Vol. 62 No. 1-4 (2013): Journal of Energy special issue: Papers from 9th International Conference of the Croatian Nuclear Society “Nuclear Option in Countries with Small and Medium Electricity Grids”, Zadar, 2012

Special Issue Article

• Future without Nuclear Energy; is it Feasible, is it Sensible?

  Vladimir Knapp, Dubravko Pevec

  3-18

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• Nuclear Power as an Option in Electrical Generation Planning for Small Economy and Electricity Grid

  Željko Tomšić

  19-32

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• Aging of Power Cables in Nuclear Power Plant due to Influence of Local Temperature Conditions

  Irena Jakić, Nenad Debrecin

  33-44

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• Use Of Micro-Void Content Growth Rates To Validate And Add Value To Electrical Insulation Tan-Delta Aging Testing

  David A. Horvath, Greg M. Hostetter

  45-53

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

  Vesna Benčik, Nikola Čavlina, Davor Grgić

  54-67

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• Nuclear Fuel Modelling During Power Ramp

  Federico Cantini, Martina Adorni, Francesco D’Auria

  68-80

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

  R. Gonzalez, A. Petruzzi, F. D’Auria, O. Mazzantini

  81-92

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• BETHSY 9.1b test calculation with TRACE using 3D vessel component

  Andrej Prošek, Ovidiu-Adrian Berar

  93-103

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• Risk Impact of Maintenance and Other Activities with Regard to Plant Areas

  Ivan Vrbanić, Ivica Bašić

  104-112

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• Liquid-salt-cooled Reactor Start-up with Natural Circulation

  Emilien Gros, Bojan Petrović, Davor Grgić

  113-130

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• On the Estimation and Reduction of the Frequency of the Loss of Offsite Power Event

  Hrvoje Grganić, Zdenko Šimić

  131-141

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• Validation of EOPs/FRGs Procedures Using LOHS Scenario

  Damir Konjarek, Josip Vuković, Tomislav Bajs

  142-158

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• Criticality Safety Analysis of Spent Fuel Storage Pool for NPP Mochovce using MCNP5 Code

  Ján Haščík, Gabriel Farkas, Jakub Lüley, Branislav Vrban, Róbert Hinca, Martin Petriska, Vladimír Slugeň, Jozef Lipka, Peter Urban

  159-170

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• Monte Carlo Codes for Neutron Buildup Factors

  Krešimir Trontl, Dubravko Pevec, Mario Matijević

  171-179
• 24-Month Operating Cycle Containing Gadolinium Integral Burnable Absorbers for NPP Krško

  Krešimir Trontl, Dubravko Pevec, Tomislav Belavić

  180-188

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

  Mario Matijević, Krešimir Trontl, Dubravko Pevec, Radomir Ječmenica

  189-199

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• Comparison of the SCALE, SERPENT and MCNP Criticality Safety Calculation of the NPP Krško Spent Fuel Pool

  Marjan Kromar, Bojan Kurinčič

  200-208

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• Impact of Limited Reprocessing Capacity on Nuclear Material Utilization in Advanced Fuel Cycles

  Abiodun Adeniyi, Bojan Petrović, Bo Feng, Take K. Kim

  209-220

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