwiec | | |