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Marjan Kromar

Observed names: Kromar, Marjan, M Kromar, M. Kromar
ORCID: 0000-0001-8960-203X
Observed ORCID: 0000-0001-8960-203X
OpenAlex ID: A5068607447
On the estimation of nuclide inventory and decay heat: a review from the EURAD European project
2023 · Dimitri Alexandre Rochman, Francisco Álvarez-Velarde, et al. · EPJ Nuclear Sciences & Technologies · 20
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Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat
2022 · Peter Jansson, Martin Bengtsson, et al. · Nuclear Science and Engineering · 18
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Rod insertion method analysis – A methodology update and comparison to boron dilution method
2017 · Vid Merljak, Marjan Kromar, et al. · Annals of Nuclear Energy · 15
An introduction to Spent Nuclear Fuel decay heat for Light Water Reactors: a review from the NEA WPNCS
2024 · Dimitri Rochman, Alejandro Algora, et al. · EPJ Nuclear Sciences & Technologies · 14
An overview of power reactor kinetics and control in load-following operation modes
2023 · Gašper Žerovnik, Dušan Čalič, et al. · Frontiers in Energy Research · 13
Advanced methods in teaching reactor physics
2010 · Luka Snoj, Marjan Kromar, et al. · Nuclear Engineering and Design · 13
Spent fuel characterization analysis using various nuclear data libraries
2022 · Dušan Čalič, Marjan Kromar · Nuclear Engineering and Technology · 10
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A perspective of using nuclear power as a dispatchable power source for covering the daily fluctuations of solar power
2023 · Samo Gerkšič, Damir Vrančić, et al. · Energy · 9
Determination of neutron flux redistribution factors for a typical pressurized water reactor ex-core measurements using Monte Carlo technique
2023 · Tanja Goričanec, Bor Kos, et al. · Frontiers in Energy Research · 9
Verification of kinetic capabilities of the GNOMER neutron diffusion code
2017 · Vid Merljak, Marjan Kromar, et al. · Annals of Nuclear Energy · 6
Determination of the NPP Krško spent fuel decay heat
2017 · Marjan Kromar, Bojan Kurinčič · AIP conference proceedings · 6
Applicability of the Krško nuclear power plant core Monte Carlo model for the determination of the neutron source term
2021 · Tanja Goričanec, Žiga Štancar, et al. · Nuclear Engineering and Technology · 5
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Determination of the spent fuel decay heat with the VERA core simulator
2022 · Marjan Kromar, Andrew T. Godfrey · Frontiers in Energy Research · 4
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Use of Effective Diffusion Homogenization method with the Monte Carlo code for light water reactor
2016 · Dušan Ćalić, Andrej Trkov, et al. · Annals of Nuclear Energy · 4
DRAGON and CORD-2 nuclear calculation of the NPP Krško fuel assembly
2011 · Marjan Kromar, Bojan Kurinčič · Nuclear Engineering and Design · 4
Boundary Condition Modeling Effect on the Spent Fuel Characterization and Final Decay Heat Prediction From a Pwr Assembly
2021 · Augusto Hernandez-Solis, Klemen Ambrožič, et al. · EPJ Web of Conferences · 3
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Generation and validation of a new WIMS-D library based on ENDF/B-VIII.0
2024 · Jan Malec, Oscar Cabellos, et al. · Annals of Nuclear Energy · 2
Comparison of the ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 Libraries for the Nuclear Design Calculations of the Nuclear Power Plant Krško With the CORD-2 System
2021 · Marjan Kromar, Bojan Kurinčič · Journal of Nuclear Engineering and Radiation Science · 2
Predicting Ex-core Detector Response in a PWR with Monte Carlo Neutron Transport Methods
2020 · Tanja Goričanec, Domen Kotnik, et al. · EPJ Web of Conferences · 2
Digital meter of reactivity for use during zero-power physics tests at the Krško NPP
2012 · Igor Lengar, Andrej Trkov, et al. · University of Maribor digital library (University of Maribor) · 2
Impact of thicker cladding on the nuclear parameters of the NPP Krško fuel
2010 · Marjan Kromar, Bojan Kurinčič · Nuclear Engineering and Design · 2
Analysis of fluctuations in ex-core neutron detector signal in Krško NPP during an earthquake
2023 · Tanja Goričanec, Andrej Kavčič, et al. · Nuclear Engineering and Technology · 1
Validation of the CORD-2 System for the NPP Krško Nuclear Core Design Calculations
2022 · Marjan Kromar, Bojan Kurinčič · Journal of Energy - Energija · 1
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Sensitivity and Uncertainty Analysis of PWR Spent Fuel Observables to Operational and Model Parameters
2022 · P. Romojaro, K. Ambrožič, et al. · International Conference on Physics of Reactors (PHYSOR) · 1
Corrigendum to: The 0E2 benchmarks for PWR UO
2026 · Dimitri A. Rochman, Francisco Alvarez-Velarde, et al. · Springer Link (Chiba Institute of Technology)
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Works count: 56
Citation count: 166
H-index: 9
I10-index: 7
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