Wykaz publikacji wybranego autora

Ludwik Pieńkowski, dr hab., prof. AGH

profesor nadzwyczajny

Wydział Energetyki i Paliw
WEiP-kejr, Katedra Energetyki Jądrowej i Radiochemii


  • 2018

    [dyscyplina 1] dziedzina nauk inżynieryjno-technicznych / inżynieria środowiska, górnictwo i energetyka


Identyfikatory Autora Informacje o Autorze w systemach zewnętrznych

ORCID: 0000-0002-8337-3675 orcid iD

ResearcherID: brak

Scopus: 7003600177

PBN: 5e70922c878c28a047391275

OPI Nauka Polska

System Informacyjny AGH (SkOs)





Liczba pozycji spełniających powyższe kryteria selekcji: 27, z ogólnej liczby 27 publikacji Autora


1
  • Analysis of loss of coolant accident without ECCS and DHRS in an integral pressurized water reactor using RELAP/SCDAPSIM
2
  • Attempt to validate MELCOR model of typical PWR by simulation of SB-LOCA accident
3
  • CCGT and small nuclear SMR hybrids system for flexible energy generation
4
  • CCGT and small nuclear SMR hybrids system for flexible energy generation
5
  • Ceria promotion over Ni-containing hydrotalcite-derived catalysts for $CO_{2}$ methane reforming
6
  • Ceria promotion over Ni-containing hydrotalcite-derived catalysts for ${CO_2}$ methane reforming
7
  • Comparison of nuscale SMR modelling and steady state parameters in RELAP/SCDAPSIM and MELCOR codes
8
  • Development of MELCOR thermal hydraulic model of AP1000 and its verification for a DECL break
9
  • Dialog \emph {pro} i \emph {contra}
10
  • High-temperature nuclear reactor power plant cycle for hydrogen and electricity production – numerical analysis
11
  • High-temperature nuclear reactor power plant cycle for hydrogen and electricity production – numerical analysis
12
  • Hydrogen production using high temperature nuclear reactors: efficiency analysis of a combined cycle
13
  • Hydrogen production using high temperature nuclear reactors: efficiency analysis of a combined cycle
14
  • Influence of main variables modifications on accident transient based on AP1000 like MELCOR model
15
  • Influence of main variables modifications on accident transient based on AP1000-like MELCOR model
16
  • Influence of power profile on LB-LOCA simulation of typical PWR calculated in MELCOR
17
  • Jądrowa kogeneracja
18
  • Nuclear power in Poland – standardization and safety
19
20
  • Polish Workshop on the Acceleration and Applications of Heavy Ions
21
  • Realia energetyki jądrowej w Polsce
22
  • Realia energetyki jądrowej w Polsce
23
  • Realia i mity energetyki jądrowej
24
  • Simulation of SB-LOCA of typical PWR with MELCOR code
25
  • Small reactors – new chapter in nuclear energy