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1
Spent fuel characterization analysis using various nuclear data libraries by Dušan Čalič, Marjan Kromar
Published 2022-09-01
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2
Determination of the spent fuel decay heat with the VERA core simulator by Marjan Kromar, Andrew T. Godfrey
Published 2022-12-01
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3
Determination of neutron flux redistribution factors for a typical pressurized water reactor ex-core measurements using Monte Carlo technique by Tanja Goričanec, Tanja Goričanec, Bor Kos, Klemen Ambrožič, Andrej Trkov, Luka Snoj, Luka Snoj, Marjan Kromar, Marjan Kromar
Published 2023-02-01
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4
Analysis of fluctuations in ex-core neutron detector signal in Krško NPP during an earthquake by Tanja Goričanec, Andrej Kavčič, Marjan Kromar, Luka Snoj
Published 2024-02-01
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5
An overview of power reactor kinetics and control in load-following operation modes by Gašper Žerovnik, Dušan Čalič, Samo Gerkšič, Marjan Kromar, Jan Malec, Anže Mihelčič, Andrej Trkov, Luka Snoj
Published 2023-02-01
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