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Piotr Mazgaj
Piotr Mazgaj
Warsaw University of Technology, Institute of Heat Engineering, Power Division
Zweryfikowany adres z pw.edu.pl - Strona główna
Tytuł
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Cytowane przez
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Comparison of CATHARE results with the experimental results of cold leg intermediate break LOCA obtained during ROSA-2/LSTF test 7
P Mazgaj, JL Vacher, S Carnevali
EPJ N-Nuclear Sciences & Technologies 2, 1, 2016
242016
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, 8-18, 2015
152015
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
102021
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
Uncertainty analysis of the hydrogen production in the PHEBUS FPT-1 experiment
P Mazgaj, P Darnowski, G Niewinski
Proceedings of the 28th International Conference Nuclear Energy for New …, 2019
32019
Simulation and analysis of pipe and vessel blowdown phenomena using RELAP5 and TRACE
S Gurgacz, GM Niewinski, M Pawluczyk, P Mazgaj
Journal of Power Technologies 94 (5), 61-68, 2015
32015
Study of the ageing effects on the lower head failure in a PWR reactor
R Lo Frano, S Paci, P Darnowski, P Mazgaj
International Conference on Nuclear Engineering 83761, V001T01A016, 2020
22020
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
22019
Conceptual neutronic design of a 300 MWth lead fast reactor core
P Mazgaj
Unpublished M. Sc. thesis, Warsaw University of Technology, Warsaw, Poland, 2010
22010
LTO Modifications to Reduce the PTS Issue--Results of TH Calculations in the Context of the APAL European Project
M Puustinen, G Patel, P Kral, T Nikl, I Clifford, R Trewin, J Hartung, ...
American Nuclear Society, 2023
12023
et.;“Severe Accident Simulations Dedicated to the SAMG Decision-Making Tool Demonstration”
P Darnowski, P Mazgaj, I Bašić, I Vrbanić, M Skrzypek, J Malesa, A Silde, ...
29th International Conference of the Slovenian Nuclear Society Conference …, 2020
12020
EPR Medium Break LOCA Benchmarking Exercise Using RELAP5 and CATHARE
S Gurgacz, M Pawluczyk, P Mazgaj, P Darnowski, K Samul, M Skrzypek
U.S. Nuclear Regulatory Commission, 2015
12015
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
12015
Development of a measurement and reconstruction system for determining the phase distribution in a two-phase flow vertical tube using Electrical Impedance Tomography
MJ Gatkowski, T Buchner, G Niewiński, P Mazgaj
Journal of Power Technologies 94 (5), 77-84, 2015
12015
EVALUATION OF THE DETERMINISTIC BENCHMARK FOR THE ADVANCED PRESSURIZED THERMAL SHOCK ANALYSIS FOR LONG TERM OPERATION (APAL) PROJECT
K Angermeier, Y Dubyk, R Tiete, P Baranova, B Pusztai-Spisák, ...
27th International Conference on Structural Mechanics in Reactor Technology 2024, 2024
2024
CENTERED BENCHMARK ON STRUCTURAL ASSESSMENT WITHIN APAL PROJECT–RESULTS AND CONCLUSIONS
B Spisák, R Tiete, V Pistora, P Dillström, S Szávai, O Costa, DF Mora, ...
27th International Conference on Structural Mechanics in Reactor Technology 2024, 2024
2024
Impact of Selected Long-Term Operation Improvements Relevant to the Pressurized Thermal Shock in PWR
P Mazgaj, P Darnowski, R Trewin, P Kral, M Puustinen
Proceedings of the 13th International Conference of the Croatian Nuclear …, 2022
2022
MelSUA–An Open-Source MATLAB Toolbox for Sensitivity and Uncertainty Analysis with MELCOR Code
P Darnowski, P Mazgaj
13th International Conference of the Croatian Nuclear Society, Zadar …, 2022
2022
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