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Exploring the Factors Influencing Expansion of Nuclear Energy in Croatia

Energies (Basel), 2021-12, Vol.14 (23), p.8022

2021

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Dynamics for Sustainable Nuclear Buildup Based on LWR and FBR Technologies and Its Impact on CO2 Emission Reduction

Energies (Basel), 2020-01, Vol.13 (1), p.134

2020

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Promises and limitations of nuclear fission energy in combating climate change

Energy policy, 2018-09, Vol.120, p.94-99

2018

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PWR Containment Shielding Calculations with SCALE6.1 Using Hybrid Deterministic-Stochastic Methodology

Science and Technology of Nuclear Installations, 2016-01, Vol.2016, p.1-30

2016

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Modeling of the ORNL PCA Benchmark Using SCALE6.0 Hybrid Deterministic-Stochastic Methodology

Science and Technology of Nuclear Installations, 2013-01, Vol.2013, p.1-9

2013

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Radioactive waste management in Croatia - public opinion, legal framework, and policy

Energy policy, 2020-11, Vol.146, p.111804, Article 111804

2020

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Modelling of Heat Transfer Phenomena for Vertical and Horizontal Configurations of In-Pool Condensers and Comparison with Experimental Findings

Science and technology of nuclear installations, 2010-01, Vol.2010, p.1-16

2010

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Selected Papers from TopSafe 2008: Safety at Nuclear Installations

Science and technology of nuclear installations, 2010-01, Vol.2010, p.1-2

2010

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Dose rates modeling of pressurized water reactor primary loop components with SCALE6.0

Nuclear engineering and design, 2015-03, Vol.283, p.175-192

2015

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Experimental Characterization of a Passive Emergency Heat Removal System for a GenIII + Reactor

Science and technology of nuclear installations, 2010, Vol.2010, p.1-12

2010

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Investigation of a Coolant Mixing Phenomena within the Reactor Pressure Vessel of a VVER-1000 Reactor with Different Simulation Tools

Science and technology of nuclear installations, 2010-01, Vol.2010, p.1-14

2010

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Machine Learning of the Reactor Core Loading Pattern Critical Parameters

Science and technology of nuclear installations, 2008, Vol.2008, p.1-6

2008

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Boration modeling of the PWR biological shield using SCALE6.1 hybrid shielding methodology

Annals of nuclear energy, 2015-11, Vol.85, p.979-994

2015

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CATHARE Assessment of PACTEL LOCA Experiments with Accident Management

Science and technology of nuclear installations, 2010-01, Vol.2010, p.1-8

2010

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The potential of fission nuclear power in resolving global climate change under the constraints of nuclear fuel resources and once-through fuel cycles

Energy policy, 2010-11, Vol.38 (11), p.6793-6803

2010

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Lattice codes pin power prediction comparison : Selected and expanded papers from International Conference Nuclear Energy for New Europe 2010, Portoroz, Slovenia, September 6-9, 2010

Nuclear engineering and design, 2012, Vol.246, p.27-40

2012

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

Energija, 2022-07, Vol.62 (1-4), p.3-18

2022

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Support vector regression model for the estimation of γ-ray buildup factors for multi-layer shields

Annals of nuclear energy, 2007-12, Vol.34 (12), p.939-952

2007

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Characterization of Fast Neutron Transmission Through an Iron Shield

Energija, 2023-07, Vol.72 (2), p.8-14

2023

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Lattice codes pin power prediction comparison

Nuclear engineering and design, 2012-05, Vol.246, p.27-40

2012

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ZERO ELECTRIC ENERGY ISLAND CONCEPT IN CROATIA – PRELIMINARY STUDY FOR THE ISLAND OF VIS

Energija, 2022-09, Vol.58 (5), p.480-493

2022

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Monte Carlo Codes for Neutron Buildup Factors

Energija, 2022-07, Vol.62 (1-4), p.171-179

2022

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

Energija, 2022-07, Vol.62 (1-4), p.180-188

2022

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PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes

Energija, 2022-07, Vol.68 (2-3), p.171-183

2022

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I2S-LWR Activation Analysis of Heat Exchangers Using Hybrid Shielding Methodology With SCALE6.1

Energija, 2022-06, Vol.65 (1-2), p.138-150

2022

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Exploring the Factors Influencing Expansion of Nuclear Energy in Croatia

Dynamics for Sustainable Nuclear Buildup Based on LWR and FBR Technologies and Its Impact on CO2 Emission Reduction

Promises and limitations of nuclear fission energy in combating climate change

PWR Containment Shielding Calculations with SCALE6.1 Using Hybrid Deterministic-Stochastic Methodology

Modeling of the ORNL PCA Benchmark Using SCALE6.0 Hybrid Deterministic-Stochastic Methodology

Radioactive waste management in Croatia - public opinion, legal framework, and policy

Modelling of Heat Transfer Phenomena for Vertical and Horizontal Configurations of In-Pool Condensers and Comparison with Experimental Findings

Selected Papers from TopSafe 2008: Safety at Nuclear Installations

Dose rates modeling of pressurized water reactor primary loop components with SCALE6.0

Experimental Characterization of a Passive Emergency Heat Removal System for a GenIII + Reactor

Investigation of a Coolant Mixing Phenomena within the Reactor Pressure Vessel of a VVER-1000 Reactor with Different Simulation Tools

Machine Learning of the Reactor Core Loading Pattern Critical Parameters

Boration modeling of the PWR biological shield using SCALE6.1 hybrid shielding methodology

CATHARE Assessment of PACTEL LOCA Experiments with Accident Management

The potential of fission nuclear power in resolving global climate change under the constraints of nuclear fuel resources and once-through fuel cycles

Lattice codes pin power prediction comparison : Selected and expanded papers from International Conference Nuclear Energy for New Europe 2010, Portoroz, Slovenia, September 6-9, 2010

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

Support vector regression model for the estimation of γ-ray buildup factors for multi-layer shields

Characterization of Fast Neutron Transmission Through an Iron Shield

Lattice codes pin power prediction comparison

ZERO ELECTRIC ENERGY ISLAND CONCEPT IN CROATIA – PRELIMINARY STUDY FOR THE ISLAND OF VIS

Monte Carlo Codes for Neutron Buildup Factors

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

PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes

I2S-LWR Activation Analysis of Heat Exchangers Using Hybrid Shielding Methodology With SCALE6.1

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