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Piotr Darnowski
Piotr Darnowski
Warsaw University of Technology, Institute of Heat Engineering, Power Division
Zweryfikowany adres z itc.pw.edu.pl
Tytuł
Cytowane przez
Cytowane przez
Rok
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
182018
Analysis of the BEAVRS PWR Benchmark using SCALE and PARCS
P Darnowski, M Pawluczyk
Nukleonika 64 (3), 87-96, 2019
162019
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
162017
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
152022
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
152016
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
152015
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
112020
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
92020
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
82022
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
82021
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
82021
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
82017
Minor Actinides impact on basic safety parameters of medium-sized sodium-cooled fast reactor
P Darnowski, N Uzunow
Nukleonika 60 (1), 171-179, 2015
82015
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
72014
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
62021
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
62021
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
62021
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
52022
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
52021
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
52019
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