Wykaz publikacji wybranego autora

Mateusz Malicki, mgr inż.

doktorant

Wydział Energetyki i Paliw
WEiP-kej, * Katedra Energetyki Jądrowej


Identyfikatory Autora

ORCID: brak

ResearcherID: brak

Scopus: 57191957505




1
  • Analysis of melcor code utility for safety assessment of high-temperature reactors
2
  • Analysis of melcor code utility for safety assessment of high-temperature reactors
3
  • Attempt to validate MELCOR model of typical PWR by simulation of SB-LOCA accident
4
  • Comparison of nuscale SMR modelling and steady state parameters in RELAP/SCDAPSIM and MELCOR codes
5
  • Development of MELCOR thermal hydraulic model of AP1000 and its verification for a DECL break
6
  • Eastern-design VVER nuclear reactors in European Union
7
  • Eastern-design VVER nuclear reactors in European Union
8
  • High-temperature nuclear reactor power plant cycle for hydrogen and electricity production – numerical analysis
9
  • High-temperature nuclear reactor power plant cycle for hydrogen and electricity production – numerical analysis
10
  • Influence of main variables modifications on accident transient based on AP1000 like MELCOR model
11
  • Influence of main variables modifications on accident transient based on AP1000-like MELCOR model
12
  • Influence of power profile on LB-LOCA simulation of typical PWR calculated in MELCOR
13
  • Neutron flux evolution in accelerator driven system with pulsed neutron source
14
  • Neutronic analysis of mixed thorium-uranium fuel bundle for CANDU reactors
15
  • Neutronic analysis of mixed thorium-uranium fuel bundle for CANDU reactors
16
  • On the physical explanation of lethargy use in nuclear reactor physics. Alternative energy binning technique
17
  • Safety analysis of coolant needed supply for spent fuel pool in light of Fukushima accident
18
  • Safety analysis of coolant needed supply for Spent Fuel Pool in light of Fukushima Accident
19
  • Simulation of SB-LOCA of typical PWR with MELCOR code
20
  • Validation of VHTRC calculation benchmark of critical experiment using the MCB code
21
  • Validation of VHTRC calculation benchmark of critical experiment using the MCB code