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7 results

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1. Neutronic and thermal-hydraulics coupling for simulations of the TRIGA Mark II reactor
Romain Henry, 2017, doctoral dissertation

Keywords: nuclear physics, nuclear research reactors, TRIGA reactor, Monte-Carlo neutron transport, fluid dynamics, thermodynamics, simulations
Full text (file, 10,43 MB)

2. Use of hybrid methods for neutron transport and sensitivity analysis
Bor Kos, 2020, doctoral dissertation

Keywords: hybrid transport, variance reduction, nuclear data, sensitivity, uncertainty, shielding, fusion, fission, total Monte Carlo (TMC), MCNP, ADVANTG, Denovo, SUSD3D, SANDY
Full text (file, 22,24 MB)

3. Molecular insights into the oxygen-sensing pathway and erythropoietin expression regulation in erythropoiesis
Jana Tomc, Nataša Debeljak, 2021, review article

Keywords: erythropoiesis, erythropoietin, molecular mechanisms, oxygen-sensing pathway, hypoxia-inducible factor, post-translational modifications, protein interactions, nuclear transport, transcriptional regulation
Full text (file, 670,39 KB) This document has more files! More...

4. Feasibility study for design and utilization of a cold neutron irradiation facility at the JSI TRIGA reactor
Diego Martín Cuellar Fernandez, 2023, master's thesis

Keywords: Neutron transport, Cold neutrons, Nuclear reactions, Neutron scattering, Neutron absorption, Cross sections.
Full text (file, 4,11 MB)

5. Determination of neutron flux redistribution factors for a typical pressurized water reactor ex-core measurements using Monte Carlo technique
Tanja Goričanec, Bor Kos, Klemen Ambrožič, Andrej Trkov, Luka Snoj, Marjan Kromar, 2023, original scientific article

Keywords: MCNP, ADVANTG, pressurized water reactor, Monte Carlo neutron transport, control rod, neutron flux redistribution factor, rod insertion, Krško nuclear power plant
Full text (file, 63,84 MB) This document has more files! More...

6. Generation and validation of a new WIMS-D library based on ENDF/B-VIII.0
Jan Malec, Oscar Cabellos, Marjan Kromar, Andrej Trkov, 2025, original scientific article

Keywords: deterministic transport, depletion calculations, nuclear data, WIMS-D library
Full text (file, 1,69 MB) This document has more files! More...

7. Sensitivity analysis of the LMT-006 benchmark experimentswith OpenMC
Nour Mohamed Ali Hussein Elsaied, 2025, master's thesis

Keywords: Neutron transport, Nuclear data, Verification & Validation, Sensitivity analysis, Cross section perturbation, Fission spectrum, Neutron spectrum hardness
Full text (file, 2,17 MB)

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