Piotr Darnowski
Piotr Darnowski
Warsaw University of Technology, Institute of Heat Engineering, Power Division
Verified email at itc.pw.edu.pl
TitleCited byYear
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
92016
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
72015
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
52017
Minor Actinides impact on basic safety parameters of medium-sized sodium-cooled fast reactor
P Darnowski, N Uzunow
Nukleonika 60 (1), 171-179, 2015
32015
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
32014
Solid-fuel rocket engines: layered composite materials manufacturing and thermal diffusivity measurements
A Dominiak, M Rąpała, R Domański, B Bartkowiak, P Darnowski
High Temperature Materials and Processes 33 (2), 171-177, 2014
22014
MOX and UOX fuel melt margin for European pressurized reactor
PO Stręciwilk, P Darnowski, A Dominiak, R Domański
Journal of Power Technologies 93 (3), 169-177, 2013
22013
Analysis of the BEAVRS PWR Benchmark using SCALE and PARCS
P Darnowski, M Pawluczyk
Nukleonika 64 (3), 87-96, 2019
12019
Monte Carlo Simulations of the 1000 MWth SFR OECD/NEA Benchmark with SERPENT Code
P Darnowski, A Mikołajczak
16TH INTERNATIONAL CONFERENCE OF NUMERICAL ANALYSIS AND APPLIED MATHEMATICS …, 2018
12018
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
12018
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
12017
Coordination number for random distribution of parallel fibres
P Darnowski, P Furmański, R Domański
Archives of Thermodynamics 38 (1), 3-26, 2017
12017
Neutronic analysis of modified BN-600 fast reactor core with minor actinides
P Darnowski
Instytut Techniki Cieplnej, 2013
12013
Zachowanie substancji promieniotwórczych w obiegu pierwotnym reaktora jądrowego typu PWR podczas ciężkiej awarii
P Darnowski, M Stępień, M Włostowski, K Świrski
Bezpieczeństwo Jądrowe i Ochrona Radiologiczna - Biuletyn PAA 2019 (3/4), 22-32, 2019
2019
Zintegrowane analizy awarii ciężkich na przykładzie eksperymentu Phebus FPT-1 z wykorzystaniem kodu obliczeniowego MELCOR 2.2 - Część 2: Symulacje
P Darnowski, M Włostowski
Bezpieczeństwo Jądrowe i Ochrona Radiologiczna - Biuletyn PAA 2019 (3/4), 12-21, 2019
2019
Thorium application in the medium-sized sodium-cooled fast reactor
ERSA Kumar, P Darnowski, MK Pancholi, A Dzido
E3S Web of Conferences 137, 01030, 2019
2019
Study of the Thorium Application in the Medium-Sized Sodium-Cooled Fast Reactor with Oxide Fuel
ERSA Kumar, MK Pancholi, P Darnowski, A Mikołajczak
RDPE 2019, 2019
2019
MELCOR Simulations of the SBO in Gen III PWR with EVMR
P Darnowski, P Mazgaj, E Skrzypek
NENE-2019 The 28th International Conference Nuclear Energy for New Europe …, 2019
2019
Uncertainty Analysis of the Hydrogen Production in the PHEBUS FPT-1 Experiment
P Mazgaj, P Darnowski, G Niewiński
NENE-2019 - The 28th International Conference Nuclear Energy for New Europe, 2019
2019
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
2019
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