Skoči na glavni sadržaj

Energija , Vol. 62 No. 1-4, 2013.

  • Datum izdavanja: 31.07.2017.
  • Objavljen na Hrčku: 20.04.2018.

Sadržaj

Puni tekst

(str. 0-0)

Dubravko Pevec, Davor Gegić
Uvodnik


Liquid-salt-cooled Reactor Start-up with Natural Circulation (str. 0-0)

Emilien Gros, Bojan Petrović, Davor Grgić
Izvorni znanstveni članak


Full Core Criticality Modeling of Gas-Cooled Fast Reactor using the SCALE6.0 and MCNP5 Code Packages (str. 0-0)

Mario Matijević, Dubravko Pevec, Krešimir Trontl, Radomir Ječmenica
Izvorni znanstveni članak


Full Core Criticality Modeling of Gas-Cooled Fast Reactor using the SCALE6.0 and MCNP5 Code Packages (str. 0-0)

Mario Matijević, Dubravko Pevec, Krešimir Trontl, Radomir Ječmenica
Izvorni znanstveni članak


24-Month Operating Cycle Containing Gadolinium Integral Burnable Absorbers for NPP Krško (str. 0-0)

Krešimir Trontl, Dubravko Pevec, Tomislav Belavić
Izvorni znanstveni članak


Monte Carlo Codes for Neutron Buildup Factors (str. 0-0)

Krešimir Trontl, Dubravko Pevec, Mario Matijević Matijević
Izvorni znanstveni članak


Criticality Safety Analysis of Spent Fuel Storage Pool for NPP Mochovce using MCNP5 Code (str. 0-0)

Ján Haščík, Gabriel Farkas, Jakub Lüley, Branislav Vrban, Róbert Hinca, Martin Petriska, Vladimír Slugeň, Jozef Lipka
Izvorni znanstveni članak


Validation of EOPs/FRGs Procedures Using LOHS Scenario (str. 0-0)

Damir Konjarek, Josip Vuković, Tomislav Bajs
Izvorni znanstveni članak


On the Estimation and Reduction of the Frequency of the Loss of Offsite Power Event (str. 0-0)

Hrvoje Grganić, Zdenko Šimić
Izvorni znanstveni članak


Risk Impact of Maintenance and Other Activities with Regard to Plant Areas (str. 0-0)

Ivan Vrbanić, Ivica Bašić
Izvorni znanstveni članak


Future without Nuclear Energy; is it Feasible, is it Sensible? (str. 0-0)

Vladimir Knapp, Dubravko Pevec
Izvorni znanstveni članak


BETHSY 9.1b test calculation with TRACE using 3D vessel component (str. 0-0)

Andrej Prošek,, vidiu-Adrian Berar
Izvorni znanstveni članak


Identification of Limiting Case Between DBA and SBDBA (CL Break Area Sensitivity): A New Model for the Boron Injection System (str. 0-0)

R. Gonzales, A. Petruzzi, F. D’Auria, O. Mazzantini
Izvorni znanstveni članak


Nuclear Fuel Modelling During Power Ramp (str. 0-0)

Federico Cantini,, Martina Adorni,, Francesco D’Auria
Izvorni znanstveni članak


Analysis of Rod Withdrawal at Power (RWAP) Accident using ATHLET Mod 2.2 Cycle A and RELAP5/mod 3.3 Codes (str. 0-0)

Vesna Benčik, Nikola Čavlina, Davor Grgić
Izvorni znanstveni članak


Aging of Power Cables in Nuclear Power Plant due to Influence of Local Temperature Conditions (str. 0-0)

Irena Jakić, Nenad Debrecin
Izvorni znanstveni članak


Comparison of the SCALE, SERPENT and MCNP Criticality Safety Calculation of the NPP Krško Spent Fuel Pool (str. 0-0)

Marjan Kromar, Bojan Kurinčič
Izvorni znanstveni članak


Posjeta: 16.131 *