| Simulations of the AP1000-Based Reactor Core with SERPENT Computer Code P Darnowski, P Ignaczak, P Obrębski, M Stępień, G Niewiński Archive of Mechanical Engineering 65 (3), 295-325, 2018 | 22 | 2018 |
| Analysis of the BEAVRS PWR Benchmark using SCALE and PARCS P Darnowski, M Pawluczyk Nukleonika 64 (3), 87-96, 2019 | 19 | 2019 |
| Investigation of the recriticality potential during reflooding phase of Fukushima Daiichi Unit-3 accident P Darnowski, K Potapczyk, K Świrski Annals of Nuclear Energy 99, 495-509, 2017 | 18 | 2017 |
| Demonstration of the E-BEPU methodology for SL-LOCA in a Gen-III PWR reactor P Mazgaj, P Darnowski, A Kaszko, J Hortal, M Dusic, R Mendizábal, ... Reliability Engineering & System Safety 226, 108707, 2022 | 16 | 2022 |
| Study of the material release during PHÉBUS FPT-1 bundle phase with MELCOR 2.2 P Darnowski, M Włostowski, M Stępień, G Niewiński Annals of Nuclear Energy 148 (2020), 107700, 2020 | 16 | 2020 |
| Total loss of AC power analysis for EPR reactor P Darnowski, E Skrzypek, P Mazgaj, K Świrski, P Gandrille Nuclear Engineering and Design 289 (August 2015), 8-18, 2015 | 16 | 2015 |
| Loss of coolant accident in pressurized water reactor. Prediction of a 6-inch cold leg break with Relap5 and Cathare 2 M Pawluczyk, P Mazgaj, S Gurgacz, M Gatkowski, P Darnowski Procedia Engineering 157, 333-340, 2016 | 15 | 2016 |
| Uncertainty and Sensitivity Analysis of the In-Vessel Hydrogen Generation for Gen-III PWR and Phebus FPT-1 with MELCOR 2.2 P Darnowski, P Mazgaj, M Włostowski Energies 14 (16), 4884, 2021 | 11 | 2021 |
| The development of a novel adaptive genetic algorithm for the optimization of fuel cycle length W Kubiński, P Darnowski, K Chęć Annals of Nuclear Energy 155 (2021), 108153, 2021 | 11 | 2021 |
| Minor Actinides impact on basic safety parameters of medium-sized sodium-cooled fast reactor P Darnowski, N Uzunow Nukleonika 60 (1), 171-179, 2015 | 11 | 2015 |
| Neutronic performance of a thorium based mixed oxide fuel in a burner sodium-cooled fast reactor ERSA Kumar, MK Pancholi, P Darnowski, A Dzido Energy, 118744, 2020 | 10 | 2020 |
| 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 | 9 | 2022 |
| Preliminary Analysis of an Aged RPV Subjected to Station Blackout R Lo Frano, SA Cancemi, P Darnowski, R Ciolini, S Paci Energies 14 (15), 4394, 2021 | 9 | 2021 |
| Monte Carlo Analysis of the Battery-Type High Temperature Gas Cooled Reactor M Grodzki, P Darnowski, G Niewiński Archives of Thermodynamics 38 (4), 209–227, 2017 | 9 | 2017 |
| Comparison of simple design of sodium and lead cooled fast reactor cores P Mazgaj, P Darnowski, S Gurgacz, M Lipka, K Dziubanii Journal of Power Technologies 94 (5), 16-26, 2014 | 8 | 2014 |
| Optimization of the loading pattern of the PWR core using genetic algorithms and multi-purpose fitness function W Kubiński, P Darnowski, K Chęć Nukleonika 66 (4), 147-151, 2021 | 7 | 2021 |
| Nuclear process heat application options: Highlights from the European GEMINI+ project MA Fütterer, R Pabarcius, S Hübner, L Pieńkowski, W Brudek, ... Nuclear Engineering and Design 396 (September 2022), 111879, 2022 | 6 | 2022 |
| Global uncertainty and sensitivity analysis of MELCOR and TRACE critical flow models against MARVIKEN tests M Spirzewski, P Domitr, P Darnowski Nuclear Engineering and Design 378 (July 2021), 111150, 2021 | 6 | 2021 |
| Application of genetic algorithms in optimization of SFR nuclear reactor design W Żurkowski, P Sawicki, W Kubiński, P Darnowski Nukleonika 66 (4), 139-145, 2021 | 5 | 2021 |
| The Assessment of Critical Flow Models of MELCOR2.2 and TRACE V5.0 Patch 5 Against Marviken Critical Flow Tests P Domitr, P Darnowski, M Spirzewski 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2019 | 5 | 2019 |
Piotr MazgajWarsaw University of Technology, Institute of Heat Engineering, Power DivisionZweryfikowany adres z pw.edu.pl
