Determination of neutron flux redistribution factors for a typical pressurized water reactor ex-core measurements using Monte Carlo technique

Uniform variance method for accelerated Monte Carlo criticality calculation

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Applicability of the Krško nuclear power plant core Monte Carlo model for the determination of the neutron source term

(2021) Tanja Goričanec et al.   Nuclear Engineering and Technology

SP3-coupled global variance reduction method based on RMC code

(2021) Qing-Quan Pan et al.   Nuclear Science and Techniques

IRDFF-II: A New Neutron Metrology Library

(2020) A. Trkov et al.   NUCLEAR DATA SHEETS

Evaluation of neutron flux and fission rate distributions inside the JSI TRIGA Mark II reactor using multiple in-core fission chambers

(2018) Tanja Goričanec et al.   ANNALS OF NUCLEAR ENERGY

Rod insertion method analysis – A methodology update and comparison to boron dilution method

(2018) Vid Merljak et al.   ANNALS OF NUCLEAR ENERGY

ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data

(2018) D.A. Brown et al.   NUCLEAR DATA SHEETS

Validation of neutron flux redistribution factors in JSI TRIGA reactor due to control rod movements

(2015) Tanja Kaiba et al.   APPLIED RADIATION AND ISOTOPES

On normalization of fluxes and reaction rates in MCNP criticality calculations

(2013) Gašper Žerovnik et al.   ANNALS OF NUCLEAR ENERGY