Wykaz publikacji wybranego autora

Katarzyna Skolik, mgr inż.

doktorant

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


Identyfikatory Autora

ORCID: brak

ResearcherID: brak

Scopus: 57193382320



Statystyka obejmuje publikacje afiliowane AGH od 2008 roku włącznie

typ publikacji
rocznikl. publ.książkifragm.referatyartykułypatentymapyred. czas.inne
ogółem261511
202111
2019514
201833
201755
2016633
2015633
język publikacji
rocznikrazempolskojęzyczneanglojęzycznepozostałe języki
ogółem26125
202111
201955
201833
2017514
201666
201566
kraj wydania
rocznikrazempubl. krajowepubl. zagraniczne
ogółem261610
202111
201955
2018321
201755
2016633
201566
Lista Filadelfijska
rocznikrazempubl. z LFpubl. pozostałe
ogółem26224
202111
2019514
201833
201755
201666
201566
punktacja MNiSW
rocznikrazempubl. z pkt. MNiSWpubl. pozostałe
ogółem261313
202111
201955
2018312
201755
2016633
2015633
publikacje recenzowane
rocznikrazempubl. recenzowanepubl. nierecenzowane
ogółem261313
202111
201955
2018312
201755
2016633
2015633



1
  • Analysis of loss of coolant accident without ECCS and DHRS in an integral pressurized water reactor using RELAP/SCDAPSIM
2
  • Analysis of melcor code utility for safety assessment of high-temperature reactors
3
  • Analysis of melcor code utility for safety assessment of high-temperature reactors
4
  • Assessment of RELAP/SCDAPSIM for turbine trip transient in NuScale-SMR
5
  • Attempt to validate MELCOR model of typical PWR by simulation of SB-LOCA accident
6
  • CCGT and small nuclear SMR hybrids system for flexible energy generation
7
  • CCGT and small nuclear SMR hybrids system for flexible energy generation
8
  • Comparison of nuscale SMR modelling and steady state parameters in RELAP/SCDAPSIM and MELCOR codes
9
  • Control rods shadow effect in the VENUS-F core
10
  • Control rods shadow effect in the VENUS-F core
11
  • Development of MELCOR thermal hydraulic model of AP1000 and its verification for a DECL break
12
  • High-temperature nuclear reactor power plant cycle for hydrogen and electricity production – numerical analysis
13
  • High-temperature nuclear reactor power plant cycle for hydrogen and electricity production – numerical analysis
14
  • Independent replica method for statistical error assessment in Monte Carlo burn-up calculations
15
  • Influence of FIMA burnup on actinides concentrations in PWR reactors
16
  • Influence of FIMA burnup on actinides concentrations in PWR reactors
17
  • Influence of power profile on LB-LOCA simulation of typical PWR calculated in MELCOR
18
  • LOCA-type scenario simulation for NuScale-SMR with RELAP/SCDAPSIM/MOD3.4
19
  • Neutronic analysis of mixed thorium-uranium fuel bundle for CANDU reactors
20
  • Neutronic analysis of mixed thorium-uranium fuel bundle for CANDU reactors
21
  • Numerical design of the seed-blanket unit for the thorium nuclear fuel cycle
22
  • Numerical design of the seed-blanket unit for the thorium nuclear fuel cycle
23
  • Safety analysis of coolant needed supply for spent fuel pool in light of Fukushima accident
24
  • Safety analysis of coolant needed supply for Spent Fuel Pool in light of Fukushima Accident
25
  • Simulation of SB-LOCA of typical PWR with MELCOR code