Piotr Darnowski
Piotr Darnowski
Warsaw University of Technology, Institute of Heat Engineering, Power Division
Verified email at itc.pw.edu.pl
Title
Cited by
Cited by
Year
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
82015
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
62017
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
Analysis of the BEAVRS PWR Benchmark using SCALE and PARCS
P Darnowski, M Pawluczyk
Nukleonika 64 (3), 87-96, 2019
22019
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
22018
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
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
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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