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





Liczba pozycji spełniających powyższe kryteria selekcji: 26, z ogólnej liczby 26 publikacji Autora


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